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EUROPEAN COMMISSION

2004 Directorate-General for Research EUR 21224Euratom - Nuclear Fission - Management of Radioactive Waste

Geological Disposal

of Radioactive Wastes

Produced by Nuclear Power

… from concept to implementation

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Contents

Preface ....................................................................................................................................................................................................................... 4

Introduction .............................................................................................................................................................................................................. 6

Themes and achievements of FP5 .............................................................................................................................................................. 11

Development of repository technology ............................................................................................................................................ 11

Long-term behaviour of wastes and containers ........................................................................................................................ 15

Groundwater and radionuclide movement around repositories ..................................................................................... 16

Safety assessment of geological disposal .................................................................................................................................... 18

Public involvement in repository programmes .......................................................................................................................... 20

Looking forward to the next five years: FP6 ............................................................................................................................... 21

Further reading ...................................................................................................................................................................................................... 23

Projects within FP5 ............................................................................................................................................................................................. 24

Repository technology .................................................................................................................................................................................. 25

Waste and container behaviour ............................................................................................................................................................. 28

Safety assessment of geological disposal ...................................................................................................................................... 32

Groundwater and radionuclide movement around repositories ..................................................................................... 35

Public involvement in repository programmes .......................................................................................................................... 38

Thematic Networks ....................................................................................................................................................................................... 39

Geological Disposal of Radioactive Wastes Produced by Nuclear Power... from concept to implementation

Preface

4

Secure electricity supply is one of the most vitalrequirements of modern life. Like all human activ-ities in the developed world, the production of our

electricity generates wastes – although less than 5% ofthe total volume of waste that society generates every year.In the European Union, we generate about 35% of ourelectricity from nuclear energy, although this has histor-ically only produced about 0.05% by volume of ourpower production wastes. Like all wastes, those from thenuclear industry have to be managed responsibly. Thescale of their potential environmental and health hazardvaries considerably, in the same way as for wastes fromother industrial activities, such as the manufacture ofchemicals. A very small proportion of radioactive wastesare extremely hazardous, compared with almost all otherindustrial wastes, and require very special provisions toensure their safe and secure management.

We also produce radioactive wastes in hospitals – fromdiagnosis and treatment of the sick; in universities – fromvital research in biology, chemistry and engineering – andfrom many types of industry. The amounts of thesewastes are much smaller than those produced by nuclearpower generation. We all derive immense benefits fromthe use of radioactivity and it is our responsibility to futuregenerations to manage the wastes we produce withboth our own and their safety in mind.

The radioactive materials that we use in everyday life areall derived, directly or indirectly, from natural radioac-tive minerals that we mine from the rocks of Earth’s crust– we live in a naturally radioactive environment. For manyyears, since the development of nuclear power in the1950s, it has been proposed that the most appropriateand natural way of dealing permanently with our radioac-tive wastes is to return them to the ground. Carefulburial in well-engineered ‘repositories’ at various depthsbelow the land surface at specially selected sites is thefavoured solution in every country that has decidedhow to handle the problem.

Burial at several hundreds of metres depth in stable rockenvironments – so-called ‘geological disposal’ – is theoption for disposal of the most hazardous radioactivewastes because it will provide permanent safety – notjust for ourselves, but for future times very much longerthan the whole of past human history. Although we cur-rently store all our wastes safely and make every effortto minimise the amount of radioactive waste that we pro-duce – and Europe is researching ways of making fur-ther reductions – it is inevitable that there will alwaysremain some wastes that have to be disposed of deepunderground.

The European Union has been researching geological dis-posal for almost 30 years and is on the verge of construct-ing its first deep repositories. This document explainsthe current status of development and highlights inparticular the achievements of the most recent Euratomwork in the Fifth Framework Programme.

Geological Disposal of Radioactive Wastes Produced by Nuclear Power ... from concept to implementation 5

Radioactive wastes from nuclear power production

The vast majority of Europe’s radioactive wastescome from nuclear power production. They fall intothree main groups:• spent fuel (SF) removed from nuclear reactors

after its useful life;• high-level waste (HLW) residues from reprocess-

ing spent fuel;• intermediate-level waste (ILW), mainly from power

reactor operations and from reprocessing.

Most reactor fuel is in the form of fuel elementscomprising pellets of ceramic uranium dioxidesealed into thin metal tubes, a number of whichare bundled together in a fuel assembly. After it hasbeen involved in the nuclear fission process, thefuel becomes intensely radioactive as a result ofthe formation of new radionuclides – mainly ‘fis-sion products’. The build-up of fission products inthe fuel reduces its efficiency. After a few years,it must be removed from the reactor and replaced.After removal from a reactor, one or more spent fuelassemblies will be sealed into a metal containerfor emplacement in a repository.

HLW originates as a liquid residue from reprocess-ing SF to extract uranium and plutonium for reuse.The liquid contains most of the radioactivity fromthe original SF. It is evaporated and the dry residuecontaining the radionuclides is melted with a muchlarger volume of inert glass-forming material toproduce a homogeneous, solid, vitreous waste form.The glass is cast in stainless steel containers thatare sealed and may be placed in a further metal con-tainer for emplacement in a repository.

ILW arises principally from reactor operations,from reprocessing SF (e.g. the metal tubes that con-tained the fuel, and other parts of fuel elements)and from decommissioning nuclear facilities. ILWis generally embedded in a matrix of cement or bitu-men inside steel or concrete drums or boxes, to pro-duce monolithic waste packages for disposal.

Apart from developing disposal options, Euratomis also researching the potential to reduce theamounts of some of thelongest-lived radionuclidesin some of these wastes.This involves chemical sep-aration of these radionu-clides followed by nucleartransmutation in particleaccelerators or nuclear reac-tors. This is a very long-termresearch programme. If itproves economically andtechnically possible toimplement, it will requirecontinued access to nuclearpower facilities and it willnot remove the requirementfor geological disposal.

Cutaway illustrations of(top) spent fuel in acopper container – about5 m long; (centre) vitrifiedHLW in a stainless steelcontainer (about 1 mlong); and (bottom) a500-litre stainless steeldrum of ILW fragmentsembedded in a cementmatrix. The pictures arenot to scale.

(Courtesy SKB)

(Courtesy BNFL)

(Courtesy BNFL)


Introduction

6

Geological disposal of radioactive wastes isbased on the principle that the deep rock envir-onment is stable and largely unaffected by

environmental change for hundreds of thousands – evenmillions of years – times that are longer than thosesince the appearance of modern humans in Africa andtheir spread across the globe, during and after the lastice age. Materials that are carefully emplaced deepunderground will be well isolated from people and theenvironment in which we live (see Box 1).

Unlike many of our other industrial waste products,radioactive wastes have a useful characteristic. Their haz-ard progressively decreases by natural processes ofradioactive decay – the very mechanism that makesradioactivity useful in the first place. As a result, manyof the radioactive isotopes (radionuclides) in our wasteswill decay to a few millionths of their original activity overthe first few thousand years after burial and they will pres-ent no future hazard. Even for the most hazardouswastes, it is estimated that more than 99.9% of theiroriginal activity will never escape from a repository.

In the far distant future, only the most long-lived (thatis, weakly decaying) and mobile radionuclides will be ableto move out into the rock by natural processes. Thesewill be diluted and dispersed by the slow movement ofgroundwaters in fractures and pores deep in the rock,and their presence will be lost among the natural vari-ability of Earth’s radiation ‘background’. Essentially, inthe far distant future, geological disposal returns asmall, residual amount of radioactivity back to nature.How can we know this?

The science and technology of geological disposal origin-ated and has grown over the last decades – about thelast 25 to 30 years in Europe (see Box 2). There has beenan energetic international effort to develop and researchthe concept. It is aimed at designing repository systemsthat will provide good containment, at identifying the righttypes of geological environment in which to locate them,and at evaluating how the radionuclides will behave overlong periods of time in the future.

All of this information is brought together in models ofthe future evolution of repositories that indicate how eachbarrier will behave (called ‘performance assessment’) overthousands of years. The overall long-term safety of a

repository is determined in part from such assessments,but also by more readily understandable analogies drawnfrom the observable behaviour of natural geological sys-tems and materials over equivalent periods of time.

Repositories must be practical and effective (see Box 3).It is essential that they can be built, operated and closedusing robust, secure technology. Most of all, scientistsand technologists must be able to show with confidencethat the radioactivity will be adequately contained andthat the disposal system will function as intended forimmensely long periods of time. They must be able toexplain convincingly why there is scientific and techni-cal confidence in safety, both today and in the far future.

This last topic is vitally important. Our society, which hasbenefited from the use of radioactivity, has to make deci-sions about how to handle the wastes it has produced.In our developed social structures, people want to beinvolved in the decision-making process so we need tobe informed and to understand the issues well.

The European Commission began funding basic R&D intogeological disposal in the early 1970s and, in 1975, start-ed to foster co-operation between European laboratoriesand institutions and help develop concepts suitable forthe wastes and the natural environments of Europe.There has been almost 30 years of Commission-support-ed work since then (see Box 4), the most recent beingwithin the Commission’s Fifth Framework Programme(FP5), a five-year, highly co-ordinated exercise that wascompleted in early 2004. During this time, many ques-tions have been raised and answered and a mature sci-entific and engineering basis has evolved.

This document summarises and puts into context theachievements of the FP5 work and evaluates the scien-tific and technical status of geological disposal today.The European Union moved to enlargement in mid-2004, with five more countries joining the nine thatalready require geological disposal facilities for nuclearpower production wastes. The first European geologicalrepositories, in Sweden and Finland, will be close to con-struction around 2010-2015 – making the EuropeanUnion and the USA the most advanced programmes inthe world. We conclude by looking forward to the sup-port and integration work that will lead up to this point,in the Sixth Framework Programme (2004-2006).


Geological disposal is based on the concept of mul-tiple barriers that work together to provide contain-ment. The barrier concept prevents deep ground-waters, present in almost all rock formations, fromrapidly leaching the wastes and transportingradioactivity away from the repository. There areboth ‘engineered barriers’ that are constructed inthe repository and ‘natural barriers’ in the sur-rounding geological environment. For disposal inhard rocks and clays, the basic engineered barri-er components are the solid waste, its container(usually metal and often multi-layered), and abuffer or backfill material (clay or cement) that fillsthe space between the container and the rock. Insalt formations, where there is no groundwater, thebuffer is replaced by crushed salt. The naturalbarrier is provided by the rocks and soils betweenthe repository and Earth’s surface.

These barriers work together to provide containmentand safety:• the container protects the waste and prevents any

water reaching it for at least several hundredyears and, in some concepts, for tens or even a

hundred thousand years – by this time, mostactivity will have decayed inside the waste matrix;

• the buffer protects the container, preventingwater from flowing around it and absorbing anymechanical disturbance that might be caused byfuture deep-earth movements (associated withmajor earthquakes) – if it is highly impermeable,such as clay, it also contains any radionuclidesthat eventually escape from the container;

• the rock and the geological environment of therepository provide stable mechanical, chemical andwater flow conditions around the engineered bar-riers for very long times, allowing them to containradionuclides for much longer than if they were leftat Earth’s surface – this ‘cocoon’ effect is due tothe very slow rate of natural processes at depth;

• the rocks, soils and waters around and above therepository slow down, or completely immobilise,and dilute and disperse any eventual releases ofactivity so that they do not cause a hazard in thenatural environment.

BOX 1: Geological repositories

8

BOX 2: The development of geological disposal

The earliest work on geological disposal originatesfrom the USA in the 1950s and 1960s, whendeep salt formations were first considered as hostrocks in which to build waste repositories. Rock saltprovides a dry environment for construction andoperation underground, easily conducts heat awayfrom the waste and is impermeable to groundwa-ter that could leach the wastes. Whilst there werelimited practical tests of the properties of such envi-ronments in the USA, the first concerted workinternationally only began in the 1970s. In 1975,the EC commissioned work to identify potentiallysuitable rock formations in Europe, producing anatlas of hard igneous and metamorphic rocks (suchas granite and gneiss), clay-rich rocks and salt for-mations that might be considered for disposal.All were identified for their stability, low permeabil-ity and good containment properties.

Since then, work has been focused around thesethree geological environments. The European coun-tries involved in disposal R&D have opted to lookat one or more of them, depending on their nation-al geological conditions. Each country has devel-oped its own active research and developmentprogramme, with elements of the work partially sup-ported by the European Commission – first actingto promote studies and then to integrate them.

Basic R&D in the field and in the laboratory hasbeen augmented by practical tests and experi-ments in specially constructed underground facil-ities that have operated for more than 20 years. Thepractical implementation of disposal has, howev-er, been slow, owing to the political and social prob-lems associated with selecting repository sites.This stems from a widespread fear of radioactivi-ty and nuclear energy, arising from their associa-tion with nuclear weapons and compounded by the

long period of innate secrecy of the nuclear indus-try, from which it is only just emerging. This atmos-phere was prevalent throughout the 1980s and1990s. Now, the first national repository pro-grammes to have overcome these setbacks (Swedenand Finland) have narrowed down to potentialrepository sites and hope to begin construction inthe next ten years.

The steps from concept to implementation will thushave taken many decades and the further opera-tional steps leading to final closure of geologicalrepositories are expected to take at least as long.

Unlike any other industrial or environmental devel-opments, geological disposal programmes evolveslowly and cautiously and will take many decadesto complete.



BOX 3: What will geological repositories look like?

The multi-barrier design of a geological repositoryreflects the types of waste to be contained and thenature of the geological environment. The twofundamental designs that are being widely devel-oped involve large, often concrete-lined caverns forlarge packages of intermediate-level wastes and nar-row tunnels or boreholes for canisters of the moreradioactive high-level wastes, which also emit heatfor some hundreds of years after they are buried. The illustrations show examples of these basicdesigns.

Cross-section of a typicalconceptual design for a

repository for large-volumecontainers of ILW usingconcrete-lined caverns

(courtesy Nagra).

Conceptual design fora spent fuel repository inhard, granitic rocks, with steel-copper containers surrounded bycompacted bentonite clay (courtesy SKB).


10

Euratom began work on geological disposal in1975. The EC shares the costs of work with EUMember States and organises work in programmesthat normally last about five years. The earliest workfocused on identifying potentially suitable geo-logical formations in Europe. Since 1979, work haseffectively fallen into two main categories: scien-tific and technical studies on the long-term safe-ty of disposal – which has involved an extremelydiverse range of projects – and experimental andengineering work that is carried out in under-ground laboratories, such as the Asse salt mine inGermany and the Mol facility in clay in Belgium,in support of design and safety studies. Throughagreements with non-EU countries, work has alsobeen carried out in other underground facilities (e.g.in Switzerland) and there has been a long and prof-itable scientific exchange with Canada, Japan,Switzerland and the USA, among others.

Working together in EC programmes has providedtremendous added value by bringing togethernumerous academic and professional scientists,waste disposal organisations and regulatory agen-cies, and the involvement of the EC has resultedin wide and efficient dissemination of results to allend-users. The two most recent R&D programmes(Fourth and Fifith Framework Programmes: 1994– 2002) saw the evolution of the original conceptof co-ordination of national activities, which haddriven earlier programmes. Today, as the geologi-cal disposal concept moves to maturity and imple-mentation, the emphasis is very much on integra-tion of efforts in order to rationalise and optimisesolutions that can be achieved in Europe.

To this end, current programmes are built around‘Thematic Networks’ which bring expertise frommany countries together to work on common‘Integrated Projects’. The EC also launched Cluster(Club of Underground Storage Testing and Research

facilities for underground waste disposal). Groupsand networks working on related issues have beenbrought together in Cluster workshops – for exam-ple, on all types of underground laboratory activ-ity (at a conference in Belgium in September2001), and on the topical issue of excavation dis-turbance to the rock (at a conference inLuxembourg in November 2003). These organisa-tional structures will form the core of FP6, whichtakes the programme through until 2006.

BOX 4: The development of R&D in the EC


Themes and achievements of FP5

Building on the logical breakdown of work inFP4 and earlier programmes, the principalachievements of FP5 can best be explored under

the following thematic headings:

• Development of repository technology• Long-term behaviour of wastes and containers• Groundwater and radionuclide movement around

repositories• Safety assessment of geological disposal• Public Involvement in repository programmes

The following section highlights the main achievementsin each of these themes and more detail is provided inthe boxes on each topic.

Development of repository technologyAs we move closer to the construction of repositories,a key theme has been the large-scale testing and demon-stration of the technologies that will need to be deployedin a few years time. Until recently, repository designs wereessentially concepts on paper – plans and layouts show-ing how the wastes and the barriers can be arranged toprovide the required performance. These had served foridentifying the processes that control rock and materi-als behaviour and as a basis for designing experimentsin underground laboratories, but there had been relative-ly few projects aimed at testing the practical feasibili-ty of handling the engineered components under real-istic repository conditions.

The Prototype Repository Project, carried out in Sweden,was the first full-scale demonstration and test of themachinery that would be used for placing waste contain-ers and the surrounding bentonite clay buffer vertical-ly in boreholes, in the floor of disposal tunnels in hardrocks such as granite. In hard rocks, the disposal con-cept involves a durable metal waste container (copperand steel in this project) surrounded by pre- manufac-tured (blocks) or in-situ compacted bentonite to form thebuffer. As the buffer slowly absorbs water naturallypresent in the rock, it swells and, after some decades,seals the container permanently from contact with theslowly moving groundwaters.

A related project, carried out in an underground la-boratory in Switzerland, simulated the horizontalemplacement of waste containers and the clay bufferalong the axis of disposal tunnels. This closely instru-mented test also reproduced the heating of the bufferand the rock that will be caused by the radioactivedecay of waste and looked at the way the buffer absorbswater from the rock. It was possible to test and to begin

Pictures of a heater,inserted inside highlycompacted bentoniteclay blocks in a 2.5 mdiameter tunnel ingranite before andafter their heating.This full-scale test ofheat and watermovement has beenused to simulate theperiod immediatelyafter a wastecontainer and its claybuffer are emplacedin a repository(courtesy ENRESA).

A major ‘prototype repository’ project in Sweden hastested the engineering methods needed to place full-scale model spent fuel containers into disposallocations in a deep underground laboratory in granite– a dummy (non-radioactive) copper container canbe seen being rotated for emplacement in a disposalhole in the floor of a tunnel (courtesy SKB).



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to validate, under realistic disposal conditions, the math-ematical models used to predict how these processes occur.

In clay repositories, the buffer material will comprise ben-tonite clay pellets, rather than blocks. An equivalent full-scale test in an underground laboratory in clay inSwitzerland evaluated the mechanical procedures foremplacing the buffer. After artificially accelerating theuptake of water by the pellets – it would take many hun-dreds of years for water to enter the engineered barri-ers in this very dry rock – it was possible to examine theisolation and barrier properties of the final clay mass

Important practical lessons were learned in each ofthese three projects about how to handle materials andengineered barrier components under deep undergroundconditions. In a repository, the operators will need to beable to adapt to working routinely in restricted space,under natural temperature and humidity conditions.Eventually, it will also be necessary to perform demon-strations of how to handle fully radioactive waste con-tainers remotely. An important factor in the long-term behaviour of a

repository is the disturbance of the rock around wastedisposal tunnels and boreholes by theexcavation method – the ‘excavationdisturbed zone’ (EDZ), which couldinclude the formation of small, openfractures. Typically, civil engineers usedrill-and-blast in hard rocks, mechan-ical excavation in softer rocks such asclays, or tunnel-boring machines(TBMs) in any rock with reasonablestrength. A disturbed zone could affecthow water moves around the engi-neered barriers. It was recognised thatTBMs cause the least disturbance inhard rocks, but there was limitedknowledge about the EDZ in clays,where it was believed that the plasticor swelling nature of the rock couldcause disturbances to heal naturally.Such healing has now been observed

under a range of conditions and appropriate mathe-matical and physical rules developed to describe it.

A heated, dummy waste container being emplacedinto a tunnel in clay, where it will be surroundedby pelletised bentonite clay buffer material. Thecontainer is initially supported on blocks of com-pacted bentonite (courtesy ENRESA).


BOX 5: Key repository technology achievements

• Full-scale testing of high-precision drilling forcontainer deposition holes in granite.

• Demonstration of full-scale, inactive canister andbentonite clay buffer emplacement.

• Emplacement of bentonite clay tunnel backfillabove deposition holes with high homogeneityand density.

• Industrial-scale manufacture of preformed blocksof clay buffer material of the quality needed forwaste disposal and full-scale testing of bentonitepellet emplacement.

• Full-scale emplacement of clay and concreteshaft seals.

• Validation of models used to predict the thermo-hydro-geochemical and mechanical developmentof the clay buffer at large-scale under simulateddisposal conditions.

• Acoustic emission tests of self-healing in clays aswater enters open fractures caused by excavationdisturbance.

• Simulation of excavation disturbance healingaround tunnels in clay caused by swelling back-fill material and observation of natural healing withtime after excavation, even in open tunnels.

• Testing models for salt deformation around heat-ed waste containers at full-scale, over eight years,confirming earlier laboratory tests.

• Long-term tests on instrumentation used in salt,allowing development of operational monitoringsystems for repositories.

As a result of these large-scale tests under real con-ditions, repository designers and engineers arenow increasingly able to develop operational plansfor repositories that can be refined over the yearsbefore construction work begins.

Repositories will remain open for many decades aswaste is emplaced – possibly even long afterwards if soci-ety decides that it wishes to maintain an option tomonitor the waste disposal zone directly or to be ablemore easily to retrieve them for some purpose (see Box5). Prolonged exposure of the disposal and access tun-nels to the atmosphere could also disturb the rockproperties, especially in clays, which are prone to drying. This effect has now been examined in detail byaccelerated ventilation of a test tunnel in the Swissunderground laboratory in clay.

Like some clays, rock salt also tends to creep and healnaturally. Since 1990, a full-scale experiment had beencarried out in a salt mine in Germany, using six inactive,but electrically heated waste containers, each weighing65 tonnes. The disposal tunnel around the simulated con-tainers had been filled with crushed rock salt and the nat-ural creep of the host rock had sealed the containers intoplace. After eight years, the whole system was excavat-ed and the material properties studied, allowing good val-idation of many of the predictions made about the devel-opment of the salt properties over time.

A long-term test of the behaviour of a non-radioactive, simulated high-level waste containerin an experimental gallery in a mine in a deepsalt formation in Germany. The container can beseen as crushed rock salt is being excavated fromaround it, after the test (courtesy DBE).


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Eventually, repositories will have to be closedand sealed. Although this is still many decadesinto the future, underground tests have alreadybeen under way for some years to begin eval-uating appropriate designs for seals, especial-ly for the access shafts from the surface tothe repository. Full-scale bentonite clay andconcrete seals have been emplaced in an exper-imental shaft in an underground laboratory inclay in Belgium. The work has tested the devel-opment of seal properties that aim to preventwater movement in and around the seal zone.An important factor was the removal of theshaft support system – temporary engineeringintended for the operational period of the repos-itory – so as to ensure a good seal directly withthe surrounding rock.

One of the common advances made in all of thetests of repository technology has been in thefield of instrumentation to measure a widerange of rock and material properties.Instruments need to be able to operate for longperiods, sometimes in adverse conditions of hightemperatures or aggressive chemistry. Advanced,fibre-optic techniques for data transmissionunderground have been developed and testedwithin the current programme.

Much has been learned that will be usefulwhen considering how to monitor real reposi-tories through their operational lives and beyond.A Thematic Network on monitoring began to lookat technical and societal requirements for suchactivities – a truly cross-cutting issue wherethere are diverse views on what is needed andhow and when monitoring data could be used.This is closely linked to the whole issue of‘phasing’ repository development so as to estab-lish a broad consensus of confidence beforemoving from one step of disposal to the next(see Box 6).

BOX 6: Phased repository development

Because repository development programmes will take manydecades from inception to completion, it is important thatthey are robust and responsive enough to whether the ever-changing backdrop of social and political change, scientif-ic and technological development and the inevitable turnoverof expert staff and decision-makers as the years pass. We willnot be involved in many of the key, but distant decisions thatneed to be taken before a repository is closed.

This has led to the concept of ‘phasing’ or ‘staging’ in whichthe programme is broken into manageable steps that canbe completed and handed along with confidence to futuregenerations, while leaving them able to modify decisionstaken today if they so wish. Each phase should enhancethe overall safety and security of the wastes. Some of thequestions that arise in phasing, and which are beingaddressed by networks within the EC programmes, are:

• how long should we store wastes before taking themunderground and can we do this securely?

• can the option to retrieve wastes be incorporated intodesigns without affecting their isolation performance?

• how long can a repository remain open for inspection ofthe disposal zone and can it be readily closed?

• can and should specific repositories be flexible to adaptto changing rates and amounts of waste production overfuture decades?

• what type of monitoring of the repository and its envir-onment should be carried out, and when?

• how can monitoring contribute towards understanding andhow can the results be used?

• what type of surveillance may be required to ensure thepermanent security of disposed nuclear materials?

Many of these issues are philosophical in nature, but eachhas a practical implication. In many cases, there is norequirement to reach decisions today, but we must all beaware that choices will always exist and it is our respon-sibility to be aware of them and be prepared to make deci-sions when required.


Long-term behaviour of wastes andcontainersEurope’s most highly active radioactive wastes destinedfor geological disposal comprise spent fuel (SF), takenfrom power reactors and stored to cool for severaldecades before disposal, and vitrified high-level wastes(HLW) from reprocessing spent fuel to extract reuseableuranium and plutonium. SF comprises uranium oxide fuelelements that contain accumulations of highly active fis-sion product radionuclides. HLW consists of the sameradionuclides that have been separated from the urani-um oxide and incorporated into a solid glass matrix.

Euratom’s earliest work in the 1970s and 1980s was oncharacterising HLW and how it will behave in a reposi-tory. This work is essentially complete and a solid under-standing is now in place. Only limited studies contin-ue to refine some of the chemical data on howradionuclides are slowly leached from glass in contactwith groundwaters. The emphasis today is on fully inte-grated studies of how all the material and chemical com-ponents in and around the waste will interact over longtimes. The results enable many of the earlier conser-vatisms on radionuclide leaching to be removed – glassis a very durable material under disposal conditions.

The corrosion rate of the metal waste containers controlsthe time of first release of radionuclides into the sur-rounding engineered barriers. The rate depends on thetype of metal used – some concepts place little weighton the container as a barrier and use relatively short-livedmaterials such as iron and steel, while others utilise veryresistant metals such as copper and titanium. These twoconceptual approaches to the role of the container in themultibarrier system are called respectively ‘corrosionallowance’ and ‘corrosion resistance’. The mechanismof corrosion – general, localised or cracking as result ofstresses in the metal – as well as the chemistry of theporewaters around the container, are also critical factors.FP5 continued to examine metal corrosion, focusing inparticular on the behaviour of a wide range of possiblecontainer metals in saline waters that are present in manydeep geological environments. There is now so much

information available that this work is able to makestate-of-the-art recommendations for the most appropri-ate container materials for use in salt, clay and graniterepository rocks.

Once containers are breached by corrosion, the SF orHLW can also be corroded or dissolved by porewaters thatpenetrate inwards from the surrounding rock and theengineered barriers. This may take thousands, eventens of thousands of years to initiate. The chemicalconditions inside a breached waste container are com-plex, being controlled by the salinity and oxidisingcapacity of the water, the products of metal corrosionand the radiation from the waste. Waste corrosion – espe-cially SF breakdown – is extremely slow, and experimen-tal work in the laboratory on conditions inside copper-steel SF containers has confirmed this. Chemicalconditions tend to minimise the rate at which radionu-clides are released into solution from the SF or becomemobile so that they can migrate into the surroundingbuffer material. In fact, the current work has shown ear-lier assumptions used in safety assessments to be unre-alistically conservative – the waste and container pro-vide much better barriers than had been assumed.


16

BOX 7: Key achievements in waste and container behaviour

• Improved understanding of how glass alteration productsthemselves act to adsorb, precipitate and thus help immo-bilise radionuclides leached from the glass by groundwa-ters and pore waters in the repository.

• Validation of complete resistance of titanium-palladium con-tainer materials to localised and stress corrosion in brines,as well as its negligible general corrosion rate (0.2µm/year).

• Confirmation of suitable ‘corrosion allowance’ canistermaterials with high pitting corrosion resistance for use insalt – such as TStE 355 carbon steel; of the suitability ofHastelloy C-22, copper and copper-nickel alloys and car-bon steel for disposal in granites with bentonite buffers;of chromium-nickel steels as the most promising contain-er material for repositories in clay.

• State-of-the-art recommendations on the most appropriatecontainer materials for different geological disposal envi-ronments.

• Experimental confirmation of extremely low dissolutionrates of spent fuel under realistic conditions replicating thoseinside corroded copper-steel containers – much lower thanvalues that had been used in safety assessments to date.

• Confirmation that the chemically reducing conditionsinside copper-steel waste containers will considerablyreduce the mobility of uranium and neptunium releasedfrom corroding spent fuel, before they can leave the con-tainer – again reducing the conservatively calculatedimpacts of previous safety assessments.

Spent fuel and HLW are extremely stable materials and willremain so in the deep, stable environment provided by geo-logical disposal. As a result of many years of study, theirproperties and behaviour are well understood. We have arange of suitable metals in which to contain them so that theycan be deposited and isolated inside the buffer and the rockof a deep repository.

Groundwater and radionuclidemovement around repositoriesRadionuclides that move slowly out of the degrad-ed engineered barriers may become mobile ingroundwaters in the rocks surrounding the repos-itory. How they move through fractures and poresin the rock and are slowed down or immobilisedby interaction with the minerals in the rockshas been extensively studied for many years.The root of understanding the ‘transport’ processis to be able first to estimate the movement ofwater through the rock, then to superimpose thechemical behaviour of the radionuclides as theyinteract.

FP5 focused its transport studies on fracturedhard rocks, such as granite. Both water flow andradionuclide transport in this environment are nowwell understood and one of the remaining chal-lenges is to be able to capture the natural vari-ability of these processes in models and in fieldmeasurements. Whilst we can already do this con-servatively enough for safety assessments (seelater), it is recognised that increasing field dataand progressive advances in science will enableus to do this more accurately and realistically asthe years go by.

The water in deep geological environments oftendisplays high salinities that reflect the ‘age’ ofthe water, or how long it has been present in therock and interacting with it. Saline waters aredense, which tends to make them less mobile,and most deep environments contain heteroge-neous bodies of water of different chemistry,age and origin. Our ability to model groundwa-ter flow and to relate it to water chemistry needsto be tested by looking at these natural flowsystems, because they have operated for very longtime periods – similar to those we are concernedwith for waste containment. This type of studyinvolves looking at the distribution of water of dif-ferent composition in large volumes of rock –


typically over tens of square kilometres and downto one or two kilometres depth – the scale of a repos-itory site. Detailed chemical and natural isotopemeasurements of the waters and the rock mineralstell us much about how long water has resided inthe rock, where it came from and how stable theflow system would be if a repository were to beplaced at depth.

Water chemistry controls how radionuclides behavein deep groundwaters – whether they are in solu-tion in organic or inorganic form and whether theycan attach themselves to tiny colloid particles.Much work in FP5 has focused on what controls thebehaviour of the actinide series radionuclides (suchas plutonium, neptunium and americium), as wellas the most mobile radionuclides, such as radio-active iodine. New analytical techniques are pro-viding ever increasing understanding, and theimproved databases, combined with integratedreactive transport and geochemical evolution mod-els, should progressively reduce the conservatismwith which we frequently model many aspects ofradionuclide movement.

All of this information and modelling can be test-ed using ‘case studies’. Two exercises have beencompleted recently – one looking at the organicchemistry of actinide radionuclides in the porewater environment of the boom clay in Belgium, apotential repository host rock, the other at histor-ically contaminated deep environments in Russia.This latter project examined evidence for the mobil-ity of mainly shorter-lived radionuclides that hadbeen injected deep into the ground as liquid waste– a practice that would not be accepted today inEurope. Nevertheless, the sites provided a usefulinsight into transport and retention processes.

BOX 8: Key achievements in groundwater and radionuclidemovement

• Significant gaps in the thermodynamic database for thetetravalent actinides were filled, and understanding oftheir complexation with organic species much improved.

• Molecular scale modelling and quantum chemicaltools applied for the first time to evaluate the coord-ination chemistry of actinides in natural waters.

• New X-ray spectroscopic techniques used to look ingreat detail at mineral surface sorption of actinides.

• Increased understanding of the important role of min-eralisation (e.g. in cement degradation products) in fix-ing radionuclides inside the repository barriers.

• Demonstration of the large-scale barrier effect ofthick clay layers in preventing radionuclide migra-tion at depth in a contaminated site.

• Demonstration of the immobility of uranium colloidsin a clay formation as a result of ultrafiltration.

• Detailed characterisation of americium colloid in-stability and americium interaction with organic com-plexants in clay.

• Broad agreement between performance assessmentmodellers and experimental and observational scien-tists on the current ‘fitness for purpose’ of the repre-sentation of transport processes in safety assess-ments – including identification of ‘closed’ andlow-relevance issues/processes and areas where rep-resentation can and will be improved in future.

• Identification of ways to move forward with integrat-ed reactive pathway evaluation linked with time-dependent geochemical evolution – giving more real-ism to performance assessments and allowing areduction in conservatism.

Our understanding of the most important aspects ofradionuclide chemistry in natural waters continues toimprove and we are filling important gaps where there havebeen questions for many years – the key example beingcolloid behaviour. New analytical techniques will provideever-increasing detail in our knowledge and realism to ourmodels – but in the meantime, the safety assessment mod-ellers are generally content with the adequacy with whichthey can represent chemical transport aspects.


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Safety assessment of geological disposalAll of the processes discussed above control the way inwhich a repository behaves over thousands of years intothe future. We need to understand how all the process-es fit together and what the fate of each radionuclidein the waste will be. Most will never leave the wastematrix or its container, decaying in situ. But somemobile and very long-lived radionuclides will eventual-ly begin to disperse into the rock. Evaluating what hap-pens to them and their possible impacts on people andthe environment far into the future is called ‘safetyassessment’ (SA) and has formed a focus for EC pro-grammes for the last 25 years.

The methodology for carrying out safety assessment isnow thoroughly developed and tested – indeed, it is aroutine exercise used regularly, at various programmestages, to compare alternatives: designs, layouts, mate-rials, geological environments and repository sites.Safety assessment looks at the behaviour of the wholedisposal system to evaluate possible radiological impactson people. Its cousin, ‘performance assessment’ (PA)models the behaviour of components of the system – per-haps comparing the suitability of different containermaterials, or combinations of container materials, underdifferent conditions. Performance assessment is itselfbased on connected ‘process models’ that reflect detailedscientific understanding. PA generates the buildingblocks of a complete safety assessment, often by pro-ducing simplified models of processes in parts of the dis-posal system, or simplified datasets that can be moreeasily managed in a full SA.

Bentonite is one of the most important components ofmost engineered barrier and seal designs; a major exer-cise in FP5 looked at every aspect of the behaviour ofthis material at a process model level and at how theseare translated into PAs, focusing in particular on the con-sistency of the data and the evaluation methods. The keyrole of bentonite buffer is to ‘slow down’ the move-ment of chemicals and radionuclides around waste con-tainers to a rate controlled by diffusion – an exception-ally slow chemical transport mechanism.

The important barrier functions of bentonite can beaffected if it is attacked by the alkaline pore fluidsfound in the cements and concretes that will inevitablybe used in repository construction. Repository hostrocks. too, could react with these fluids. These interac-tions have been extensively studied both experimental-ly and by thermodynamic modelling. It was found thatthe depth of reaction penetration into bentonite bufferand clay host rocks is not significant enough to affecttheir performance.

Process models that describe materials behaviour in arepository need to consider all of the driving mechanisms– thermal, chemical, hydraulic and mechanical (‘TCHM’)resulting from the radioactive decay heating of thewastes, the chemical composition of materials andpore waters, and the rock stresses. These can each beaffected by external events, too – for example, in thedistant future, some European countries will be coveredby thick ice sheets in a new ice age – with thermal andmechanical load impacts being transmitted even torepository depths and changes in groundwater flowand chemistry.

Coupling these TCHM process models together is an areawhere much work is continuing in EC programmes. Theconstant growth of scientific and computational capac-ity means our ability to make ever-more realistic and inte-grated models of system evolution should contribute toa continued, progressive reduction in the conservatismsthat have been used in PA and SA.

When some metals corrode under the anaerobic condi-tions inside closed engineered barriers, it is possible togenerate large amounts of hydrogen gas. Other gases pro-duced in the wastes might also be radioactive – 14C con-taining methane, for example. The pressures producedif hydrogen gas cannot slowly disperse through the rockcould damage the engineered barriers, so there hasbeen much study of how gas is generated and how itmoves in a repository. FP5 launched a Thematic Networkon this topic that was able to integrate present knowl-edge and identify several areas where more work will be


needed if we are to be able to include better-characterisedgas impacts in safety assessments, instead of having touse overly conservative assumptions.

Any radionuclides that do escape from the rock and deepgroundwaters could find their way into the biosphere.Pathways for radionuclides through surface waters,soils, plants and animals to people are complex.Nevertheless, the ability to identify and evaluate themis a key aspect of safety assessment as the biospherepathways and processes ultimately control the potentialhuman radiation doses we calculate and these are com-pared with regulatory standards to decide whether arepository provides sufficient safety. The biosphere is avery complex and constantly changing natural system,especially when looked at over thousands of years – notleast, as a result of changing climate and human habits.Consequently, there are numerous uncertainties aboutfuture biosphere states. Safety assessors seek to getround this problem by identifying present- day biospheremodels that can act as reference states covering the mainenvironmental conditions that could occur over the nexthundreds of thousands of years.

One project in FP5 has taken the approach of identify-ing five specific biosphere models that cover a range ofclimate and land use conditions – in Hungary, Spain,Belgium, Germany and Sweden. Comparisons weremade between the behaviour of critical radionuclides ina range of exposure pathways in each environment.This work was linked to a climate change modelling exer-cise that used global-scale climate models to evaluatehow each of the reference biosphere sites could evolve.

Owing to uncertainties about the biosphere and humanbehaviour in the distant future, many people suggest thatradiation doses should not be used alone or as themain measure of repository performance or safety aftera few thousand years. A major FP5 project consideredmore than 20 possible alternative indicators of safety –or of the performance of various parts of the repositorysystem that show how well it is functioning at differenttimes in the future. Future safety cases are likely to usea range of these indicators to support arguments on howadequately a repository performs its isolation role.

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BOX 9: Safety assessment achievements

• Simulation of the complex coupled processes occurring asbentonite clay buffer becomes saturated with water andswells during the early thermally active period of a repos-itory: but there are still uncertainties – the interaction ofbentonite with cement and the movement of gas in ben-tonite both need further study.

• Experimental and modelling studies of cement interactionwith clay and granite – insignificant impacts found on repos-itory performance.

• Testing of fully and partially coupled TCHM process mod-els for hard, fractured rocks – particularly important in theresaturation and heating phase, a few hundred years afterwaste emplacement.

• Examination of stress effects of rock permeability andevaluation of hydromechanical conditions in a repositoryduring glacial periods.

• Identification of uncertainties about gas generation andbehaviour in repositories, allowing structuring of the nextstage of EC studies.

• Development of reference European biosphere models cov-ering a range of climate and environmental states, to helpassess possible radiation doses to people in the future.

• Application of global- and regional-scale climate modelsto evaluate the evolution of reference biospheres in Europe.

• Testing of the utility of alternative (to radiation dose) per-formance and safety indicators – including radiotoxicity flux-es and concentrations in water, distribution of radioactiv-ity in ‘compartments’ of the repository, the rock and thebiosphere and the flux of activity between them.

Safety assessment is an established, everyday activity.Today, it takes a practical and conservative approach (it over-estimates impacts) – future developments will allow it tobecome more realistic.

Public involvement in repositoryprogrammesMany people see radioactive waste disposal as acomplex, difficult and dangerous technologicalactivity that can only be understood by a fewexperts and which is likely to cause insidious,long-lasting damage to our own and our children’senvironment. Whilst the same fears might beengendered by many other activities, we aremore familiar with them and much less con-cerned – we have a particular fear and a widelyfelt distrust of anything associated with radioac-tivity and radioactive wastes.

Fear and mistrust stem from lack of informationcombined with a feeling of powerlessness toaffect developments. This situation must beovercome by ensuring that we are properlyinformed about the issues and actively involvedin making decisions about them. The whole of theEuratom programme is now focused on ener-getic efforts to ensure that information is adver-tised and accessible.

Today, enhancing transparency in radioactivewaste management activities and encouraging cit-izen participation are top-level concerns in allEuropean organisations concerned with the issue.Two of the FP5 projects with the broadest par-ticipation have looked into and tested methodsfor communicating the technical complexities(especially those surrounding safety assess-ments), and receiving and responding to feedbackin a process of public dialogue. For a specific dis-posal project, both local people and the nation-al population might wish to be involved and thismust all be done in the framework of national andsocial and economic European interests.

One project focused on the difficulty of makingcomplex performance assessments transparentto those elements of the non-scientific commu-nity which need to be involved in decision-



making. One finding was that PAs would benefit frombroader involvement – beyond the specialists. Concernedpeople ask questions that PA can help to answer, if itis properly structured and designed to be responsive. Thesetting of regulations for waste disposal also benefits frompublic dialogue. National waste management pro-grammes thus need to set aside resources to allow suchbroader public participation – a set of lessons thatought to be valued far beyond radioactive waste man-agement, in addressing any complex policy issue.

A major step forward in real public involvement was seenin the EC project which brought together 30 communi-ties across Europe to share views and experience. A keytheme of the seminars was public involvement in set-ting national radioactive waste management frame-works and regional policy, and in local decision-making.Local people are extremely interested in taking a role indecisions on how repository projects could develop.The results of the shared experiences of these groups willundoubtedly identify good common practices and stim-ulate local empowerment over coming years, as geolog-ical disposal moves from concept to reality in theEuropean Union.

Looking forward to the next five years:the Sixth Framework Programme (FP6)Science and technology grow and develop – a never-end-ing process of learning and improvement. Requirementsfor radioactive waste management will change as nation-al and European programmes evolve. The prospect ofchange is inevitable and does not prevent rational,informed decisions and actions being taken at any pointin time – if it did, our advanced society would never havedeveloped. Thirty years of European R&D have nowbrought us close to the first implementation of radioac-tive waste disposal, putting the final piece in place togive us a complete and sustainable system for one of ourmost important sources of everyday energy.

However, in implementing geological disposal, we mustalways be aware of developments, be able to respond tochange and to make the best use of new advances

when it is appropriate. The European context, too, willchange, as the Union expands and new Members, withtheir own specific waste management problems to solve,enter the arena.

The next five year programme FP6 (2002-2006) pin-pointed these issues – the need to identify and answeroutstanding questions, to pursue appropriate and prom-ising new developments and, above all, to integratenational activities to reach commonly applicable solu-tions. The overall theme is the sustainable integrationof European research in the geological disposal ofradioactive waste. The programme has thus becomestill more focused. The future will see yet more integra-tion, with fewer, larger projects, involving more partners.This is in common with European Union research poli-cy in general.

The first group of such topics that will be studied,mainly within Networks of Excellence and IntegratedProjects, has already been identified (see Box 10).Networking will develop a common European view on themain issues, strengthen the scientific basis, evaluatepracticalities, build structured knowledge transfer andmanagement methodologies, and provide a forum fortraining – the latter being a vital matter, given thedecades’ long timescales of waste management projectsand the consequent need to ensure that knowledge andexperience is propagated from one generation to the next.

This large-scale integration is clearly timely as the nextfive-year programme will bring Europe to the thresholdof actual repository construction, which may commencearound 2010. More than 30 years of concerted Europeanresearch and development will have come to fruition.


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BOX 10: The first group of projects for FP6

• The NF-PRO project will establish the scientific andtechnical basis for evaluating the safety function“containment and minimisation of release” of the near-field of a geological repository for high-level radioactivewaste and spent fuel. It will investigate dominantprocesses and process couplings affecting the isola-tion of nuclear waste within the near-field, and applyand develop conceptual and mathematical models forpredicting the source-term release of radionuclidesfrom the near-field to the far-field. The results and con-clusions of experimental and modelling work will beintegrated in performance assessment.

• COWAM 2 will build on the highly successful firstCOWAM project. It aims to improve the governanceof radioactive waste management by addressing soci-etal expectations, needs and concerns in radioactivewaste decision-making processes, notably at localand regional levels. It will also increase societalawareness of, and accountability for, the managementof radioactive wastes, develop guidance on innovativedemocratic governance, and develop best practicesand benchmarking on practical and sustainable deci-sion-making processes recognised as fair and equi-table by the stakeholders involved.

• Some small nuclear power programmes in the expand-ed EU may not have the resources or the full range ofexpertise to build their own repositories for long-livedradioactive wastes. Even for countries that could poten-tially implement national projects, there are environ-mental and economic advantages in co-operation. Theprospect that countries could work together to exploreshared regional solutions has been much discussed inthe EU. Such solutions raise new transnational issuesnot so far addressed by national programmes: nuclearsecurity, safety of multi-user repositories with diversewaste types, national and European public accept-ability, trans-boundary waste transport, and national andEuropean economics and law. The SAPIERR project isa pilot initiative that will help the EC to begin to estab-lish the boundaries of the issue, collating and integrat-ing information in sufficient depth to allow conceptsfor potential regional options to be identified andscope given to the new RTD needs.

• In recent decades, the actinide sciences have stag-nated and become less attractive to young scien-tists. Europe has seen basic research in this areadramatically reduced. Only a few national researchinstitutions and one international institute (JRC) areable to maintain the necessary research infrastructure.The ACTINET project aims to revitalise the subject andmake it attractive to students so that a new genera-tion of actinide scientists and engineers can devel-op. It will reinforce links between national nuclearresearch institutes, the JRC, and the radiochemistrylaboratories of academic research organisations –27 partners in total within the network. The projectwill significantly improve the accessibility of themajor actinide facilities to the European scientificcommunity, form a set of pooled facilities, improvemobility between member organisations, merge andoptimise parts of their research programmes, andstrengthen European excellence through a selectionprocess for joint proposals. By reducing the frag-mentation of the community and putting a criticalmass of resources and expertise into shared chal-lenges, it will help Europe to remain a world force inthe field of actinide sciences.

• The ESDRED project provides the opportunity forradioactive waste management organisations to worktogether efficiently to generate and share solutions,systems and technologies for constructing, operatingand closing a deep geological repository. It will makepractical scientific and engineering studies of four top-ics that are not well addressed by existing or easilyadaptable mining, civil and nuclear engineering tech-nologies: buffer manufacturing and construction forhorizontal disposal drifts, waste canister transfer andemplacement into horizontal and vertical disposal loca-tions, heavy load emplacement in horizontal dispos-al drifts, and reinforcing and plugging drifts withlow-pH cementitious materials. Monitoring and retriev-ability at all steps of repository construction, opera-tion and closure will be integrated into relevant tech-nical modules. Each module will provide access tovarious industrial solutions compatible with nation-al repository concepts and geological environments.


Further reading

The volume of literature on geological disposal isenormous, not least in the extensive series ofEuratom reports that have been published over

the last decades. These recently published books pro-vide a lead into the general subject area for those wish-ing to know about geological disposal in more depth.

• Chapman, N.A. and McCombie, C. (2003) Principlesand standards for the disposal of long-lived radio-active wastes. Elsevier (publisher), 277 pps

• EURADWASTE'04-Radioactive waste management.Community policy and research initiatives, Proceedingsof the sixth EC conference, Luxembourg 29 March -1 April 2004, Publications Office of the EuropeanCommunities, EUR 21027 EN

• Euratom-Nuclear Fission and Radiation protectionprojects selected for funding 1999-2002, PunlicationsOffice of the European Communities, 2003, EUR20617 EN

• NEA (1999) Geological disposal of radioactive waste.Review of developments in the last decade. OECDNuclear Energy Agency, Paris.

• NEA (2002) Establishing and communicating confi-dence in the safety of deep geological disposal. OECDNuclear Energy Agency, Paris.

• NRC (2003) One step at a time: the staged develop-ment of geologic repositories for high-level radioactivewaste. United States National Research Council,National Academy Press, Washington DC.



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Projects within FP5

The following pages provide more information onthe objectives, challenges and achievements ofthe many projects that formed components of the

Fifth Framework Programme.

The projects are presented in the following pages in tabular form, in two groups:• RTD projects on:

- Repository technology- Waste and container behaviour- Safety assessment of geological disposal- Groundwater and radionuclide movement around

repositories- Public involvement in repository programmes

• Thematic Networks

Where significant results had been published at the timethis brochure was prepared, the main findings are indi-cated in the RTD projects table. The objective of theThematic Networks has been to review key areas after10 to 15 years of research and development and thusto identify ‘closed’ issues as well as those requiring fur-ther work.

Overall, the emphasis within the Fifth FrameworkProgramme has been on integration of RTD studies, bothwithin specific topics associated with geological dispos-al, and by links that improve understanding of the wholedisposal system. To put this integration in context, the dia-gram below shows how each of the project fits into place.

Integration diagram of FP5 RTD projects and Thematic Networks


Repository technology

BAMBUS II

Title: Backfill and material behaviour inunderground salt repositories – Phase II

Co-ordinator: Werner Berchtold, FZK/PTE,[email protected]

Abstract: objectives and results to date

This is the last project in a long series of investigations in theAsse salt mine (HAW, TSDE, DEBORA, BAMBUS I) before clo-sure of the mine in the next few years. In Germany, the wastecontainer emplacement concepts in salt formations use back-filling with crushed salt to stabilise the repository. Backfilling pro-vides long-term sealing of the waste from the biosphere as a resultof backfill compaction owing to salt creep and consequent

excavation convergence. In all the experiments, the waste decayheat was simulated by electric heaters. To determine the achievedbackfill compaction in detail, one of the TSDE test drifts and bothDEBORA boreholes were uncovered after terminating the exper-iments. Post-test laboratory analysis of the backfill, as well asmeasuring the data together with a re-calibration of measuringinstruments, confirmed the numerical predictions and thus thematerial behaviour and 3D-computer models. From these stud-ies, the conclusion can be drawn that the mathematical mod-els, which were developed to simulate the behaviour of backfilland rock formations, are now sufficiently able to simulate the per-formance of a radioactive waste repository for heat-generatingwaste in salt. In the process of excavating the test zone, 280 cor-rosion samples of selected container materials were recoveredand their durability assessed by several laboratory techniques.The results showed very low corrosion rates and almost no pit-ting corrosion effects. The final report on the project has beenpublished under EUR 20621.

EB & VE

Title: EB (engineered barrier emplacement)and VE (ventilation) experiment projectsin the Opalinus clay at Mt Terri,Switzerland

Co-ordinator: Juan Carlos Mayor, ENRESA,[email protected]


The EB experiment aims to demonstrate a new concept for theconstruction of HLW repositories in horizontal drifts, in com-petent clay formations. The principle of the new constructionmethod is based on the combined use of a lower bed made fromcompacted bentonite blocks, and an upper backfill made witha bentonite-pellets-based material. It has been demonstratedthat fabrication of bentonite pellets with the required densi-ty, and production of the specified grain sizes (to optimise pack-ing potential) in a continuous industrial line process is feasi-ble. After emplacement testing in a 6 m long, 3 m in diametertunnel model, of different methods (pneumatic, auger, belt con-veyor), it has been demonstrated that auger method providesthe highest emplaced dry density without major gaps. The fea-sibility of a new construction method of engineered barriers inhorizontal drifts using bentonite pellets (upper part) and blocks(lower bed) has been demonstrated. Although the artificial sat-uration situation removes reality from the “in-situ” experi-ment, and emplaced dry density values are lower than the tar-get ones, the model emplacement results serve to demonstrateachievable densities in a real-world setting. Highly useful

information has been obtained for the design of a repository,in relation to drift size and the handling of the bentonitebuffer and waste canister. Geophysical and hydrogeological char-acterisation of the EDZ, both prior and after hydration of thebentonite buffer, has been performed. Data on the hydraulicand mechanical parameters, both in the rock and the EDZ, weregathered and investigated during the 19-month operationalphase of the project.

The VE experiment is a ventilation test carried out in situ ina 1.3 m diameter by 10 m long horizontal tunnel. The ob-jectives of the test were to estimate the desaturation and resat-uration times in clay rock, produced by drift ventilation; thesaturated hydraulic conductivity of the rock (macro-scale)and comparison with values obtained at smaller scales and eval-uation of the scale effect impacting this important parame-ter; and the evolution of the EDZ, in terms of changes inhydraulic conductivity and of displacements caused by the gen-eration of cracks on drying. Hydraulic characterisation of theclay rock material has been carried out, namely the water reten-tion curve, relative permeability and saturated hydraulic con-ductivity. A specific drying test was conducted to measure therate of evaporation from several core samples under con-trolled climate conditions. These results have been used forthe first calibration of the design model calculations.Geoelectrical and geochemical characterisation has beenmade of the rock surrounding the test section, before start-ing the desaturation-resaturation cycle. These non-destructivemethods, which use various sensors, have enabled the watercontent and water potential for a consolidated clay formationto be determined. The resulting database confirms the appli-cability of the measuring techniques applied to hard clayrocks. The experimental data gathered so far have allowed a



26

first calibration of the different hydromechanical modelsused, particularly of CODE-BRIGHT, corresponding to adesaturation phase of the rock. Rock desaturation (i.e. degreeof saturation lower than 95%) occurs in a small ring aroundthe tunnel (i.e. thickness about 50 cm or lower), after a verylow relative humidity desaturation cycle over several months.

It is reasonable to foresee that under real repository construction conditions with much higher relative humidity,the desaturation of this kind of rock will not be a relevant issue.Rock deformations induced by pore water changes (and hencechanges in the stress state) are also very small.

FEBEX II

Title: Full-scale engineered barriers experi-ment in crystalline host rock – phase II

Co-ordinator: Fernando Huertas, ENRESA,[email protected]


The overall aim of the project is to study the behaviour of theengineered barrier components of a high-level radioactivewaste repository in granite. The project has so far comprisedtwo phases which include an in-situ test at the Grimsel under-ground laboratory (Switzerland), a mock-up test (for con-trolled conditions) above ground in Spain, and a series of lab-oratory tests and numerical modelling of all the tests. FEBEXI demonstrated the feasibility of handling and constructing anengineered barriers system. It also studied the combinedthermal, hydraulic and mechanical (THM) and thermal,hydraulic and geochemical (THG) processes of a repository inthis region. FEBEX II extends this work to improve knowledgeof the THM and THMG processes, especially in a more hydrat-ed clay barrier, in order to improve, calibrate and validate exist-ing numerical codes. A key objective is to examine the poten-tial changes that may occur in the buffer material – inparticular, by their interaction with solutes in porewaters andgroundwaters. FEBEX II also looks into gas and radionuclidetransport processes inside the engineered barriers as the ben-tonite properties evolve, and at waste container corrosionprocesses in reference metals. The heat and bentonite-rockinteraction modify the hydraulic regime inside the rock mass,and this is also studied, with special emphasis on the exca-vation-disturbed zone (EDZ).

Two engineering objectives are also important: evaluation ofthe long-term behaviour and performance of instruments andmonitoring systems – with potential implications for a realrepository – and investigation into the technological aspectsof canister retrievability, in order to identify potential problemsthat should be taken into account in this reference reposito-ry concept. The major achievements of the project so far have been:

• The feasibility of constructing engineered barriers for the hori-zontal storage of canisters placed in drifts has been demon-strated. Specifically, it has been shown that the manufac-turing and handling of bentonite blocks is feasible atindustrial scale and that the clay barrier may be construct-ed with a specified average dry density in order to achievethe permeability and swelling pressure required for the bar-rier. Furthermore, highly useful information has been obtainedfor the design and construction phase of a repository, in rela-tion to the size of the drifts, the specifications and proce-dures for the manufacturing and handling of the bentoniteblocks, the basic characteristics of the equipment for con-struction of the clay barrier, and insertion of the waste can-isters and construction of concrete plugs, etc.

• The CODE-BRIGHT numerical THM model is capable of rea-sonably predicting the measured results of the two large-scaletests. During this period, it has been necessary to modify justminor details of the model as it has been observed that itscore is based on solid physical laws. Although complete val-idation is never possible, the checks performed have signif-icantly increased the degree of confidence in the capacityof the model for the performance assessment of the THMbehaviour of a repository near field.


PROTOTYPE REPOSITORY

Title: Full-scale testing of the KBS-3 conceptfor high-level radioactive waste

Co-ordinator: Christer Svemar, SKB, [email protected]


The main objectives of the project are to use engineering, full-scale demonstration and in-situ testing to prove the feasibilityof a repository concept for hard rock, using the Äspö hard rocklaboratory in Sweden. The prototype repository consists of twotunnel sections with four and two canister deposition holesrespectively. The outer section should be dismantled after fiveyears of operation, while the other section may be operated forup to 20 years. A concrete plug separates the two sections, andthe test is isolated by an outer plug. Electrical heaters insidethe canisters simulate the decay heat of the spent fuel and thecanisters are embedded in a highly compacted bentonite buffer.A tunnel-boring machine (TBM) with diameters of 5 m for the

tunnel and 1.75 m for the vertical holes was used for excavation.The boring of the horizontal drift was based on proven technol-ogy, while the vertical boring needed more accurate precisionsthan ever done before. The outcome was better than expected.The project used “MX-80” bentonite from Wyoming for the buffer.Techniques have been developed, following co-operation betweenSpain and Sweden, for the compaction of blocks with dimen-sions ranging from brick size to cylinders with a diameter of1.65 m and height of 0.5 m. Large bentonite blocks wereplaced in a column and the canister lowered into the centre hole.Backfilling of the tunnel used a mixture of 70% crushed TBMmuck and 30% bentonite (a soda-treated natural Ca-bentonitefrom Greece). In situ compaction gave both better than expect-ed results (in the centre) and worse (close to the rock). Waterinflow was a problem, not only because the instrumentation inthe backfill required a long installation time, but also becauseof the high inflows – 5 l/min along a 5 m section of the tunnel.This project is closely related to the FEBEX II project (above)with horizontal canister emplacement. Full-scale testing of aSwedish “in-drift” method has recently been scheduled forthe Äspö hard rock laboratory.Further information available at: http://www.skb.se/prototype

SELFRAC

Title: Fractures and self-healing within theexcavation disturbed zone in clays

Co-ordinator: Frédéric Bernier, SCK.CEN,[email protected]


The main objectives of the project are to characterise theExcavation Damaged or Disturbed Zone (EDZ) in clay and its evo-lution with time, as it may lead either to a significant increasein permeability related to diffuse and/or localised crack prolif-eration, or (as a result of self-sealing and self-healing) a reduc-tion in permeability with time. Two potential geological forma-tions for deep radioactive waste repositories were studied: theOpalinus clay (Switzerland) and the Boom clay (Belgium).Triaxial and biaxial tests were used to understand and quanti-fy the fracturing process and the increased permeability relat-ed to crack proliferation around excavations. The results of

these tests allowed sets of parameters to be established fornumerical simulation. Other tests characterised self-sealingand self-healing processes by monitoring the evolution of flowproperties along a fracture, and by means of acoustic emission.Results of these tests show that in Boom clay self-sealingoccurs very quickly after flooding of the fracture. During self-sealing the permeability decreases up to values close to the per-meability of intact Boom clay (about 4.10-12 m/s). The first in-situ test conducted in Opalinus clay at Mt Terri studied theinfluence of bentonite swelling pressure on transmissivity in theEDZ. Permeability measurements were performed during thestages of a long-term load test in order to investigate mechan-ical-hydraulic effects. The assumed healing effect/process,combined with a significant reduction in transmissivity (near-ly two orders of magnitude), has been proven. An in-situ test inBoom clay at Mol is studying the long-term evolution of the dis-turbed zone along a gallery. A reduction of the extent of the EDZwith time is being observed. It has been shown that open frac-tures close progressively. One year after the excavation of thegallery, the extent of open fractures did not go beyond a zoneof about 0.6 m around the gallery.


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Waste and container behaviour

CONTAINER CORROSION

Title: Long-term performance of candidatematerials for HLW/SF disposal containers

Co-ordinator: Emmanuel Smailos, FZK,[email protected]


To determine the influence of essential parameters (e.g. com-position of host rock, temperature, gamma radiation) on the cor-rosion of canister materials and to gain a better understand-ing of the corrosion mechanisms. In-depth corrosion studieswere performed on selected materials in simulated rock salt,granite and clay environments: carbon steel, stainless steels(Cr-Ni steels), nickel-base alloys (Hastelloy C-4 and HastelloyC-22), the titanium-palladium alloy Ti99.8-Pd and copper(Cu)-base materials. The results obtained in salt brines up to150°C indicate agreement with previous studies that the pas-sively corroded alloy Ti99.8-Pd is the strongest candidate forthe manufacture of long-lived containers (corrosion-resistantconcept). Under all test conditions this material was complete-ly resistant to local corrosion and stress-corrosion cracking, andits general corrosion rate was negligible/low (0.2 µm/a). Theactively corroded TStE355 carbon steel and the Cu-base mate-rials Cu, Cu-Ni 90-10 and Cu-Ni 70-3070 are promising forthe corrosion-allowance concept. They are resistant to pittingcorrosion, in terms of an active-passive corrosion element,

and their general corrosion rates, although clearly higher thanthe value of Ti99.8-Pd, imply corrosion allowances reasonablefor thick-walled containers. The corrosion rate of the Cu-basematerials clearly decreases through galvanic coupling withcarbon steel, i.e. the more noble Cu-base materials will becathodically protected by the less noble carbon steel. Theresults obtained in granitic water and granitic-bentonite envi-ronments at 90°C indicate that the materials Hastelloy C-22,Cu, Cu-Ni alloys and carbon steel are strong candidates for con-tainers to be disposed of in a granitic formation. These mate-rials exhibited a high resistance to stress-corrosion cracking(SCC) and to pitting and crevice corrosion under relevant dis-posal conditions. Only the alloy Cu-Ni 70-30 has shown a slightsusceptibility to SCC under very hard test conditions, i.e.extremely low strain rates of 10-6-10-7 s-1 and a chloride con-centration of 50,000 ppm, which is more than seven times high-er than the chloride concentration expected in the Spanishgranitic-bentonite environment. Electrochemical studies inclay water (anaerobic and aerobic conditions, T=16-140°C, 100-50,000 ppm Cl-) indicate that among the passively corrodedmaterials only Ti99.8-Pd is completely resistant to pitting andcrevice corrosion. Hastelloy C-4 and Hastelloy C-22 showslight crevice corrosion at Cl- concentrations higher than20,000 ppm. The Cr-Ni steels investigated show a lower resist-ance to pitting corrosion than Hastelloy, but they are resistantto pitting at Cl- concentrations which are relevant for theBelgian disposal concept. Considering material costs and con-tainer fabrication aspects, Cr-Ni steels are considered themost promising material for containers to be disposed of in aclay repository.

COBECOMA

Title: State-of-the-art document on the corro-sion behaviour of container materials

Co-ordinator: Bruno Kursten, SCK.CEN,[email protected]


Carbon steels, stainless steels, nickel-based alloys, titanium-based alloys, and copper have been widely investigated aspotential container materials, depending on the studied hostrock formation. The results obtained in salt environmentsindicate that the passively corroding Ti99.8-Pd is the primary

choice for the thin-walled corrosion-resistant concept, sinceits general corrosion rate is negligible and it is highly resist-ant to localised corrosion and stress corrosion cracking (SCC)in salt brines. The TStE 355 carbon steel is the first candi-date for the corrosion-allowance concept because it is resist-ant to pitting corrosion and SCC and its general corrosion ratesare sufficiently low to provide corrosion allowance acceptablefor thick-walled containers. Stainless steels, Ni-based alloys,and Ti-based alloys are the most important candidate contain-er materials in clay for the thin-walled concept, while carbonsteel is considered the main choice for the thick-walled cor-rosion-allowance concept. Studies performed in granite seemto indicate that copper containers provide an excellent corro-sion barrier with an estimated lifetime exceeding 100 000years. The TStE 355 carbon steel is also a valid option for athick-walled container concept in granite.


CORALUS 2

Title: Integrated in-situ corrosion test ofalpha-active HLW glass – phase II

Co-ordinator: Elie Valcke, SCK.CEN, [email protected]


To validate the long-term behaviour predictions generatedunder the GLASTAB project. This is being done by compar-ing the GLASTAB experimental and modelling results with theexperiments undertaken in the CORALUS project: the alter-ation kinetics and radionuclide release and migration arebeing studied in situ at Mol (Belgium) in the HADES under-ground research facility under conditions as realistic as pos-sible to those of disposal.

DACAPO

Title: Development and automation of chemi-cal analytical procedures for thedetermination of non-gamma emittingradionuclides in radioactive waste

Co-ordinator: Johannes Fachinger, FZJ,[email protected]


To develop advanced methods for the destructive analysis ofconditioned radioactive waste and the automation of these meth-ods. The project aimed to develop reliable methods in order tominimise the risk for the employees, by short analytical pro-cedures or by pre-separation of the main activity, like 137Csor 60Co. Different decomposition methods have been devel-oped based on pressurised microwave digestion and on com-bustion. All waste matrices could be disintegrated sufficient-ly except slag from decontamination melting processes formetals. Methods have been developed to investigate suchresidues and validated with a cement powder with a knownradionuclide inventory. The separation of the radionuclides fromthe dissolved waste samples was performed by precipitation,liquid-liquid extraction, solid-phase extraction and high-perform-ance liquid chromatography (HPLC). The last two methods could

be performed in a completely automated manner, and thelast method has the added advantage that the HPLC systemcan be coupled with an on-line liquid scintillation counter fordirect measurement of a- and ß-emissions. The detection lim-its of such a system are sufficiently low for most ß-emitters,which occur in higher activities in the waste. However, the detec-tion limit for a-emitters of 5 Bq/ml is still too high with respectto the required detection limits for destructive waste analysis.In order to reduce the dose rate, several new extracting agentshave been synthesised to separate 137Cs and 60Co (thenuclides which cause the highest dose rates in the samples)selectively from all other radionuclides. Furthermore, theextracting agents have been fixed on a polymer resin or silicato get a stable material which could be used in automated chro-matographic systems. In general, most of these extractingagents were able to separate Co and Cs but unfortunately athigh pH values which will disturb further analysis procedures.Nevertheless, one agent, poly(Terpy-1-co-NBE)-coated silica,was able to extract Co at low pH (1.5 - 2.5). This is an impor-tant development because no alternative separation method wasavailable for Co. A model has been developed for calculationof the radionuclide inventory of a waste package based on thegradient between samples from different locations of a wastedrum, and has been checked by statistical computer model-ling. It could be shown that such a calculation would lead toa conservative estimation for stirred cemented waste for astorage facility, if a sufficient number of waste packages werecalculated in this way. However, it could not be used for theinventory estimation of single waste packages.

GLAMOR

Title: A critical evaluation of the dissolutionmechanisms of HLW glasses in condi-tions of relevance for geological disposal

Co-ordinator: Pierre Van Iseghem, SCK.CEN,[email protected]


To determine whether the observed behaviour of waste glassunder disposal conditions (see GLASTAB) is attributable to theselection of the experiments used to develop the models or to thechoice of hypotheses incorporated in the models. This concert-ed action was organised to allow mutual exchanges of experimen-tal work and models among the partners. It is expected to leadto a common European understanding on the approaches usedto model the observed dissolution rate decrease with time (com-bining retention, affinity and diffusion phenomena), and shouldallow quantification of the uncertainties arising from the choiceof one model rather than another.


30

GLASTAB

Title: Long-term behaviour of glass: improv-ing the glass term and substantiatingthe basic hypothesis

Co-ordinator: Isabelle Ribet, CEA, [email protected]


To improve knowledge of nuclear glass behaviour and increasethe dependability of source term models and predictionsunder representative repository conditions. Experimentalinvestigations covering the formation of the alteration gelthat develops when glass is exposed to water, the interactionof the glass with environmental materials such as clays or metalcanister corrosion products, and radionuclide retention inthe alteration products were combined with a two-track mod-elling approach: the first focused on the alteration rate andprovided a better understanding of phenomena responsible forthe rate decrease that is systematically observed during glassalteration; the second, an operational approach, has led to per-formance calculations that can be used by the safety author-ities, and has enhanced the degree of realism by limiting theoverly conservative aspects of the preceding approaches.

• The nature and properties of the glass alteration layer are high-ly dependent on both the glass composition and the alterationconditions (temperature, pH, water flow rate, etc.), and theyevolve with reaction progress. These observations were cor-roborated by studies of natural analogues of the alteration gels(palagonite). The formation of the alteration layer systema-tically corresponds to a significant drop in the glass alterationrate. Various models have been developed for the formationof the alteration gel and for the glass surface alteration rate.The methods range from microscopic approaches, such asMonte Carlo modelling, to macroscopic approaches combin-ing silicon retention in the gel, silicon diffusion in the gel andpossibly in the hydrated glass layer, and the onset of siliconsaturation at the glass/gel interface. Attempts have alsobeen made to model gel formation based on the use of geo-chemical models taking account of the formation of solid solu-tions and, from a texture standpoint, using coupled transport-chemistry models to describe the evolution of the gel porosity.The drop in the alteration rate is indeed modelled accordingto the alteration conditions, although it is still necessary touse empirical parameters.

• The presence of near-field materials – in particular clays –modifies glass alteration kinetics. A major effort has beenundertaken to characterise the properties of these materi-als in order to progress toward a coupled description of theglass evolution in contact with clay. Significant differencesin behaviour can be observed depending on the nature of thematerials. The main phenomena likely to account for theeffects of clay are silicon sorption on the clay and the pre-cipitation of secondary phases containing silicon.Nevertheless, these phenomena do not prevent very lowglass alteration rates from being reached after a time peri-od that depends on the quantity of clay involved.

• Sorption and co-precipitation are two major phenomenaconsidered as accounting for radionuclide retention in theglass alteration products. Experiments in complex glass-gel-solution systems have confirmed that the behaviour of ele-ments and the predominant sorption mechanism depend onthe physicochemical conditions: trivalent elements releasedby glass dissolution are incorporated by (ad)sorption ongels at near-neutral pH. Under basic pH, there is competi-tion between adsorption and aqueous carbonate complex-ation, leading to decreased retention (the solubility-limitingphases could be carbonates). In MgCl2 brines, the pre-dominant sorption mechanism is ion exchange (low efficien-cy). Over the long term, the behaviour of actinides and lan-thanides is controlled by the precipitation of poorly solublemineral phases.

All the results were incorporated into an overall view of glassperformance to substantiate the hypotheses supporting theoperational models of glass alteration: these are simple,robust models with varying degrees of realism, to be coupledwith environmental models for performance assessment cal-culations. The conclusion is that glass performance is high-ly dependent on the reactivity of the surrounding environment,on the residual alteration rate (i.e. the rate observed over thevery long term), and on the hypotheses postulated concern-ing the repository constituents that must be taken into account.Performance assessments have shown that when the alterationconditions are compatible with the onset of a residual rate,the overall performance of the repository is directly related toperformance of the glass itself: its low alteration rate controlsthe release of radionuclides from the site.


IN-CAN PROCESSES

Title: Rates and mechanisms of radioactiverelease and retention inside a wastedisposal canister

Co-ordinator: Mark Cowper, NuclearTechnology plc, [email protected]


To examine the interactions between spent fuel radiolytic dis-solution and container corrosion, in terms of the effect ofhydrogen overpressure, the retention capability of the corrosionproducts, and the influence of corrosion products on the redoxbalance within the container. Experimental work was carried outon both simulated materials (alpha-doped UO2 simulating oldfuels) and irradiated fuels using, in particular, the isotopicdilution method to attempt to measure very low dissolution rates.More fundamental approaches were used to understand thechemical reactivity of Fe(II) towards U(VI) and Np(V) by devel-oping RIXS measurements and quantum mechanics calculations.Data on experiments involving uranium dioxide and alpha-doped uranium dioxide were compared with dissolution rates ofspent fuel (with the additional effects of beta and gamma radi-ation doses) under anaerobic conditions using a hydrogen gasatmosphere. In the presence of iron, the dissolution rates arevery low and current values used in safety assessments are

conservative. Furthermore, the solubility of uranium dioxide isalso very low in the presence of iron, with uranium solution con-centrations measured of less than 0.02ppb – significantlylower than previously published data in the scientific literature.The second part of the programme, a study of the potential ofactively corroding iron to reduce oxidised aqueous U(VI) andNp(V) species to less soluble U(IV) and Np(IV), involved the devel-opment and use of an innovative electrochemical cell. There wasalso a significant development where RIXS – resonant inelas-tic soft X-ray scattering – spectroscopy was used to study andmeasure quantitatively the reduction of aqueous U and Npspecies on to the corroding iron surface. U(VI) reduction can occurin solution instead of at the solid surface, and carbonate com-plexes are reduced at a quicker rate than hydroxyl complexes.These results were in agreement with a new computer modelthat calculated from first principles the expected reaction path,and the relative reaction rate for the reduction of U(VI) to U(IV)and Np(V) to Np(IV) in solutions with various ligands. These datashow that even if more oxidised (and more soluble) U(VI) andNp(V) species are released into solution from the waste form byradiolysis reactions, the reducing conditions present due to thecanister materials are sufficient to reduce them to less solubleproducts, significantly reducing the inventory of U and Np inthe groundwaters that flow away from the repository through thehost rock. This will reduce the expected dose to the far field andhas significant implications for current performance assessmentmodels for high-level waste disposal that do not take intoaccount the indirect contribution from canister materials.

SFS

Title: Spent fuel stability under repositoryconditions

Co-ordinator: Jean-Marc Cavedon, CEA, [email protected]


To identify the processes controlling spent fuel alteration in thenear-field environment of a deep geological repository, whichwill act as reference input data for national geological

disposal performance assessment exercises. The project aimsto obtain a reliable radionuclide source term, including theinstantaneous release fraction (IRF) of radionuclides at the timeof water ingress and the much slower release from matrix dis-solution. The focus is on (i) the potential increase with timeof the IRF due to intrinsic spent fuel evolution before wateringress; and (ii) the matrix radiolytic dissolution process, forwhich no shared alteration model is yet available. Experimentson simulated samples, as well as irradiated uranium oxide andMOX fuels, were carried out in both saline and argillaceous con-ditions. Significant focus has been put on the effect of hydro-gen on the radiolytic process.


32

Safety assessment of geological disposal

BENIPA

Title: Bentonite barriers in integrated per-formance assessment

Co-ordinator: Jesus Alonso, ENRESA, [email protected]


To assess the state of the art in the treatment of bentonite bar-riers in Integrated Performance Assessment, evaluating themethods and data available to justify convincingly the capac-ity of bentonite to perform its assigned safety functions. Anin-depth analysis and cross comparison has been made of thedifferent models available for the numerical simulation of thebehaviour of bentonite barriers at different levels of detail. Theconsistency and availability of data needed by the models hasbeen evaluated. The overall result is a better understandingof the modelling and computer programs related to the per-formance of bentonite barriers. Numerical simulations havealso been carried out at both process and integrated levels withrespect to hydraulic, mechanical, chemical and transportprocesses. Modelling at process level included reactive trans-port, especially to assess the effects of cementitious degra-dation products on bentonite minerals, coupled T-H-M mod-elling, including the growth of canister corrosion products, and

radionuclide transport associated with colloids potentiallygenerated by bentonite barriers. For repositories in crystallinerock, the project studies confirmed that as long as the bufferis in place and functions as a diffusion barrier, the release ratesof radionuclides from the near field to the geosphere remainlow. The simulations indicate that these rates are very sensi-tive to the water-flow rate around the buffer and much less sen-sitive to the transport parameters in the bentonite, and are notaffected much by changes of the buffer thickness. For arepository in a clay layer, the host rock normally acts as a hugebuffer around the engineered barrier. Under the expectedconditions, the contribution of the advection in the surround-ing rock is very small, with the emplacement tunnels effec-tively sealed and a low vertical hydraulic gradient, the over-all contribution of the bentonite to ensure low release ofradionuclides is very small. This is because the host rock aboveand below the repository horizon is an extremely effective trans-port barrier, with very low permeability and good sorptionproperties. Overall, bentonite barriers are able to ensure thattransport in the near field is controlled by diffusion. Their resat-uration is expected to be completed in a few years whiletemperatures and stresses remain within moderate ranges. Theeffect of canister corrosion products should be investigatedfurther. Chemical conditions evolve smoothly, but importantuncertainties remain in the presence of cementitious products.The final report on the project has been published underEUR 21023.

BENCHPAR

Title: Benchmark tests and guidance oncoupled processes for performanceassessment of nuclear waste repositories

Co-ordinator: Herbert Henkel, KTH, [email protected]


To improve the thermo-hydro-mechanical (THM) coupled process-es models used in radioactive waste repository performance andsafety assessment. The methodology for conducting technicalauditing for THM modelling was successfully developed via aquestionnaire. In the near-field rock-buffer system, a series ofTHM analysis was performed on homogeneous and fractured rockmasses. The importance of the couplings on the safety indica-tors was evaluated by comparing the THM calculations to par-tially coupled ones (e.g. TM, TH, HM). Coupling is most impor-tant in the short term (less than 100 years) and it has beenconcluded that for confidence building and demonstration

purposes, a fully coupled approach is necessary to interpret mon-itoring data correctly that would be collected after repository clo-sure. In the upscaling exercise, methodologies and numericaltechniques were developed to determine upscaled H, M and HMproperties of highly fractured rocks in two and three dimensions.This demonstrated the impact of stress on permeability undera range of stress conditions. The possibility of increased per-meability and enhanced permeability anisotropy under high-stressratios was recognised for the first time. The results showed theneed to acquire very precise fracture geometry data, whichemphasises close co-operation between site characterisation andthe ultimate users of the data for design and safety analysis ofa repository. A synthetic exercise was conducted describing HMconditions during the dynamics of a glaciation cycle. Importantcoupling to the behaviour of glaciated terrain systems wasidentified and large-scale deformations and strength of therock mass were investigated. Modelling of glacial sheet and per-mafrost were performed and differences between coastal andinland sites identified.

Further information available at: http://www.benchpar.com

Geological Disposal of RadioactiveWastes Produced by Nuclear Power ... from concept to implementation 33

BioMoSA

Title: Biosphere models for safety assessmentof radioactive waste disposals based onthe application of the reference bios-phere methodology

Co-ordinator: Gerhard Pröhl, GSF, [email protected]


To develop and compare results of generic and site-specificassessment models that were developed for five Europeansites in Belgium, Germany, Hungary, Spain and Sweden, cov-ering a wide range of living habits and agricultural and climat-ic conditions. Guidance in model development was given by theReference Biosphere Methodology that was developed within

the IAEA BIOMASS programme. The main objectives ofBioMoSA are: • To identify common and site-specific features, events and

processes (FEPs) that need to be modelled• To identify principal fundamental differences between dif-

ferent sites• To compare the results and quantify the variability of site-

specific models • To conclude a generic biosphere tool for application in long-

term safety studies• To provide guidance on how detailed specific sites have to

be modelled in order to achieve credible and sufficiently reli-able results in long-term performance assessment studies

• To identify the possibilities and limitations for applying thegeneric biosphere tool in different national contexts

• To provide guidance for application of the generic biospheretool to real sites.

BIOCLIM

Title: Modelling sequential biosphere systemsunder climate change for radioactivewaste disposal

Co-ordinator: Delphine Texier, ANDRA, [email protected]


To provide a scientific basis and practical methodology forassessing the potential impacts of long-term climate changeon biosphere characteristics in the context of radiologicalperformance assessments (PA) of radioactive waste repositor-ies in deep geological formations. Climate models that can sim-ulate future climate changes in Europe over very long timescaleshave been developed and their results linked to an understand-ing of the pattern of biosphere changes for five selectedEuropean regions, in order to address the issue of how to rep-resent future biosphere systems in long-term radiological per-formance assessments. The project was designed to advancethe state-of-the-art of biosphere modelling in four steps:• Step 1: summarise information on issues that have to be

addressed when considering climate change impacts onrepository safety, and the current methods used to representenvironmental change in repository safety assessments.

• Step 2: use a hierarchy of climate models to derive the cli-matic changes for selected discrete time periods of interestto radioactive waste management (i.e. selected time slicesduring glacial and interglacial periods). The outputs fromthese models consist of climate and vegetation cover sce-narios for selected time periods in the future. Statistical down-scaling approaches have been developed and evaluated toenable climate model output for large areas to be downscaledto more appropriate scales for the regions of interest.

• Step 3: develop and apply integrated, dynamic climatemodels, representing all the mechanisms important forlong-term climatic variations such as atmospheric forcing,ice-sheet development and ocean changes. The time-depend-ent results from these models have been interpreted interms of regional climate evolution using a set of downscal-ing methodologies.

• Step 4: interpret the complementary outputs from Step 2and 3 in terms of model requirements for the post-closureradiological performance assessment of deep geologicalrepositories for radioactive wastes. To develop a methodo-logy to demonstrate how biosphere systems can be represent-ed in the long term.

Further information available at: http://www.andra.fr/bioclim/

BIOCLIM

Title: Modelling SequentialBiosphere Systems underClimate Change forRadioactive Waste Disposal

Co-ordinator: Delphine Texier,ANDRA, France

[email protected]


To provide a scientific basis and practical methodology forassessing the potential impacts of long-term climate changeon biosphere characteristics in the context of radiologicalperformance assessments (PA) of radioactive waste reposito-ries in deep geological formations. Climate models that cansimulate future climate changes in Europe over very longtimescales have been developed and their results linked to anunderstanding of the pattern of biosphere changes for fiveselected European regions, in order to address the issue of howto represent future biosphere systems in long-term radiolog-ical performance assessments. The project was designed toadvance the state-of-the-art of biosphere modelling in foursteps:• Step 1: summarise information on issues that have to be

addressed when considering climate change impacts onrepository safety, and the current methods used to representenvironmental change in repository safety assessments.

• Step 2: use a hierarchy of climate models to derive the cli-matic changes for selected discrete time periods of interestto radioactive waste management (i.e. selected time slicesduring glacial and interglacial periods). The outputs fromthese models consist of climate and vegetation cover sce-narios for selected time periods in the future. Statistical down-


34

ECOCLAY II

Title: Effects of cement on clay barrier per-formance

Co-ordinator: Nicolas Michau, ANDRA, [email protected]


To understand the physico-chemical behaviour of argillaceousand granitic materials altered by the effects of a hyperalkaline

plume, and assess the evolution of the confinement perform-ances of these materials, a series of laboratory tests and analy-sis. Data was acquired on sorption and migration of radionu-clides, on mineralogical transformations and modifications tothe properties of bentonite, of clay and crystalline host rocksin contact with either alkaline fluids or different kinds ofcement. Hydrogeochemical modelling sought to define and opti-mise a model for hyperalkaline alteration. Simulations weremade of the long-term behaviour of clay and crystalline rockunder the effect of an hyperalkaline plume, and a performanceassessment study was carried out.

SPIN

Title: Testing of safety and performance indi-cators

Co-ordinator: Dirk-Alexander Becker, GRS,[email protected]


To identify and test safety and performance indicators. The indi-cators have been tested by recalculating existing performanceassessments of disposal systems for high-level waste in crys-talline formations in Spain, Germany, Finland and Switzerland.The three proposed safety indicators and their preferred appli-cation to time frames are: effective dose rate – most relevantto early time frames; radiotoxicity concentration in biospherewater – preference for medium time frames; radiotoxicity fluxfrom geosphere – preference for late time frames. For theeffective dose rate, the data from present regulations were usedas a range of reference values. Reference values for radiotox-icity concentration and fluxes were taken from natural environ-ments that are known to be radiologically safe. The project

concluded that several performance indicators can be used toshow different aspects of the functioning of the individual com-partments of the multi-barrier system. These indicators and theirpreferred applications are: (1) inventories in compartments:showing where the radionuclides are at different points intime, and the retention of radionuclides from the biosphere;(2) fluxes from compartments: showing the decreasing releaserates from successive compartments, including radioactivedecay and ingrowth, and the delayed release; (3) time-integrat-ed fluxes from compartments: showing decay during delayedtransport; (4) concentrations in compartment water: showingthe decrease of concentration by dilution, dispersion anddecay in successive compartments; and (5) transport timesthrough compartments: showing the potential importance of indi-vidual radionuclides to the release of radiotoxicity by compar-ing them to their half-lives. For investigations relating to thetotal radionuclide spectrum, performance indicators based onradiotoxicity should be used. For single-nuclide investigations,activity-based indicators can be used. The final report on theproject has been published under EUR 19965.


Groundwater and radionuclide movementaround repositories

ACTAF

Title: Aquatic chemistry and thermodynamicsof actinides and fission products rele-vant to nuclear waste disposal

Co-ordinator: Reinhard Klenze, FZK, [email protected]


To generate basic thermodynamic data for the actinides withrespect to both dissolved and mineral-bound species. A notablebreakthrough was the filling of serious gaps in the database fortetravalent actinides. Understanding actinide complexationwith small organic ligands, which may serve as a model com-pound for natural organic matter, has been substantiallyincreased using various spectroscopic methods and theoreti-cal approaches. For the first time, computational methods(molecular modelling) have been applied to chemical problemsrelated to nuclear waste disposal. It is envisaged that quantumchemical tools will play an important role for future investiga-tions on the co-ordination chemistry and thermodynamic ofactinides in natural aquatic systems. The co-operation of dif-ferent laboratories with expertise in either spectroscopic

actinide speciation or profound experience in modelling sur-face sorption reactions provided an improved understanding ofactinide interaction at the mineral/groundwater interface.Mechanistic insight into the sorption of U(VI) on iron oxides,including surface-enhanced redox reactions, has been achievedas well as the elucidation of the speciation of trivalent actinidessorbed on to alumina and clay minerals. The first applicationof the grazing incidence X-ray absorption spectroscopy (GIX-AFS) represents a huge step forward towards the spectroscop-ic characterisation of surface sorbed actinides at even trace con-centration level. For the prediction of the U(VI)sorption ontorock minerals, a ‘composite’ model has been parameterised suc-cessfully using sorption data derived for the mineralogicalrock constituents. The combination of wet chemical methods,surface analysis and spectroscopic techniques helped toimprove the basic understanding of solid solution formation ofactinides in calcite, cement degradation secondary phasesand phosphates. Such mineralisation processes are believedto be of cardinal importance for the actinide reactions in thenear- and far-field of a nuclear waste repository. The resultsgained in the ACTAF project indicate that inclusion in second-ary phases can lead to strong actinide retention in the repos-itory or the surrounding geosphere.

BORIS

Title: Building confidence in deep disposal:the borehole injection sites at Tomsk-7and Krasnoyarsk-26

Co-ordinator: Stephen Wickham, GalsonSciences, [email protected]


To utilise data from real examples of radionuclide movement

in the deep underground, to improve understanding of theprocesses involved, that can then be transferred to perform-ance assessment of deep geological repositories. Two sites inRussia – Krasnoyarsk-26 and Tomsk-7 – where liquid wasteshad been injected were used for the study. The results indi-cated that clay layers formed an effective barrier to verticalmigration of radionuclides, that groundwater sampled only afew metres away from waste injection points has significant-ly reduced levels of radioactivity compared with the originalinjection solutions, and that colloids and naturally present bac-terial populations occur in the groundwaters and could influ-ence radionuclide transport processes. The final report on theproject has been published under EUR 20615.

HUPA

Title: Effects of Humic Substances on theMigration of Radionuclides:Complexation and Transport of Actinides

Co-ordinator: Gunnar Buckau, FZK, [email protected]


To quantify the impact of humic colloid mediated transport forthe assessment of the long-term safety of nuclear waste dis-posal. For this purpose, actinide ions are being studied and therequired database is complemented to generate data for theinteraction of actinides and iodine with dissolved and surface-bound humic substances. The overall approach is to generateknowledge and process understanding for the generation ofhumic substances under natural conditions, as well as the gen-eration from clay organic matter under perturbed geochemicalconditions in the near-field.



36

RETROCK

Title: Treatment of geosphere retentionphenomena in safety assessments

Co-ordinator: Mikko Nykyri, Safram Oy,[email protected]


To examine how the retention and transport of radionuclidesare and should be recognised in PA models for deep geologi-cal repositories in saturated hard fractured rock. The project judges in depth the available concepts, their applicabil-ity for simplified PA models, and seeks the proper measuring

approaches and data abstraction schemes (data “up-scaling”)for the utilisation of experimental data. The main focus is onexamining whether simplifications frequently adopted in PAscan be defended with more complex process models, experi-ments, and other scientific knowledge bases. Information wassolicited through a questionnaire. In the next stage, the sci-entific basis of the modelling concepts, their applicability forintegrated PA models, measuring approaches and data up-scal-ing for the utilisation of the experimental data were evaluat-ed. In-depth discussions examined the most important and con-tentious concepts. An additional aim is to enhance thecommunication between the various disciplines, especiallybetween PA modellers and other researchers. RETROCK hasalready directed attention to a number of PA modelling issuesthat probably require future developments.

PADAMOT

Title: Palaeohydrogeological data analysis andmodel testing

Co-ordinator: Paul Degnan, NIREX, [email protected]


Because the long-term safety of an underground repositorydepends on the continued performance of the repositoryenvironment, in- sufficiently isolating the wastes and atten-uating any releases, demonstrating that climatic impacts donot degrade containment properties is important. Scenariosfor groundwater evolution relating to climate change are cur-rently poorly constrained by data and process understanding.There is some criticism that current hydrogeological modelsare over simplified and do not address the full variabilityinherent in natural systems over time. PADAMOT is using min-eralogical and hydrochemical data to investigate changes ingroundwater conditions over time, as a result of changing cli-mate, to develop improved process understanding and processmodels from these quantitative data. This work includesinnovative modelling of reactions coupled with transport.

Minerals and groundwater at sites in Spain, the Czech Republic,Sweden and the UK are being investigated to relate their evo-lution to the environmental record. Isotopic signatures of frac-ture minerals from near-surface rocks are being compared withdeep fracture minerals to find out the differences betweendeep and shallow impacts of past environmental conditions.Samples are being used to evaluate analytical techniques thatwere not previously available, e.g. ion probe and laser ablation.These new techniques are helping PADAMOT scientists to dis-tinguish between specific groundwater episodes. It is anticipat-ed that the data will give information that will enable zones tobe compared with the chronology of past climatic events.

Results will provide guidance and data on varying geosphereconditions in response to changing environmental conditionsand climate. Knowledge will be interpreted and synthesisedin order that it can have direct application to safety assess-ments. The enhanced understanding will have generic valuefor all radioactive waste management agencies and regulators,as well as site-specific significance.

Further information available at:http://www.bgs.ac.uk/padamot


TRANCOM II

Title: Transport of radionuclides due tocomplexation with organic matter inclay formations

Co-ordinator: Norbert Maes, SCK.CEN,[email protected]


To develop and demonstrate a conceptual model for thedescription of the migration of radionuclides in natural organ-ic matter (NOM) rich, chemically reducing clay environments(using the Boom clay) that can be implemented in performanceassessment models. The project addresses the migrationbehaviour of radionuclides identified as important for longterm safety (U, Se, Pu). The transport mechanism of theradionuclide species studied is mainly dominated by an immo-bilisation process (reduction-precipitation in case of U and Se,or a strong quasi-irreversible interaction with the solid phasefor Am) combined with a constant release of a low concentra-tion of the radionuclide. For Se and U, constant release is con-trolled by a solubility limit of the precipitated phases and the

transport is independent of NOM. The dominant effect ofNOM on U was the formation of colloids. The formation of organ-ic complexes could not be demonstrated. These colloids (> 2nm) did not increase the U mobility as they were immobilisedin the host formation by ultrafiltration. Am (analogue for triva-lent Pu) becomes immobilised upon interaction with the claysolid phase but this is not controlled by solubility. Am complex-es easily with mobile NOM, but upon interaction with theclay, the bulk of these complexes dissociate instantaneouslyand only a small part persists as a “stabilised” complex withslow dissociation kinetics. In the presence of an Am inorgan-ic solid source, this results in a constant release of “sta-bilised” Am-OM complexes at a concentration level someorders of magnitude lower than its solubility. For Pu, theunderlying processes are not understood and the questionremains whether Pu will be present as Pu(IV) or Pu(III) underreducing clay conditions but the behaviour in the migrationexperiments resembles that of Am. Colloids were found to beeither unstable in, or filtered by, the Boom clay. A transportmodel, POPCORN, was developed to describe and evaluate theinfluence of NOM on radionuclide transport in clay. The meth-ods, results and conceptual models developed for the Boom clayalso serve as a reference for other clay formations and wastetypes (chemo-toxic wastes). The final report on the project hasbeen published under EUR 21022.


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Public involvement in repository programmes

COWAM

Title: Nuclear waste management from a localperspective

Co-ordinator: Gilles Heriard-Dubreuil,MUTADIS Consultants, [email protected]


To empower local actors through a networking process betweendifferent local contexts, countries and cultures; to gather anddiscuss the experiences of decision-making processes at thelocal level within their national context in Europe; to set upan arena for balanced exchanges between local actors, NGOs,regulators and implementers; and to promote new approach-es to decision-making in national contexts in Europe. Two hun-dred and thirty delegates from ten countries met. Thirty local

communities were involved and local communities and NGOsrepresented 65% of the audience. In each seminar, casestudies in different local and national contexts were reviewed.They were presented by people coming from different positionsand playing different roles in the decision-making process. Fivemain issues were identified: local democracy; expertise in thelocal decision-making process; influence of the local actorson the national nuclear waste management framework; region-al development policy; and site selection process. Local peo-ple and representatives are interested in playing an active rolein the discussions over nuclear waste management issues. Theusual technical divisions between types of waste or betweenoptions are not very relevant when trying to understand theissues faced by communities. This sharing of experiencepoints out good practices which can be adapted from one coun-try to another or used to stimulate local empowerment.

The conclusions are available at:http://www.cowam.com/final.htm

RISCOM II

Title: Enhancing transparency and public par-ticipation in nuclear waste management

Co-ordinator: Magnus Westerlind, SKI,[email protected]


To support transparency of decision-making processes bymeans of a greater degree of public participation. The find-ings are expected to be relevant for decision-making in com-plex policy issues in a much wider context. Performanceassessment (PA) in particular has been an activity whereexperts communicate with other experts. Now, the users of PA

have widened to include members of the public, concernedgroups and communities involved in site selection processes.The experts thus have to communicate facts and values withstakeholders and decision-makers. As regulatory standards andcriteria set the framework for PA, it is important to openthem up for public input. It was shown by organised hearingsthat the RISCOM model can be used to support the design ofpublic events and decision processes for the sake of transparen-cy. The project found that evidence from dialogue processessuggests that the actual use made of information is minimal.This suggests that great care should be taken in targeting infor-mation resources where they will be most useful. A nuclearwaste management programme must have resources to allowfor citizen participation. Proper resources will encourage pos-itive engagement, improve decision-making, and increasepublic confidence.


Thematic Networks

ACTINET

Title: Network of excellence for actinidesciences

Co-ordinator: Jae-Il Kim, FZK, [email protected]


To sustain and disseminate knowledge and expertise, as wellas to maintain a threshold level of research activity in actinidesciences in Europe. This particular research area requires rein-forced links between national nuclear research institutes, theJRC, and radiochemistry laboratories of a number of aca-demic research organisations: networking will not only facil-itate the co-ordination and utilisation of available facilities,but will also consolidate, optimise, and give the necessary impe-tus to enliven the research and training activities in actinidesciences in Europe. The Thematic Network ACTINET hasbeen used to launch a sustainable network gathering a num-ber of institutions from large national laboratories to univer-sity departments, within the broad area of actinide science,with the following objectives for FP6:

• significantly improve the accessibility of the major actinidefacilities to the European scientific community, and form aset of pooled facilities that will evolve to a multi-site user facil-ity, as the cornerstone of a progressive integration process

• improve mobility between the ACTINET member institutions,in particular between academic institutions and national lab-oratories holding the pooled facilities, facilitate mobility ofyoung researchers within the Network, and promote doctor-ate students

• merge part of the research programmes conducted by themember institutions, and optimise the research programmesand infrastructure policy via the ACTINET managementprocedures

• strengthen European excellence through the internal selec-tion process of the joint programme proposals, and reducethe fragmentation of the community by putting criticalmass of resources and expertise on shared challenges, inorder for Europe to remain or become a world force in thefields of actinide sciences

• disseminate knowledge on actinide sciences through vari-ous databases, communications in workshops and sem-inars, and joint activation of research tools (e.g. modellingand code development).

COMPAS

Title: Comparison of alternative wastemanagement strategies for long-livedradioactive wastes

Co-ordinator: Mark Dutton, NNC Ltd, [email protected]


To compare strategies that have been adopted or are beingconsidered for the management of spent nuclear fuel and long-lived radioactive waste, involving individuals from the wastemanagement organisations of 15 countries. The project wasorganised around a series of four workshops. At each ofthese, the strategies, approaches and data relevant to eachcountry were presented and discussed. The first workshopaddressed the historical basis of the existing waste, its cat-egorisation and the amount of spent nuclear fuel and waste

that will have to be managed as a result of the existingnuclear power programmes and the other sources of radioac-tive waste. The roles of reprocessing and partition and trans-formation in affecting the waste to be managed were alsoaddressed. The second workshop looked at the issues thatdetermine the strategies that had been adopted or werebeing considered by each country. These included interna-tional treaties, European directives, technical and financialissues as well ethical issues. The third workshop determinedwhich issues affected key decision points in the managementof the fuel and materials in both the short- and long-term.It also identified the generic strategies that are being imple-mented or being considered and the reasons for them. Thefinal workshop identified the key issues that affect the suc-cess or otherwise of implementing a long-term managementsolution, such as a repository, and, based on the experienceof the participating counties, identified the key aspects of theprocess leading up to a successful selection of a site. Otherissues, such as the potential use of multi-national reposito-ries were also addressed. The final report on the project hasbeen published under EUR 21021.



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CROP

Title: The cluster repository project



To review and collect information on design, constructionand modelling of engineered barrier systems (EBS) as well ason experimental procedures within various types of geologi-cal environments in nine networking countries.

Several national underground research laboratories (URLs) forstudying the possibility of safe deep disposal of radioactivewaste have been in operation for different periods of time andhave formed the "Cluster" of URLs in this project. They rep-resent various geological media, such as crystalline rock inSweden (Stripa and Äspö), Finland (Olkiluoto), Switzerland

(Grimsel) and Canada (Pinawa), bedded salt and salt domesin the United States of America (WIPP) and Germany (Asse),respectively, and sedimentary clay formations in Belgium(Mol), France (Bure) and Switzerland (Mt. Terri). The variousgeological situations have led to different design and instru-mentation of the aforementioned URLs. However, the engi-neered barriers have a similar function and, despite some obvi-ous differences, many of the solutions and techniques arebelieved to be applicable to disposal concepts in various rocktypes. The results from tests conducted in many different geo-logical media and involving a large number of engineered bar-rier system components are expected to be valuable to all organ-isations involved in repository development.

The project notes that all studied repository concepts fulfil veryhigh demands on long-term safety, and reports on areas wherelessons have been learned, issues remain, and has indicatedareas of high potential for technical improvements of repos-itory concepts and the testing of them.

MONITORING

Title: Monitoring in a Stage Approach toDisposal

Co-ordinator: Steve Barlow, Nirex, [email protected]


To improve the understanding of and the options for monitor-ing within a phased disposal concept and to identify how mon-itoring can contribute to decision-making, operational and post-closure safety, and overall confidence in safety. The chosenmethodology will be motivated by the monitoring needs at eachstep of a phased approach, but constrained by technical

difficulties and by the available technology. The aim of mon-itoring is to provide information for making decisions. This couldinclude: acceptability of operating conditions for personnel andgeneral population; provision of an environmental database onthe site and its surroundings for current and future generations;confirmation of the understanding of some aspects of systembehaviour used in developing the safety case, and to allow fur-ther testing of assessment models or provision of additionalinformation to give society confidence to take decisions on themajor stages of the repository development programme. It willalso strengthen confidence, for as long as society requires thatthe repository has no undesirable impacts after closure. Indetermining the duration of certain monitoring activities, theevolution of the repository needs to be considered, as well asthis societal component. The final report on the project hasbeen published under EUR 21025.


NET EXCEL

Title: Networking for research on radioactivewaste geological disposal



Concerns the forming of a network of European end-users foranalysing the present status and future needs in research, tech-nological development and demonstration (RTD) for the dis-posal of highly radioactive waste in the three classical rockmedia: salt, clay/clay sediments and crystalline rock. Theaim is to generate value additional to that gained by the indi-vidual participants. The expected results of the project are acommon and systematic basis for prioritisation and co-ordi-nation of future European research and development work forradioactive waste management, and suggested areas and pri-orities for joint European projects.

In general, there are differences in the type of high-level and

long-lived radioactive waste (for instance, either spent fuel orvitrified waste if the reprocessing option is considered byutilities) that the participating organisations have responsibil-ities for, and the time schedules for their work. The nationalregulatory framework may also induce some differences. Oneof the initial issues of the project is to shed light on therationale for these observed differences.

In contrast, the practical way to carry out the necessary RTDactivities and the principles behind the process is to estab-lish priorities for the necessary RTD-work is quite similar.Common ground is analysed for the role/responsibilities of theparticipating organisations, for the establishment of prioritiesfor the RTD work, and for the modus operandi of the organi-sations to carry out the RTD. The issue of prioritising the poten-tial RTD activities is addressed and the factors taken intoaccount by the participating organisations have been sum-marised and analysed with respect to the common denomi-nator in the project. The expected results of the project area common and systematic basis for prioritisation and co-ordination of future European research and development workfor radioactive waste management, and suggested areas andpriorities for joint European projects.

GASNET

Title: Gas issues in safety assessment of deeprepositories for radioactive waste

Co-ordinator: Simon Norris, Nirex, [email protected]


To evaluate the present treatment of gas issues in safetyassessments of deep geological repositories for radioactivewaste, and to improve the translation of scientific informationon these issues into safety arguments for such repositories.The emphasis of the work was on the requirements of safetycases rather than on reviewing understanding of gas genera-tion and migration processes, as this had already beenaddressed in recent work that provided the background to theGASNET project.

The end result of the project is a report that documents thecurrent approaches used in dealing with gas issues in safetyassessments and the strengths and limitations of these

approaches. By considering the general requirements fordealing with gas issues in safety cases, the work was alsointended to strengthen the foundation for assessing gas issuesin safety assessments. The final report considers require-ments for the treatment of gas issues in the context of a safe-ty case for a deep repository, with documentation of currentapproaches and discussion of the strengths and limitations ofthese approaches, where appropriate. Only the effects of gasgeneration after repository closure from the wastes and repos-itory construction materials that are present are specificallyaddressed, although the influence of processes occurringprior to closure on the inventory of gas-generating materialsremaining at closure, does fall within the scope of the study.The concluding section of the report contains a summary ofthe principal general uncertainties identified in the GASNETproject in assessing the effects of gas generation in reposito-ries, and of those gas-related issues for which it currentlyremains difficult to provide a satisfactorily robust treatment.The final report on the project has been published underEUR 20620.


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NAnet

Title: Natural analogue studies and theirapplications to repository safety assess-ment and public communication

Co-ordinator: Bill Miller, ENVIROS Ltd, [email protected]


To review past and present use and understanding of naturalanalogues with the intention of promoting more consideredapplications of them in future safety assessments and for pub-lic communication. This involves a comprehensive and criti-cal re-examination of published studies.

In addition to true 'natural' analogues, the NAnet project alsoconsiders archaeological and industrial analogues (e.g. thedegradation of old man-made materials) and anthropogenicanalogues (e.g. where radionuclides have been deliberately oraccidentally released into deep or shallow environments).

The scope of the project includes analogues that are relevantto the most common radioactive waste repository design andconcepts, including surface and near-surface repositories forLLW and deep repositories for HLW or ILW. The project con-siders the potential wide-ranging applications of qualitative andquantitative analogues information to safety cases whichemploy multiple lines of reasoning, rather than just to the morerestricted scope of mathematically based radiological perform-ance assessments. The project also examines attempts thathave previously been made to use natural analogues to com-municate with the stakeholders on radioactive waste manage-ment issues.

In the light of this, NAnet has a clear aim of recommendinghow a more thorough use and understanding of analogues infuture safety assessments can be achieved and how better util-isation in terms of 'added value' is possible from previous ana-logue studies.

Further information available at:http://www.enviros.com/zztop/nanet/

European Commission

EUR 21224 – Geological Disposal of Radioactive Wastes Produced by Nuclear Power

Luxembourg: Office for Official Publications of the European Communities

2004 – 42 pp. – 21.0 x 29.7 cm

ISBN 92-894-8090-4

15K

I-NA

-21224-EN

-C

geological disposal of radioactive wastes produced by...

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