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ISO Standard of Waste Activity Evaluation Method for Contaminated and Activated waste

November / 2012, IAEA LABONET in Brussels, Belgium M. Kashiwagi

Copyright 2012 JGC all rights reserved

Developing Activity Evaluation Method for DTM nuclides: Application method and Target waste

1

Main Activity Evaluation

method

Target wastes

Waste Examples

ISOStandard

Empirical method:Scaling factor method(SF method)

Contaminated waste

Concentratedliquid, Spent resin, DAW, etc.

ISO21238-2007

Theoretical method:Activation calculation method

Activated waste

Control rod, Channel box, Burnable poison, etc.

ISO16966(DIS)Under

developing

DTM nuclides: Difficult to measure nuclides such as C-14, Nb-94, α emittersDIS: Draft of International Standard (Now voting)


ISO Standard(ISO21238:2007)

IAEA Document(NW-T-1.18:2009)

ISO21238 was published in April 2007. NW-T-1.18 was published in 2009.

“Scaling factor method for L& ILW generated at NPP”

“Determination and Use of Scaling Factors for Waste Characterizationin NPPs”

Property:Text book, Examples

Property:Basic Manual

(Describe basic methodology) (Gathering many country’s practices)

Published ISO International standard and IAEA technical document for SF method


ISO Standardization: ISO21238 Member of Project Team for Developing ISO Standard of SF Method

3

NNoo IISSOO PPaarrttiicciippaanntt CCoouunnttrryy TTCC8855 SSCC55 PPrroojjeecctt TTeeaamm 1 Argentina (IRAM) ○ ○ ○ CNEA, NRA 2 Belgium (IBN) ○ ○ ○ ELECTRABEL 3 Canada (SCC) ○ ○ ○ OPG 4 China (SAC) ○ ○ -- -- 5 France (AFNOR) ● ○ ○ EDF 6 Italy (UNI) ○ ○ -- -- 7 Japan (JISC) ○ ○ ● TEPCO, JJGGCC 8 Kenya (KEBS) ○ ○ -- -- 9 Korea (KATS) ○ ○ -- -- 10 Russian Federation(GOST R) ○ ○ -- -- 11 Spain (AENOR) ○ ○ ○ ENRESA 12 Sweden (SIS) ○ ○ ○ SKB, Ringhals 13 United Kingdom (BSI) ○ ● ○ BE, BNFL, UKAEA 14 USA (ANSI) ○ ○ ○ EPRI, Consultant 15 Austria (ON) ○ -- -- -- 16 Bulgaria (BDS) ○ -- -- -- 17 Switzerland (SNV) ○ -- ○ NAGRA 18 Netherlands(NEN) -- ○ ○ NRG, NEN 19 Germany (DIN) -- -- ○ ISTec

Project team was consisted of Nominated experts from 19 institutes from 12 countries.

●: Convener○: Participant member

TC85: Nuclear Energy

SC5: Nuclear fuel cycle


Scope : ISO Standard of Scaling Factor Method

4

Radioactivity of

DTM nuclide

Sampling andRadiochemical

analysis of Radioactive

waste

DTM Nuclide

Key Nuclide

Evaluation of the data

Correlation is confirmed

Value of SF(DTM / Key

nuclide)

SF

Non- destructive measurement

Radioactivity ofKey nuclide

(Co-60,Cs-137)

Individual Waste

package

Waste package

scan

rotation

DTM: Difficult to measure nuclide(such as C-14, Ni-63 etc.)

ISO21238 covered these parts.

ISO14850 covered


ISO 21238:2007Contents of ISO Standard of SF Method for L/ILW

Chapter 1. - 3. Common item

Chapter 4. Sampling4.1 Representative sampling4.2 Rejection of outlier4.3 Record of sample

Chapter 5. Evaluation Methodology5.1 Applicability of Scaling Factor method5.2 Evaluation by linear relationship5.3 Evaluation by nonlinear relationship5.4 Selection of Key nuclides5.5 Integration and classification methodology

for Scaling factor5.6 Scaling Factor accuracy


IAEA Nuclear Energy Series: NW-T-1.18Contents of IAEA document of SF Method

1. Scaling factor basis– Basic philosophy

(Empirical method based on similarity production & behavior)– Basis of evaluation

(Log-normal distribution & Correlation)2. Scaling factor method application

– Application principle (steps of basic application manner)– Summary of application practices in selected member states

3. Commonality and consensus in scaling-factor programs– Evaluation of influencing factors

(component material, fuel and physic-chemical property)– Evaluation of application methods

(Key nuclide, calculation method, trend evaluation and international integration) etc.

4. Quality management– Quality management in each developing stage

Annexes : 20 country’s Practices of SF method


ISO 21238: 2007Chapter 5. Methodology – Calculating Method

Calculating method of Scaling factor

A. Geometrical mean

B. Linear regression of logarithm

- Based on linear relationship of DTM nuclide and key nuclide

- Based on the log normal distribution

There are two recommended manners for calculating Scaling factor.

- Based on non-linear relationship of DTM nuclide and key nuclide

- Based on log normal regression.

Actual distribution(Ni-63/Co-60)

Actual scatter diagram

(Ni-63/Co-60)


IAEA Document: NW-T-1.18 Actual Practices of Selection of Calculation Method of SF

Scaling factor calculation method for determining the radioactive concentrations of DTM nuclides in waste packages, most countries, as shown in following Table, are determining or planning to apply the “Geometrical mean” or “Logarithmic regression” .

Calculation Method Share of application

Geometrical mean (log mean) Around 50 %

Linear regression of logarithms Around 40 %

Arithmetical mean Around 10 %


ISO 21238: 2007Chapter 5. Methodology – Classification methodology

- Reactor component materials (--> CP nuclides)

- Fuel stability (--> FP nuclides and α emitters)

- Volatile property (--> C-14) etc.

Classification of wastesSetting appropriate SF required consideration of classification based on following conditions.

Integration of wastesIt is possible to integrate to many country’s data under consideration of above classification.


IAEA Document: NW-T-1.18 Classification methodology by influence factor

Sampling should be carried out in consideration of following factors:- Plant type (BWR and PWR, difference in reactor component material )- Fuel stability group (Fuel is stable, Slight fuel failure, Large fuel failure )- Waste stream (Example: The case of C-14 in BWR )

CP Nuclide (Ni-63/Co-60)(Component Material)

FP Nuclide(Alpha/Cs-137)(Fuel stability)

C-14 in BWR (C-14/Co-60) (Volatile property)


ISO 21238: 2007Integration and Classification

by the Type of Waste for CP Nuclide

There is no appreciable difference - in the ratio of DMT nuclides and Key nuclide

between type of waste in the same type of plants. - between the physicochemical behavior in each CP Nuclide.

Key Nuclide Appropriate waste classification for SF evaluation

Co-60

1. Unified SFs can be established irrespective of the type of waste.

2. However, if classification is needed for the purpose of more detail estimation, classifying is not restricted.

Similarity in the CP Nuclides


IAEA Document: NW-T-1.18 Integration of waste stream and type of waste

Type of Waste Reactor Coolant

Spent Resin Concentrates Cartridge

Filter DAW TOTAL

Correlation Coefficient 0.94 0.92 0.76 0.90 0.91 0.81

Geometrical mean 7.1 E - 1 7.7 E - 1 4.9 E - 1 4.5 E - 1 3.6 E - 1 4.5 E - 1

Ratio(%) ProbabilityJapanese PWRReactor Coolant

Spent Resin

DAW

Cartridge Filter

Concentrates

Liquid waste

Solid waste

Example: CP Nuclides : Ni-63/Co-60 - Japanese PWR


IAEA Document: NW-T-1.18 Integration of international radiochemical analysis data which collected independently.

Type of Waste Japan Liquid waste

FranceLiquid waste

GermanyLiquid waste

Japan Solid waste

FranceSolid waste TOTAL

Correlation Coefficient 0.85 0.98 0.95 0.97 0.93 0.95

Geometrical mean 5.1 E - 1 9.0 E - 1 3.1 E - 1 3.9 E - 1 4.1 E - 1 4.3 E - 1

France

Japan

Germany

Japan

France

Liquid waste

Solid waste

Ratio(%) Probability

CP Nuclides : Ni-63/Co-60 - 3 Country’s PWR plants


ISO Standardization(ISO DIS16966) IAEA Document

ISO16966 will be published by the end of 2013.

Developing ISO16966 (DIS), “Theoretical activation calculation method to evaluate the radioactivity of activated waste generated at nuclear reactor”

IAEA Nuclear Energy Series, “Examples and Practices of

Theoretical activation calculation method for

Characterization”

Property: Text book, ExamplesProperty: Basic Manual

(Describe basic methodology) (Gathering many country’s practices)

ISO International Standard and IAEA Document for Theoretical Activity Evaluation Method

Standard has been developing in ISO Project team.

Just planning.

DIS: Draft of International Standard


ISO Project Team Member List for Developing Theoretical Evaluation method (ISO16966)

15

●: Convener○: Participant member

No ISO Participant Country TC85 SC5 Project team

1 Argentina (IRAM) ○ ○ ○ NRA2 Belgium (NBN) ○ ○ ○ SCK/CEN3 Bulgaria (BDS) ○ ○ -- --4 Canada (SCC) ○ ○ ○ NWMO5 China (SAC) ○ ○ -- --6 France (AFNOR) ● ○ ○ EDF, AREVA7 India (BIS) ○ ○ -- --8 Iran, Islamic Republic of ( ISIRI ) ○ ○ -- --9 Japan (JISC) ○ ○ ● JGC, Utility10 Kenya (KEBS) ○ ○ ○

11 Korea (KATS) ○ ○ ○ KEPCO NP12 Russian Federation (GOST R) ○ ○ -- --13 Spain (AENOR) ○ ○ ○ ENRESA14 Sweden (SIS) ○ ○ ○ SKB15 Switzerland (SNV) ○ ○ ○ NAGRA16 United Kingdom (BSI) ○ ● -- --17 USA (ANSI) ○ ○ ○ DW James

Consulting18 Ukraine ( DSSU ) ○ ○ -- --19 Austria (ASI) ○ -- -- --20 Italy (UNI) ○ -- -- --21 Germany (DIN) ○ -- ○ ISTec (Obs.)22 Netherlands (NEN) -- ○ -- --

Project team was consisted of nominated experts from13 institutes from 12 countries.

Project team has been developing Standard from 2010.


ISO Standardization Process

16

Vote

Approval condition : DIS & FDIS approved if a 2/3 of the members of the TC/SC are in favor and not more than 1/4 of the total number of votes are negative .

- Show the skeleton of target standard- Collection of experts for project team

from Member Body (MB)New Work Item Proposal

(NWIP)1

Committee Draft(CD)2

Draft of International Standard(DIS)3

Final Draft of International Standard(FDIS)4

International Standard(Published as ISO Standard)5

Vote result: 12 country’s experts

Vote

Approval condition:NWIP approved at least 5 countries to participate actively in the project

- Show the Standard to MB- Final vote to the Standard for publishing

- Show the revised of Standard to MB- Collect final comments to the standard

from MB

- Show the draft of Standard to MB- Collect comments to the draft from MB

2011.Jun.02, CD registered

Approval condition :CD is needed consensus (general agreement), treat as same as condition of DIS vote.

Vote result: 14 country’s YES2011.Dec.12 vote closed2012.August, DIS registered

2011.Apr.7 vote closed

2013.Jan.7 vote closed


Main Activity estimation methods in ISO 16966 Outline of “Point” and “Range” estimation methods

Point Estimation Method Range Estimation Method

Outline of method

Calculate concentration or ratio of nuclides at specific point in the waste (mainly in one activated radioactive waste) or representative (maximum orconservative) point of waste.

Evaluated average ordistribution of concentration orratio of nuclides by calculatingmany assumed irradiation points.

(Assumed evaluation points selected randomly which are

covered all condition of irradiation) .

Usage

- Evaluation of inventory for safety assessment of disposal in the planning stage.

- Evaluation of activity concentration of specific waste for verifying theoretical evaluation method etc.

- Evaluation of activity concentration of waste packages for declaration to dispose.


ISO DIS16966: Basic Plan and Contents of ISO Standard

18

Clause 1. - 2. Common itemClause 3. Theoretical evaluation method

3.1 General3.2 Point estimation method3.3 Range estimation method

Clause 4. Calculation4.2 Selection and determination of input

conditions4.2.1 Input parameters4.2.2 Elemental composition4.2.3 Neutron fluence rates4.2.4 Irradiation conditions

4.3 Activation calculation4.3.1 Calculation code4.3.2 Setup input data4.3.3 Determining number of calculations

4.4 Validation and uncertainties4.5 Records

Category of Method Theoretical evaluation method is classified 2 categories. (Detail is specified in Annex A)

Calculation basisBasic calculation condition (Input data and calculation manner).(Detail will be specified in Annex B and C)

Validation, etc.Quality control.(Detail will be specified in Annex D and E)


ISO DIS16966: Outline of “Range Estimation Methods”

Conversion Coefficient method Correlation method Averaging Method

Image of Evaluation

Outline of Evaluation

method

There is close relationbetween Key index, suchas burnup (normally fuelis controlled by burnup)and the concentration ofDTM nuclide in activatedcomponent.The concentration of DTM nuclide is able to evaluate as “conversion coefficient” by activation calculations considered the range of actual reactor condition (e.g. element,neutron, irradiation condition).

There are specificrelations amongsimultaneouslygenerated nuclides inthe same part (that is,neutron, elementalcomposition, irradiationtime are same) ofactivated component.The ratio of DTM nuclide and Key nuclide are able to calculate by activation calculations considered the range of actual reactor irradiation condition.

Elemental composition andirradiation condition arealmost same in fixedequipment. The differenceof nuclide's concentrationsis generated by thedifference of neutroncondition.The concentrations in the reactor component or parts of reactor are calculated by activation calculations considered the range of actual reactor condition and position of equipments.

Target waste

Channel box, Control rod, Burnable poison, etc. → Graphite block, Core shroud,

Pressure vessel, etc.

19

WasteType A

Represented Value

WasteType B

Represented Value

Calculation value

Con

cent

ratio

n of

E

valu

ated

nuc

lide(

Bq/

t)

DTM

nuc

lide（

Bq/

t）


ISO DIS16966: Basic flow of Setup Input Database for Range Estimation Method

20

Sufficient number of input data are created and activation calculations are carried out.

Selection of the evaluation point in the waste based on shape of waste. (at random)

Study of property and irradiation history of target waste.

Selection of evaluation point

Selection of activated waste

Selection of concentrationof elemental composition

Selection of loading positionin operation cycles

Fixing neutron condition at Selected point in reactor

Setup of input data

ActivationCross section

Sufficiency

Completion of input database

No

Yes

Irradiation Time Setup of the irradiation time and the neutron

condition which were based on the operational cycle of reactor and the loading position in the reactor. (at random)Normally, activation cross section prepare from library of calculation code.

Setup of the concentration of the parent element based on concentration distribution of chemical analysis data. (at random)

If database dose not reach sufficient number of input data, continue to select next evaluation point and condition.

(at random for Range method)



(at random)


ISO DIS16966: Image of Setup the input datafor Activation Calculation 1

21

Activation point in target waste

Loading position in the reactor

Irradiation condition (Neutron flex)

Example of channel box Rotation of fuel load position in reactor

Example of thermal neutron flex

Select right thermal neutron flux based on the selected position in activated metal and rotation of fuel load position.

Random sampling(from uniform distribution)

Random samplingbased on ratio of

several represented fuel rotation patterns.

Select neutron flux based on activation point and loading position among fuel cycles.


ISO DIS16966: Image of Setup the input datafor Activation Calculation 2

22

Concentration of chemical elemental composition

in target wasteIrradiation condition

(Irradiation time)

Distribution of element concentrationAverage and standard deviation of distribution are determined based on chemical analysis data of cold samples of CB/BP/CR etc..

Irradiation time (Example)

Assume normal distribution of total irradiation time based on distribution of actual reactor operation time from 13,000 BWR fuel assembly’s records.→ Setup “Average” and “Standard deviation” from actual distribution of total irradiation time .

Random sampling Random sampling


ISO DIS16966: Result of Range Estimation Method

23

Scatter diagramNb-94/Co-60

Distribution diagramNb-94/Co-60

Log-normalprobability diagram

Nb-94/Co-60

Correlation coefficient: 0.83

Good correlation Seemed good log-normal distribution

Seemed good log-normal distribution

Calculation result of Channel box (ZrTN804D:Zircaloy) in BWR plant.

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