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Development of Next-Generation LWR in JAPAN Tomofumi Tomofumi Y Y amamoto amamoto , , Shigeru Kasai Shigeru Kasai The Institute of Applied Energy The Institute of Applied Energy IAEA International Conference on Opportunities and Challenges for Water Cooled Reactors in the 21st Century 27 – 30, October 2009, Vienna, Austria

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Page 1: Development of Next-Generation LWR in JAPAN€¦ · Development of Next-Generation LWR ... concept of total management system Investigate innovative seed technologies related to the

Development of Next-Generation LWR in JAPANTomofumiTomofumi YYamamotoamamoto,, Shigeru KasaiShigeru Kasai

The Institute of Applied EnergyThe Institute of Applied Energy

IAEA International Conference on Opportunities and Challenges for Water Cooled Reactors in the 21st Century27 – 30, October 2009, Vienna, Austria

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IAEA CN164 Oct-28,2009 Vienna 1

Contents

1. 1. Program overviewProgram overviewBackgroundConcept of next-generation LWROutline of technology developmentsScheduleOrganization

2. Technology development 2. Technology development Development plan Regulation and codes and standards

3. Summary3. Summary

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IAEA CN164 Oct-28,2009 Vienna 2

Background

Trend in the world Trend in the world -- Nuclear RenaissanceNuclear RenaissanceDramatic expansion of nuclear energy

Trend in JapanTrend in JapanContribute to large reduction of greenhouse gas emissionsNuclear energy is the only clean base-load energy source

53 commercial reactors are in operation, meeting approximately 30% of the country’s electricity demandMaintain the share of nuclear power in the total electricity supply at about 30-40%(The Nuclear Energy National Plan, Oct. 2006)

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IAEA CN164 Oct-28,2009 Vienna 3

Background (cont.)

LongLong--term framework for nuclear energyterm framework for nuclear energy

0

1000

2000

3000

4000

5000

6000

7000

1960 1970 1980 1990 2000 2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

70

60

50

40

30

20

10

Cap

acity

[G

W]

020302010 2050 207019901970 2090Year

LWRLWR

(40y(40y--life)life)

Life Life ExtensionExtension(60y(60y--life)life)

LWRLWR(to be replaced)(to be replaced)

Fast Reactor

[Note] The capacity is assumed to be saturated at 58GWe for illustrative purpose.

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IAEA CN164 Oct-28,2009 Vienna 4

Background (cont.)

It is anticipated that many reactors will need It is anticipated that many reactors will need replacement needs starting in the 2030replacement needs starting in the 2030’’s.s.

[GWe]

20402020 2025 2030 20350

5

10

15

20

25

over 40ys over 60ys

BWRPWR

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IAEA CN164 Oct-28,2009 Vienna 5

Major target

70 70 GWd/tGWd/t ((aveave. assembly discharge). assembly discharge)

high reliability & easy maintenancehigh reliability & easy maintenance50 % reduction50 % reduction

core designcore designmaintainabilitymaintainabilitymaintenance workmaintenance work

Operation Operation & & MainteMainte--nancenance

≤≤1010--66 //ryry (short(short--term)term)≤≤1010--77 //ryry (long(long--term)term)earthquake, tsunami, airplane crushearthquake, tsunami, airplane crush

evacuation frequencyevacuation frequency

external hazardsexternal hazards

Public Public acceptanceacceptance

TBDTBD97 % 97 % (average throughout lifetime)(average throughout lifetime)24 months24 months80 80 ysys≤≤ 30 months30 months

construction costconstruction costcapacity factorcapacity factoroperating cycleoperating cycleplant lifeplant lifeconstruction periodconstruction period

EconomyEconomy

≤≤1010--55 //ryry≤≤1010--66 //ryryYesYes

core damage frequencycore damage frequencycontainment failure f.containment failure f.countermeasures against SAcountermeasures against SA

SafetySafetyUser requirements in JapanUser requirements in JapanItemsItems

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IAEA CN164 Oct-28,2009 Vienna 6

Concept of next-generation LWR

Concept for the nextConcept for the next--generation LWRgeneration LWRWorld’s best level of safety and economy in the 2030 timeframeGlobal standardSimplifying their operation and maintenanceHigh public acceptability

Reactor TypesReactor TypesOne PWR design and one BWR design

Electric outputElectric output1,700 to 1,800 MWe class

Key technologies should be developed for 800 to 1,000 MWeclass plants within the framework of the standardization of designs for the 1,700 to 1,800 MWe class

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IAEA CN164 Oct-28,2009 Vienna 7

Outline of technology development

Electrical Output

1,700–1,800 MWe

Reactor Type

PWR / BWR

[Note] The figure shows an example of PWR

Reactor core system with

very high burn-up fuel

Reactor core system with

very high burn-up fuel

Advancedsafety system

[passive and active]

Advancedsafety system

[passive and active]

Long-lived materials & innovative water

chemistry technologies

Long-lived materials & innovative water

chemistry technologies

World leading digital technology

World leading digital technology

Innovativeconstruction technology

Innovativeconstruction technology

Seismic isolation system

Seismic isolation system

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IAEA CN164 Oct-28,2009 Vienna 8

Schedule

Planning fordevelopment

Long-termtesting

Basic design

2016 - 2030

Technology development to convert the next-generation LWR

concept into reality

Complete basic design

2006 - 2007

Start full-scale developments

Feasibility study Establish plant

design concept

Determine basic specifications

Site specific design

Safety review

Construction

Start commercial operation

2008 - 2010 - 2015

Conceptual design

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IAEA CN164 Oct-28,2009 Vienna 99

Organization

The Institute of Applied Energy (IAE)

Hitachi-GE Nuclear Energy, Ltd.

Toshiba Corporation

Mitsubishi Heavy Industries, Ltd.

Organization for the Joint R&D

Government

(METI /ANRE)

Utilities

Support

Other industries & institutes

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10

Technology development

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IAEA CN164 Oct-28,2009 Vienna 11

Reactor core systemwith very high burn-up fuelGoalsGoals

Capacity factor of up to 97% spent fuel discharge reduced by 30~40%

DevelopmentsDevelopmentsVery high burn-up fuel

Up to 100GWd/t* burn-up fuelwith uranium enrichment over 5% (average discharge burn-up 70–90GWd/t)

Cladding materials for very high burn-up fuele.g. new zirconium alloys, stainless steels

Advanced reactor core system*.Maximum fuel assembly burn-up of PWR

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IAEA CN164 Oct-28,2009 Vienna 12

Reactor core systemwith very high burn-up fuel (cont.)

Phase IPhase I (fy2008(fy2008--2010)2010)Evaluation of technical impacts of 5%-10% uranium enrichment on the current fuel cycle facilities and fuel cycle cost competitivenessPreliminary evaluation of cladding materials for very high burn-up fuel

Phase II (fy2011Phase II (fy2011--2015)2015)Demonstration of fuel integrity through experimental irradiation testsPromote practical use of over 5% enriched-U fuel including associated regulatory developmentDevelop advanced reactor core system

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IAEA CN164 Oct-28,2009 Vienna 13

Advanced safety system[best combination of passive and active safety system]

GoalsGoalsSafe, reliable and simplified systemReduction of equipments and maintenance work in safety system

DevelopmentsDevelopmentsBest combination of passive and active conceptsDemonstration tests for the advanced safety system

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IAEA CN164 Oct-28,2009 Vienna 14

Advanced safety system[best combination of passive and active safety system] (cont.)

Phase I (fy2008Phase I (fy2008--2010)2010)Establish conceptual design of safety systemEstimate core damage frequency (CDF) and containment failure frequency (CFF)

Phase II (fy2011Phase II (fy2011--2015)2015)Perform evaluation tests for advanced safety systemEstablish safety analysis method

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IAEA CN164 Oct-28,2009 Vienna 15

Long-lived materials and Innovative water chemistry technologiesGoalsGoals

Eighty-year plant lifetimeLarge reduction of occupational dose

DevelopmentsDevelopmentsNickel-based alloy for steam generator tube

High resistance to intergranular corrosion (IGA) and primary water stress corrosion cracking (PWSCC)

Stainless steel for BWR reactor internalsHigh resistance to irradiation-assisted stress corrosion cracking (IASCC)

Innovative coolant chemistry control technology

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IAEA CN164 Oct-28,2009 Vienna 16

Long-lived materials and Innovative water chemistry technologies (cont.)

PPhasehase II (fy2008(fy2008--2010)2010)Material design and screening tests

state-of-the-art molecular design tool and broad investigation into existing knowledge-base

Survey of applicability of water chemistry control technologies

PPhasehase IIII (fy2011(fy2011--2015)2015)Establishment of production process and Long-term verification tests for new materialsLarge-scale and long-term tests to verify applicability of water chemistry technologies

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IAEA CN164 Oct-28,2009 Vienna 17

Seismic isolation system

GoalsGoalsStandardized structural designPlant design independent from site specific conditions

DevelopmentsDevelopmentsLarge-scale seismic isolation systemEstablishment of codes and standards for seismic isolation design

Bolt HolesLead plug

damper ElastomerInner steel plates

Elastomercover

Flange

Seismic isolation system

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IAEA CN164 Oct-28,2009 Vienna 18

Seismic isolation system (cont.)

Phase I (fy2008Phase I (fy2008--2010)2010)Feasibility analysis for seismic isolation system for next-generation LWR plot planBasic characteristic tests for seismic isolation system

Phase II (fy2011Phase II (fy2011--2015)2015)Full-scale or large-scale model tests

Ultimate characteristics for seismic isolation systemPiping integrity between seismic isolation building and non-seismic isolation building, etc.

Establish evaluation method and standards for LWR plant with seismic isolation system

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IAEA CN164 Oct-28,2009 Vienna 19

Innovative construction technologies

GoalsGoalsShortening of construction period to 30 months( from 1st concrete to start of commercial operation )

DevelopmentsDevelopmentsLarge modularization technologies

Application of steel plate reinforced concrete (SC) structure to PCV*, etc.

steel plate

concrete

steel platestudtie-bar

piping sleeve

attachment for component

* Primary containment vessel of BWR

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IAEA CN164 Oct-28,2009 Vienna 20

Innovative construction technologies (cont.)

Phase I (fy2008Phase I (fy2008--2010)2010)Preliminary examination on SC structured PCV

Elementary tests for SC structure: buckling, shearing, horizontal load tests for cylindrical wall

Phase II (fy2011Phase II (fy2011--2015)2015)Large-scale SC structured PCV structure testsDevelop other techniques to allow assembly of large modular blocksEstablish analysis method and standards

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IAEA CN164 Oct-28,2009 Vienna 21

World leading digital technology

GoalsGoalsImprove plant operability, maintainability and availability

DevelopmentsDevelopmentsPlant management system adopting innovative digital technologies and devices

Utility

Plant design

Systemdesign

Operationsupport

Maintenance support

Decommissioning planning

Plant Vender

maintenance failure/malfunction

procurement scheduling

Support system / Operator console

・multi-point sensing using optical fiber ・wireless transmission・virtual/augmented reality

NPP SiteIntegrated Databasedesign, construction,

operation/maintenance <provide sufficient information for >

<example of applied technology>

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IAEA CN164 Oct-28,2009 Vienna 22

World leading digital technology (cont.)

Phase I (fy2008Phase I (fy2008--2010)2010)Comprehensive job and data analysis from plant design stage to decommissioning stage Establish concept of total management system Investigate innovative seed technologies related to the total management system

Phase II (fy2010Phase II (fy2010--2015)2015)Design major management systemsDevelop and/or verify basic digital technologies

e.g. sensor or monitor for equipments, data transmission technology, etc.

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IAEA CN164 Oct-28,2009 Vienna 23

Regulatory development

Propose appropriate regulation for the next-generation LWR plant designDevelop codes and standards from technology development stage Promote international harmonization of regulations, codes and standards for smooth introduction of the plants into the international marketCollaborate with the international organization (IAEA, OECD/NEA, MDEP), foreign standards development organizations (SDOs)

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IAEA CN164 Oct-28,2009 Vienna 24

Summary

Development of next-generation LWR started April 2008 with consortium of consisting of three major plant vender, utilities and IAE.Basic design and major R&D will be completed in 2015 and the 1st commercial operation will start around 2030.Evaluation of innovative technologies including preliminary tests is now ongoing.In June 2010, all the activities associated with this program will be reevaluated in order to proceed to the next development step