for FR Cycle in Japan June 7, 2010 Hideyuki FUNASAKA JAEA - - PowerPoint PPT Presentation

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INTERNATIONAL FORUM ATOMEXPO 2010 Current Status and Future Prospects for FR Cycle in Japan June 7, 2010 Hideyuki FUNASAKA JAEA Contents Introduction Medium- to Long-term plan around 2050 and beyond -Transition from LWR cycle to

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Current Status and Future Prospects for FR Cycle in Japan

June 7, 2010 Hideyuki FUNASAKA JAEA

INTERNATIONAL FORUM «ATOMEXPO 2010»

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 Introduction  Medium- to Long-term plan around 2050 and beyond

  • Transition from LWR cycle to FR cycle -

 Near-term plan around 2015

  • FaCT Project -

 International collaboration  Summary

* Fast Reactor Cycle Technology Development

Contents

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Development Chronology in Reactor & Reprocessing

1970 2000 2030 2060 2090年 GEN-I LWR GEN-II, III ALWR GEN-IV FR R&D、Demo.FR R&D Reprocessing Reactor 3rd GEN. Next GEN.

１ｓｔ GEN. 2nd GEN. US West Valley FR UP2 UK B205 etc FR UP2-400 RU RT-1 JP JAEA TRP FR UP3,2-800 UK THORP RU RT-2 JP JNFL RRP IN Kalpakkam CN Lanzhou-PP RT-3 Post-RRP AFCF 880t/y Plant La Hague Mod. PFRP

世界の潮流（Global Trend）は次世代炉 燃料サイクル

Global Trend of Reactor & Reprocess

  • ing to Next Genera--

tion

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Future FR fuel cycle

Japan’s Fundamental Strategy for Nuclear Fuel Cycle

FR

HLW repository U/Pu/MA fuel Spent fuel MA-free HLW

R&D

Current LWR fuel cycle

LWR

Reprocessing plant MOX fuel plant HLW repository Interim Storage Facility Spent fuel MOX fuel LEUO2 fuel HLW U, Pu Fuel cycle plant Industrial and social infra

  • structure

Technical expertise

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5  In order to replace all LWRs with FRs, it

will take about 60 years as transition period from around 2050.

 Next reprocessing plant (post-RRP

plant) is envisioned around 2050.

 Spent LWR UO2 fuels have to be

reprocessed to introduce FRs in next reprocessing.

 Also reprocessing of spent FR fuels

and LWR MOX fuels have to start around 2055-2060.

 We need to figure out effective and

rational image of next reprocessing plant.

Investigation on Transition from LWR cycle to FR cycle

2100 Installed capacity 2000

LWR FBR

Pu utilization in LWR

Rokkasyo Reprocessing Plant

Spent Fuel of LWR-UO2 Spent Fuel

  • f LWR-

MOX Spent Fuel

  • f FBR

Interim storage

Spent Fuel

  • f

LWR-UO2

Pu

Next Reprocessing Plant

TRU

Pu

2100 Installed capacity 2000

LWR FBR

Pu utilization in LWR

Rokkasyo Reprocessing Plant

Spent Fuel of LWR-UO2 Spent Fuel of LWR-UO2 Spent Fuel

  • f LWR-

MOX Spent Fuel

  • f FBR

Interim storage

Spent Fuel

  • f

LWR-UO2

Pu

Next Reprocessing Plant

TRU

Pu

Example of preconditions for transition from LWR cycle to FR cycle

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6

2005 2015 201 5

2025 2050 Validation of Economy & Reliability

Commercializatio n of FR Cycle Facilities

Basic Design & Construction

Start of Demonstration FR Cycle Facilities

2010

(JFY)

Fast Reactor Cycle Technology Development Project (FaCT）

R&D of Innovative Technologies Conceptual Design of Commercial & Demonstration FR Cycle Facilities 2015 R&D at “Monju “

 Demonstrating its Reliability as a Operation Power Plant  Establish Sodium Handling Tech.

Conceptual Designs of Commercial Facilities and Demonstration Facilities with R&D Programs

Feasibility Study(1999-2005)

Review & Basic Policy by MEXT &AEC

◆International Cooperation（GNEP, GEN-IV, INPRO etc.） ◆Cooperation with related Organization

Experimental FR “Joyo”

Decision of Innovative Tech. (2010) Approved Confirmation (2015)

R&D at Prototype “Monju “

FR Cycle Development Program in Japan

Commercialize d FR Cycle

Most Promising Concept

HLW HLW

Sodium-cooled Fast Reactor Advanced Aqueous Reprocessing and Simplified Pelletizing Fuel Fabrication FR System Fuel Cycle System

FB R

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Development Targets and Design Requirements

  • f Fuel Cycle Commercial Facility

Safety and Reliability Sustainability Economic Competitiveness Nuclear Non-Proliferation

○ Not influence on the significant radiation risk to public ○ Prevent the occurrence of off-site emergency ○ Establish the design concept possible to achieve the maintainability and repairability ○ Keep the influence of the radioactive release on the environment through normal operation below the current fuel cycle

Environment Protection Waste Management

○ Reduce the amount of radioactive waste to 1/2 - 1/5 of the current fuel cycle facilities ○ Recover more than 99.9% of U and TRU

Efficient Utilization of Nuclear Fuel Resources

○ Possible to treat the SF with the heat power of 3kW/Assy (inn the case that the out-of core time is around 5 years) ○ Fuel cycle cost should be < 340,000 JPY/kgHM (reprocessing：< 180,000 JPY/kgHM, fuel fabrication：< 160,000 JPY/kgHM ○ Pure Pu should appear in any process ○ It should be difficult to access the nuclear materials by handling low-decontamination TRU fuel

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1000$ line 0.2M 0.4M 0.6M 2.0M

Unit Construction Cost (JP Yen / kWe) MONJU :280MWe JSFR :1500MWe×2

(FOAK)

~0.18 Scale Merit (to 1500MWe) Twin Effect

2.0

Innovative Technologies

0.48

DFBR

:670MWe

Breakdown list*

0.1M 0.3M 0.5M

The unit construction cost of Monju is expressed as the construction cost divided by electric power. The unit construction cost of DFBR and JSFR are evaluated value

Others, 16% High Cr Steel, 16% Compacted R/V, 23% 2 loop heat Transport system, 26% Integrated IHX with Pump, 10% Cost Estimation by NOAK and Overnight Cost, taking into account Learning Effect

Improvement of Economics for JSFR

Large SG, 10%

*Example of first evaluation

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Typical Advanced Reprocessing Test in CPF

U/Pu/Np U Crystallization Co-extraction Co-stripping

(U/Pu/Np recovery) Solvent regeneration Concentration Adjusting Pu content

U Np valence adjustment

Am, Cm

Extraction chromatography

U/TRU (product) U (product)

MA recovery

High level liquid waste

Disassembling/ Shearing

Clarification

Spent fuel

Dissolution

0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 60 120 180 240 300 360 420 480 540 600 dissolution time（min.） dissolution fraction (-)

Experimental Results

0.1 1 10 Y La Ce Pr Nd PmSm Eu Gd Tb Dy Ho Er Tm Yb Lu Distribution Ratio D

E

Element CMPO TBP TOPO DMDBTDMA

Evolutionary Type Revolutionary Type

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10

no additive

MOX Pellet Fabrication Tests by Simplified Pelletizing Method

Pellet Pu-U Nitrate mixed Solution

MOX Powder

Pressing Sintering (Grinding) Inspectio n

Dissolving

MOX Pellet

Flowable Adjusted Pu content Additional fabrication tests including Am-MOX fuel is going on. Fuel pin irradiation tests are planned, too. Conversion by Microwave Heating Granulation Binderless granuation Die lubrication

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11 Russia

 ODS cladding irradiation, etc.

Kazakhstan

 Re-criticality elimination mechanism (EAGLE project)

France

 CEA/JAEA Cooperation

  • n Nuclear R&D

 Reactor Research & Advanced Nuclear Energy System  Advanced Fuel Cycles, etc.

 EDF/JAEA Cooperation

  • n Fast Reactor System

 Design of Prototype/ Demonstration Reactor  Operation/Maintenance, etc.

International Cooperation of R&Ds on FR Cycle

GIF

  • Sodium-cooled FR
  • Gas-cooled FR
  • Very High Temperature Reactor
  • Super Critical Water Reactor
  • Lead-cooled FR
  • Molten Salt Reactor

JAEA

Japan

IAEA

  • INPRO
  • TWG-Fast Reactors
  • TWG-Nuclear Fuel

Cycle Options U.S.A.

 U.S.-Japan Joint Nuclear Energy action Plan (JNEAP)  Fast Reactor Technology  Fuel Cycle Technology  Simulation & Modeling  Safeguards & Physical Protection  Waste Management

Trilateral Collaboration

  • Sodium-Cooled FR

 design goals and high level requirements for the prototypes  common safety principles  infrastructure needs, etc.

  • Irradiation test of MA bearing

fuels (GACID project in GIF)

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Conclusions

Japan is promoting the nuclear energy to supply stable energy and reduce CO2 emission.

  • Medium to Long-term plan around 2050 and beyond

Basic policy in Japan is closed fuel cycle. Therefore, in order to make the transition of LWR cycle to FR cycle around 2050 smoothly, intensive discussion in JAEC will be started in 2010.

  • Near-term plan around 2015 in FaCT Project

Design study and R&D of innovative technologies are now in progress aiming at adopting of innovative technologies by judging of their applicability in JFY2010. Furthermore, study of future reprocessing technology would be discussed not only as FaCT project but also in the field of transition from LWR cycle to FR cycle.

  • International collaboration

International collaboration is indispensable to efficient development of FR fuel cycle. JAEA expects further collaboration with concerned countries on FR fuel cycle by sharing the R&D items on the same target.