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AER Meeting, Working Group F

AER Meeting, Working Group F. Liblice, Czech Republic. April 6 – 9, 2010. THE HEAVY NUCLIDES TRANSMUTATION IN THE THERMAL AND FAST REACTORS CYCLES. Radoslav ZAJAC 1 -Petr DA RI LEK 1 -Vladim i r NE C AS 2. 1 VUJE, a.s. 2 Slovak University of Technology.

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AER Meeting, Working Group F

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  1. AER Meeting, Working Group F Liblice, Czech Republic April 6 – 9, 2010 THE HEAVY NUCLIDES TRANSMUTATION IN THE THERMAL AND FAST REACTORS CYCLES Radoslav ZAJAC1-Petr DARILEK1-Vladimir NECAS2 1VUJE, a.s.2Slovak University of Technology 1VUJE, a.s., Okruzna 5, Trnava, Slovakia, zajacr@vuje.sk, darilek@vuje.sk 2Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Ilkovicova 3, Bratislava, Slovakia,vladimir.necas@stuba.sk

  2. Presentation Parts • The Transmutation Fuel Cycles: • - Open Cycle (UOX) • - Mono- and Multi-Recycling Pu in VVER-440 • - IMF Fuel Cycle • - ThOX Fuel Cycle • - Mono- and Multi-Recycling Pu in SUPERPHENIX • - Codes: TRITON in the System SCALE and HELIOS 2. Some PWR and VVER MOX Calculations by HELIOS 3. Transmutation of the VVER-440 Spent Fuel in the Fast Reactor VUJE, Inc., Okružná 5, 918 64 Trnava

  3. 5 years UOX Storage UOX 4.2% U-235 Spent Fuel Fabrication VVER-440 Enrichment Final Storage Repozitory U 45 years Open Fuel Cycle (UOX) VUJE, Inc., Okružná 5, 918 64 Trnava

  4. Pu 2 years 5 years UOX Pu Pu 4.2 % U235 UOX S VVER-440 Fabrication T REPROCESSING 8.5 % Pu U UOX Irradiated PUREX U O MOX Fuel MOX R Fabrication VVER-440 100 % FP MOX 0.1% U A 0.1% Pu 100 % MA G Storage Final Depleted U E Repository 45 years Mono- and Multi-Recycling Pu in VVER-440 VUJE, Inc., Okružná 5, 918 64 Trnava

  5. 2 years Pu + MA 5 years UOX Pu + MA Pu + MA 4.2 % U235 UOX S VVER-440 Fabrication T REPROCESSING U, Zr UOX Irradiated PUREX U, Zr O Fabrication UOX + IMF Fuel R UOX + IMF Fuel VVER-440 100 % FP 0.1% U A 0.1% Pu 0.1% MA G Final UOX + IMF Storage E Storage 45 years IMF Fuel Cycle VUJE, Inc., Okružná 5, 918 64 Trnava

  6. 2 years Pu 5 years UOX Pu Pu UOX 4.2 % U235 S Fabrication VVER-440 T REPROCESSING Th, U UOX Irradiated PUREX Th, U O PuThOX Fuel PuThOX R Fabrication VVER-440 100 % FP 0.1% U A 0.1% Pu 100 % MA G Final Storage PuThOX Thorium E Repository 45 years ThOX Fuel Cycle VUJE, Inc., Okružná 5, 918 64 Trnava

  7. 2 years Pu + MA 5 years UOX Pu + MA Pu + MA 4.2 % U235 UOX S PWR-900 Fabrication T REPROCESSING 23.2 % Pu U UOX Irradiated 2.7 % MA PUREX U O MOX MOX FUEL R Fabrication Fuel Part 100 % FP 0.1% U A MOX 0.1% Pu SUPERPHENIX 0.1% MA G 1450 MWe Final Depleted U Storage Fuel Part: 136 GWd/tHM E Storage 45 years Mono- and Multi-Recycled Pu, MA in SUPERPHENIX VUJE, Inc., Okružná 5, 918 64 Trnava

  8. Results(Fuel Cycle Indicators) VUJE, Inc., Okružná 5, 918 64 Trnava

  9. 2. Some PWR and VVER MOX Calculations by HELIOS VUJE, Inc., Okružná 5, 918 64 Trnava

  10. Based on OECD Depletion Calculation Benchmark devoted to MOX Fuel Cycles Phase 1:Structure of 9 PWR Assemblies - 8 UOX and 1 MOX Assembly - Profiled MOX Assembly: high, medium and low Phase 2:Structure of 7 VVER-1000 Assemblies - 6 UOX and 1 MOX Assembly - Profiled MOX Assembly: high, medium and low Phase 3:Structure of 7 VVER-440 Assemblies - 6 UOX and 1 MOX Assembly - Profiled MOX Assembly: high, medium and low Phase 4 - 6:PWR,VVER-1000 & VVER-440 Assembly in InfiniteLattice Models of Structures in HELIOS 1.9 VUJE, Inc., Okružná 5, 918 64 Trnava

  11. PWR Model in HELIOS 1.9 Average Content of Pu/(U+Pu+Am):4.42% Burnup of UOX Assembly: 24 GWd/tHM + 34 GWd/tHM Burnup of MOX Assembly: app. 42 GWd/tHM Profiled MOX Assembly: Reds – HIGH (5.516 % Pu); Blues –MEDIUM (4.33 % Pu); Pinks –LOW (2.856 % Pu); VUJE, Inc., Okružná 5, 918 64 Trnava

  12. VVER-1000 Model Average Content of Pu/(U+Pu+Am):4.42% Burnup of UOX Assembly: 24 GWd/tHM + 31 GWd/tHM Burnup of MOX Assembly: app. 42 GWd/tHM Profiled MOX Assembly: Reds – HIGH (5.516 % Pu); Blues –MEDIUM (4.33 % Pu); Pinks –LOW (2.856 % Pu); VUJE, Inc., Okružná 5, 918 64 Trnava

  13. VVER-440 Model Average Content of Pu/(U+Pu+Am):4.42% Geometry: Gd-2 Assembly Burnup of UOX Assembly: 24 GWd/tHM + 35 GWd/tHM Burnup of MOX Assembly: app. 42 GWd/tHM Profiled MOX Assembly: Reds – HIGH (5.516 % Pu); Blues –MEDIUM (4.33 % Pu); Pinks –LOW (2.856 % Pu); VUJE, Inc., Okružná 5, 918 64 Trnava

  14. Profiled MOX Assembly: Red – (5.516 % Pu); Blue –(4.33 % Pu); Pink –(2.856 % Pu); LWR Models in Infinite Lattice Average Content of Pu/(U+Pu+Am):4.42% Burnup of MOX Assembly:42 GWd/tHM VUJE, Inc., Okružná 5, 918 64 Trnava

  15. Concentration of Pu in PWR Assembly VUJE, Inc., Okružná 5, 918 64 Trnava

  16. Development of Pu VUJE, Inc., Okružná 5, 918 64 Trnava

  17. Final Results – PWRMOX Assembly Weight Concentrations VUJE, Inc., Okružná 5, 918 64 Trnava

  18. , Weight Concentrations Final Results – Average Values VUJE, Inc., Okružná 5, 918 64 Trnava

  19. Pin Power Distribution PWR-900 MOX UOX UOX UOX

  20. Pu-239(PWR): - 63.3 % Pu-239(VVER-1000): - 62.0 % Pu-239(VVER-440): - 54.3 % Pu(PWR): - 33.0 % Pu (VVER-1000): - 32.6 % Pu (VVER-440): - 26.5 % Conclusions (1) • Average Pu Content for PWR, VVER-1000 and 440 Assemblies: 4.42 %,Final Burnup: 42 GWd/tHM • Reduction of Pu,MOX Assembly as a Super Cell Part: • Actinides: [Np+Am+Cm+Bk+Cf](PWR): 0.21 % [Np+Am+Cm+Bk+Cf](VVER-1000): 0.21 % [Np+Am+Cm+Bk+Cf](VVER-440): 0.22 % VUJE, Inc., Okružná 5, 918 64 Trnava

  21. Conclusions (2) 1. Spent LWR UOX Assembly:app. 1 % Pu 2. Reprocesing of 4.5 LWR UOX Spent Assemblies 1 MOX Assembly: 4.42 % Pu 3. Hypothesis:If is Possible to Spent 60 % of Pu-239in MOX PuDepletionLeads to Pu-239 Spending from 2.7 LWR UOX Spent Assemblies VUJE, Inc., Okružná 5, 918 64 Trnava

  22. 3. Transmutation of the VVER-440 Spent Fuel in the Fast Reactor VUJE, Inc., Okružná 5, 918 64 Trnava

  23. SUPERPHENIX and VVER-440 VUJE, Inc., Okružná 5, 918 64 Trnava

  24. PSEUDO Fuel Assembly – 91 pins PSEUDO Fertile Assembly – 91 pins PSEUDO Assemblies in HELIOS 1.10 VUJE, Inc., Okružná 5, 918 64 Trnava

  25. Reflector 1/6 Core of SUPERPHENIX; Colour part:Subject of Calculation Blanket Blanket: fertile assembly, depleted U Fuel part Fuel part: pseudo assembly, MOX 23.2 % Pu, 0.25 % U-235 Calculation Area VUJE, Inc., Okružná 5, 918 64 Trnava

  26. Multirecycling of Pu and MA in FR VUJE, Inc., Okružná 5, 918 64 Trnava

  27. Development of Pu VUJE, Inc., Okružná 5, 918 64 Trnava

  28. Development of MA Initial: 2.7 %MA in Fuel Part VUJE, Inc., Okružná 5, 918 64 Trnava

  29. Fuel Cycle Indicators VUJE, Inc., Okružná 5, 918 64 Trnava

  30. 1. Spent VVER-440 UOX Assembly:app. 1 % Pu 2. Reprocesing of 20.05VVER-440 UOX Assemblies 1 MOX SUPERPHENIX Assembly: 23.2 % Pu 3. Mass of Fuel to the repository: Sum of repr. losses [kg/TWhe]: 2.09E+001.81E-01 SUPERPHENIX Sum of FPs [kg/TWhe]: 1.01E+029.48E+01 VVER-440 Equilibrium(Fuel part) Total of loss.+FPs [kg/TWhe]: 1.03E+029.66E+01 Pu [kg/TWhe]: 3.15E+011.79E+02 Separated U [t/TWhe]: 2.06E+000.66E-01 Conclusion VUJE, Inc., Okružná 5, 918 64 Trnava

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