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2018 Symposium on Nuclear Data, Nov. 28, 2018 Multi-Purpose Digital Hall & Collaboration Room (Ookayama campus, Tokyo Institute of Technology, Meguro, Tokyo) Development of GENESIS, a general three- dimensional transport code based on the


  1. 2018 Symposium on Nuclear Data, Nov. 28, 2018 Multi-Purpose Digital Hall & Collaboration Room (Ookayama campus, Tokyo Institute of Technology, Meguro, Tokyo) Development of GENESIS, a general three- dimensional transport code based on the Legendre polynomial Expansion of Angular Flux method Akio Yamamoto *) , Akinori Giho, Tomohiro Endo *) *) Nagoya University 1 Outline  Recent trends of advanced core analysis methods  Overview of GENESIS  LEAF method  Geometry treatments  Verification results  Summary 2

  2. Recent trends of advanced core analysis methods 3 Recent trends (US)  (International) Nuclear Energy Research Initiative (NERI, I-NERI)  Consortium for Advanced Simulation of Light Water Reactors (CASL)  3D transport calculation in heterogeneous geometry  DeCART, MPACT https://www.casl.gov/ 4

  3. Recent trends (ROK)  DeCART developed by I-NERI project  nTRACER developed by SNU http://neutron.snu.ac.kr/node/7 5 Recent trends (China)  Many activities in Xi’an Jiaotong University and related reactor physics group  3D pin-by-pin (cell homogenous) transport code B. Zhang et al., “Heterogeneous Neutron Leakage Model for PWR Pin-by-pin Calculation,” 6 Ann. Nucl. Energy, 110, 443 (2017).

  4. Recent trends (EU) CEA and EdF are developing next generation core analysis code  for fast reactors D. Schneider et al., “APOLLO3: CEA/DEN Deterministic Multi-Purpose Code for Reactor Physics Analysis,” 7 Proc. PHYSOR2016 Outline of the GENESIS code 8

  5. Outline of GENESIS  Multigroup neutron and photon transport calculations  Major target: reactor cores  Generalized geometry treatment  Deterministic methods  3D LEAF 、 2D MOC  Multi-group cross sections are provided by other codes  Linkages to SRAC2006, Free-FIDO format are implemented 9 Legendre polynomial Expansion of Angular Flux (LEAF) method 10

  6. LEAF method z z y y x x y z x s 11 LEAF method 12

  7. LEAF method z 𝜔 ���,��� 𝑡  z 𝜔 ���,����� 𝑨 𝜔 ��,���� 𝑨    s s s 𝑟 𝑡, 𝑨   z 𝜔 ��,������ 𝑡 13 Planar MOC vs LEAF Planar MOC MOC for radial direction (2D) Low order calculation (e.g. diffusion, SPn) for axial direction http://neutron.snu.ac.kr/node/7 LEAF No approximation z z y s x 14

  8. Geometry treatment by GENESIS 15 Geometry – overview  3D geometry is expressed as stack of planes  Use combinatorial geometry for radial direction https://phys.org/news/2013-07-casl-milestone-validates-reactor-tva.html http://neutron.snu.ac.kr/node/7 16

  9. BWR – 3x3 fuel assemblies BWR – flux regions

  10. BWR – 3x3 fuel assemblies KAIST benchmark problem (Cho et al.)

  11. C5G7 hexagonal benchmark (Joo et al.) PWR – 4 loop type, full core with baffle reflector

  12. Seed – blanket fuel CANDU

  13. Large FBR 25 FBR fuel assembly with wrapper tube 26

  14. Verification calculations 27 C5G7 3D benchmark problem Rodded A, Rodded B Rodded B 28

  15. C5G7 3D benchmark problem RMS error of pin-by-pin fission rate (Rodded-B) 0.70 0.64 0.60 RMS difference (%) 0.50 0.40 0.34 0.30 0.25 0.20 0.13 0.10 0.00 Genesis Chaplet-3D CRX MCCG3D 29 C5G7 3D void benchmark problem Void-A Void-B 30

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