본문 바로가기
KERD
논문KCI 등재

Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX

Li Yunzhao|Cao Liangzhi|He Qingming|Wu Hongchun|Qin Shuai|Wang Yongping|Wu Yuxuan
한국원자력학회 (Korean Nuclear Society)|2023.09|Nuclear Engineering and Technology|제55권 제9호|pp. 3450-3463|DOI 10.1016/j.net.2023.05.029

2

조회

0

다운로드

1

인용

0

참고문헌

키워드

HomogenizationMonte CarloNECP-MCXPebble-bed
주제분류원자력공학

초록

In the two-step analysis of Pebble-Bed type High-Temperature Gas-Cooled Reactor (PB-HTGR), the lattice physics calculation for the generation of homogenized cross-sections is based on the fuel pebble. However, the randomly-dispersed fuel particles in the fuel pebble introduce double heterogeneity and randomness. Compared to the deterministic method, the Monte Carlo method which is flexible in geometry modeling provides a high-fidelity treatment. Therefore, the Monte Carlo code NECP-MCX is extended in this study to perform the lattice physics calculation of the PB-HTGR. Firstly, the capability for the simulation of randomly-dispersed media, using the explicit modeling approach, is developed in NECP-MCX. Secondly, the capability for the generation of the homogenized cross-section is also developed in NECP-MCX. Finally, simplified PB-HTGR problems are calculated by a two-step neutronics analysis tool based on Monte Carlo homogenization. For the pebble beds mixed by fuel pebble and graphite pebble, the bias is less than 100 pcm when compared to the high-fidelity model, and the bias is increased to 269 pcm for pebble bed mixed by depleted fuel pebble. Numerical results show that the Monte Carlo lattice physics calculation for the two-step analysis of PB-HTGR is feasible.

Abstract

In the two-step analysis of Pebble-Bed type High-Temperature Gas-Cooled Reactor (PB-HTGR), the lattice physics calculation for the generation of homogenized cross-sections is based on the fuel pebble. However, the randomly-dispersed fuel particles in the fuel pebble introduce double heterogeneity and randomness. Compared to the deterministic method, the Monte Carlo method which is flexible in geometry modeling provides a high-fidelity treatment. Therefore, the Monte Carlo code NECP-MCX is extended in this study to perform the lattice physics calculation of the PB-HTGR. Firstly, the capability for the simulation of randomly-dispersed media, using the explicit modeling approach, is developed in NECP-MCX. Secondly, the capability for the generation of the homogenized cross-section is also developed in NECP-MCX. Finally, simplified PB-HTGR problems are calculated by a two-step neutronics analysis tool based on Monte Carlo homogenization. For the pebble beds mixed by fuel pebble and graphite pebble, the bias is less than 100 pcm when compared to the high-fidelity model, and the bias is increased to 269 pcm for pebble bed mixed by depleted fuel pebble. Numerical results show that the Monte Carlo lattice physics calculation for the two-step analysis of PB-HTGR is feasible.

참고문헌 (42)

  1. Zuoyi Zhang, "Design aspects of the Chinese modular high-temperature gas-cooled reactor HTR-PM", Nuclear Engineering and Design, 236(5-6), pp.485~490 (2006), Elsevier BV[DOI]
  2. Performance Evaluation of Modern HTR TRISO Fuels, "R. Gontard", Kernforschungsanlage Jülich GmbH, ~, pp.No. KFA-HTA-IB–5 (1990), 90
  3. VSOP-computer Code System for Reactor Physics and Fuel Cycle Simulation, "E. Teuchert", Kernforschungsanlage Juelich GmbH, ~, pp.No. JUEL–1649 (1980)
  4. GAM-1: A CONSISTENT P1 Multigroup Code for the Calculation of Fast Neutron Spectra and Multigroup Constants, "G. D. Joanou", General Atomic Div., General Dynamics Corp, ~, pp.No. GA-1850 (1961)
  5. THERMOS: A Thermalization Transport Theory Code for Reactor Lattice Calculation, "H.C. Honeck", ~, pp.BNL-5826 (1961)
  6. A Program of Research and Calculations of Resonance Absorption, "L. W. Nordheim", General Atomic Div., General Dynamics Corp, ~, pp.Final Report (No. GA-2527) (1961)
  7. Surface resonance absorption in a close-packed lattice, "S.M. Dancoff", United States Atomic Energy Commission, ~ (1944)
  8. M. Ding, "Evaluation of experiments in the AVR with the DALTON–THERMIX coupled code system", Nuclear Engineering and Design, 239(12), pp.3105~3115 (2009), Elsevier BV[DOI]
  9. E. E. Bende, "Analytical Calculation of the Average Dancoff Factor for a Fuel Kernel in a Pebble Bed High-Temperature Reactor", Nuclear Science and Engineering, 133(2), pp.147~162 (1999), Informa UK Limited[DOI]
  10. H. D. Gougar, "Automated Design and Optimization of Pebble-Bed Reactor Cores", Nuclear Science and Engineering, 165(3), pp.245~269 (2010), Informa UK Limited[DOI]
  11. J. L. Kloosterman, "Comparison and Extension of Dancoff Factors for Pebble-Bed Reactors", Nuclear Science and Engineering, 157(1), pp.16~29 (2007), Informa UK Limited[DOI]
  12. Friederike Bostelmann, "SCALE capabilities for high temperature gas-cooled reactor analysis", Annals of Nuclear Energy, 147, pp.107673~ (2020), Elsevier BV[DOI]
  13. Ding She, "PANGU code for pebble-bed HTGR reactor physics and fuel cycle simulations", Annals of Nuclear Energy, 126, pp.48~58 (2019), Elsevier BV[DOI]
  14. Ding She, "XPZ: Development of a lattice code for HTR", Annals of Nuclear Energy, 97, pp.183~189 (2016), Elsevier BV[DOI]
  15. R. Sanchez, "A statistical analysis of the double heterogeneity problem", Annals of Nuclear Energy, 18(7), pp.371~395 (1991), Elsevier BV[DOI]
  16. M. Grimod, "Neutronic modeling of pebble bed reactors in APOLLO2", PhD, pp.2010
  17. Yuechao Liang, "Evaluation of the MOC based on the Sanchez-Pomraning method for double heterogeneity system", Annals of Nuclear Energy, 151, pp.107922~ (2021), Elsevier BV[DOI]
  18. A. E. Kruglikov, "Homogenised group constants generation using Monte Carlo codes for diffusion calculation of pebble bed reactor", Journal of Physics: Conference Series, 1689, pp.012026~ (2020), IOP Publishing
  19. M.A. Kalugin, "Overview of the MCU Monte Carlo software package", Annals of Nuclear Energy, 82, pp.54~62 (2015), Elsevier BV[DOI]
  20. Jaakko Leppänen, "The Serpent Monte Carlo code: Status, development and applications in 2013", Annals of Nuclear Energy, 82, pp.142~150 (2015), Elsevier BV[DOI]
  21. Initial Study on Cross Section Generation Requirements for a PBR Equilibrium Core, "J. Ortensi", Idaho National Lab.(INL), ~, pp.No. INL (2022), EXT-21-64242-Rev000
  22. Jincheng Wang, "Generation method and verification of pebble type VHTR multigroup cross sections based on OpenMC", Annals of Nuclear Energy, 159, pp.108316~ (2021), Elsevier BV[DOI]
  23. Qingming He, "NECP-MCX: A hybrid Monte-Carlo-Deterministic particle-transport code for the simulation of deep-penetration problems", Annals of Nuclear Energy, 151, pp.107978~ (2021), Elsevier BV[DOI]
  24. Forrest B. Brown, "Stochastic geometry capability in MCNP5 for the analysis of particle fuel", Annals of Nuclear Energy, 31(17), pp.2039~2047 (2004), Elsevier BV[DOI]
  25. Algorithms for Monte-Carlo Particle Transport in Binary Statistical Mixtures, "G. B. Zimmerman", Lawrence Livermore National Lab, ~, pp.No. UCRL-JC-108010; CONF-911107-24 (1991)
  26. B. Widom, "Random Sequential Addition of Hard Spheres to a Volume", The Journal of Chemical Physics, 44(10), pp.3888~3894 (1966), AIP Publishing[DOI]
  27. W. S. Jodrey, "Computer simulation of close random packing of equal spheres", Physical Review A, 32(4), pp.2347~2351 (1985), American Physical Society (APS)[DOI]
  28. C. Liang, "Optimization of Monte Carlo transport simulations in stochastic media", Proc. Int. Topl. Mtg. Advances in Reactor Physics, Education (PHYSOR 2012), pp.15~20 (2012)
  29. Paul K. Romano, "OpenMC: A state-of-the-art Monte Carlo code for research and development", Annals of Nuclear Energy, 82, pp.90~97 (2015), Elsevier BV[DOI]
  30. Ding She, "Prediction calculations for the first criticality of the HTR-PM using the PANGU code", Nuclear Science and Techniques, 32(9), pp.1~7 (2021), Springer Science and Business Media LLC[DOI]
  31. E.L. Redmond, "Multigroup Cross Section Generation via Monte Carlo Methods", Doctor, pp.1997
  32. L. Cai, "Condensation and Homogenization of Cross Sections for the Deterministic Transport Codes with Monte Carlo Method: Application to the GEN IV Fast Neutron Reactors", Doctor, pp.2014
  33. Jaakko Leppänen, "Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code", Annals of Nuclear Energy, 96, pp.126~136 (2016), Elsevier BV[DOI]
  34. Sooyoung Choi, "Impact of inflow transport approximation on light water reactor analysis", Journal of Computational Physics, 299, pp.352~373 (2015), Elsevier BV[DOI]
  35. Z. Liu, "Cumulative Migration Method for Computing Multi-Group Transport Cross Sections and Diffusion Coefficients with Monte Carlo Calculations", Doctor, pp.2020
  36. M. Ryu, "Incorporation of anisotropic scattering in nTRACER", Transactions of the Korean Nuclear Society Autumn Meeting (2014)
  37. A. Hebert, "Refinement of the Santamarina-Hfaiedh energy mesh between 22.5eV and 11.4 keV", International Conference on the Physics of Reactors (2008)
  38. Nathanael H. Hudson, "A Pebble Bed Reactor cross section methodology", Annals of Nuclear Energy, 36(8), pp.1138~1150 (2009), Elsevier BV[DOI]
  39. Ding She, "Leakage correction in group-constant generation for pebble-bed HTGRs", Progress in Nuclear Energy, 105, pp.76~82 (2018), Elsevier BV[DOI]
  40. Qiudong Wang, "Evaluation of pebble-bed homogenized cross sections in HTGR fuel cycle simulations", Progress in Nuclear Energy, 117, pp.103041~ (2019), Elsevier BV[DOI]
  41. J. Lieberoth, "Neutron Streaming in Pebble Beds", Nuclear Science and Engineering, 76(3), pp.336~344 (1980), Informa UK Limited[DOI]
  42. Yutong Wen, "An improved homogenization method for the treatment of strong absorbers in pebble-bed HTGR", Annals of Nuclear Energy, 170, pp.108983~ (2022), Elsevier BV[DOI]

관련 논문AI추천

Multigroup cross-sections generated using Monte-Carlo method with flux-moment homogenization technique for fast reactor analysisFeng Kuaiyuan, Gu Hanyang, Guo Hui, Song Qufei, Vidal Jean-François, Wu Yiwei한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제7호Improving tally efficiency and accuracy of multi-group scattering matrix calculations in the Monte Carlo code NECP-MCXCao Liangzhi, He Qingming, Li Yunzhao, Qin Shuai, Shi Jinkang, Wu Hongchun한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제12호Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysisGu Hanyang, Guo Hui, Song Qufei, Wang Ruixiang, Wu Yiwei, Xiao Yao한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제6호Cross section generation for a conceptual horizontal, compact high temperature gas reactorDownar Thomas, Jabaay Daniel, Kang Junsu, Kochunas Brendan, Seker Volkan, Ward Andrew한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제3호Treatment of non-resonant spatial self-shielding effect of double heterogeneous region이현철, 한태영한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제2호Methodology and preliminary verification of generating heterogeneous multigroup microscopic cross-section libraries for neutron transport codes based on OpenMCChen Guohua, Cui Bowen, Jiang Xiaofeng한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제8호

이 간행물의 다른 논문 (39건)

Structural and component characterization of the B4C neutron conversion layer deposited by magnetron sputteringZhu Jingtao, Cui Mingqi, Zhu Hangyu, Yang Zehua, Sun Zhijia, Zhou Xiaojuan, Tan Jinhao, Zhou Jianrong, Liu Yangpp. 3121-3125Research of aluminum nitride water load for the 4.6 GHz 500 kW LHCD system of the CFETRLi Dingzhen, Zhou Taian, Cheng Min, Zhao Lianmin, Zhang Liyuan, Hu Huaichuan, Liu Fukunpp. 3126-3132Simulation of a neutron imaging detector prototype based on SiPM array readoutTang Mengjiao, Zhang Lianjun, He Gaokui, Huang Chang, Zhao Jiangbin, Liu Yang, Tang Binpp. 3133-3139Tackling range uncertainty in proton therapy: Development and evaluation of a new multi-slit prompt-gamma camera (MSPGC) system김성훈, 조성구, 김찬형, 장세현, 조재호, 최세훈, 정종휘, 구영모pp. 3140-3149An intelligent optimization method for the HCSB blanket based on an improved multi-objective NSGA-III algorithm and an adaptive BP neural networkZhang Di, Yang Zihui, Miwa Shuichiro, Sun Guomin, Zhou Wen, Wang Jianye, Li Zhuangpp. 3150-3163
원문 보기