Development of a neutronics analysis code for pebble-bed HTRs

Nuclear Engineering and Design - Tập 329 - Trang 192-197 - 2018
Ding She1, Jiong Guo1, Zhihong Liu1, Lei Shi1
1Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China

Tài liệu tham khảo

Bende, 1999, Analytical calculation of the average Dancoff factor for a fuel kernel in a pebble bed high-temperature reactor, Nucl. Sci. Eng., 133, 147, 10.13182/NSE99-A2078 Edenius, M., Ekberg, K., Forssén, B.H., Knott, D., 1995. CASMO-4, A Fuel Assembly Burnup Program, User’s Manual. Studsvik0SOA-9501, Studsvik of America Inc. Gougar, H.D., Ougouag, A.M., Terry, W.K., 2004. Advanced Core Design and Fuel Management for Pebble-bed Reactors (No. INEEL/EXT-04-02245). Idaho National Laboratory (INL). Hébert, A., 2014. The Version5 Dragon/Donjon Distribution. http://www.polymtl.ca/merlin (accessed 18.09.17). Kunitomi, K., Sun, Y., Ball, S., Brey, H.L., Methnani, M., 2003. Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to Initial Testing of the HTTR and HTR-10. International Atomic Energy Agency, Report No. IAEA-TEDOC-1382, 227–322. Levine, 1963, Resonance integral calculations for 238U lattices, Nucl. Sci. Eng., 16, 271, 10.13182/NSE63-A26530 Lieberoth, 1980, Neutron streaming in pebble beds, Nucl. Sci. Eng., 76, 336, 10.13182/NSE80-A21324 Mathews, D., 1997. An improved version of the MICROX-2 code. Paul Scherrer Institut. Nojiri, N., Fujimoto, N., Mouri, T., Obata, H., 2004. DELIGHT-8: One Dimensional Fuel Cell Burnup Analysis Code for High Temperature Gas-cooled Reactors. JAERI-Data/Code. Nordheim, 1961, The theory of resonance absorption, Proc. Symp. Appl. Math., 11, 58, 10.1090/psapm/011/9987 She, D., Xie, F., et al., 2015. Explicit modeling of double-heterogeneous pebble-bed reactors with the RMC code. In: M&C+ SNA+MC 2015, Nashville, TN, April 19–23. She, 2016, XPZ: development of a lattice code for HTR, Ann. Nucl. Energy, 97, 183, 10.1016/j.anucene.2016.07.017 She, 2017, An equivalent homogenization method for treating the stochastic media, Nucl. Sci. Eng., 185, 351, 10.1080/00295639.2016.1272363 Teuchert, E., Breitbarth, R., 1968. Resonanzintegral-berechnung für mehrfach heterogene Anordnungen. Jül-551-RG. Teuchert, E., Hansen, U., Haas, K.A., et al., 1994. V. S. O.P. (’94) Computer Code System for Reactor Physics and Fuel Cycle Simulation. Juel-2897. Umbarger A., DiGiovine S., 1992. SIMULATE-3, Advanced Three-Dimensional Two-Group Reactor Analysis Code, User’s Manual. Studsvik/SOA-92/01. Wu, 2002, The design features of the HTR-10, Nucl. Eng. Des., 218, 25, 10.1016/S0029-5493(02)00182-6 Zhang, 2006, Design aspects of the Chinese modular high-temperature gas-cooled reactor HTR-PM, Nucl. Eng. Des., 236, 485, 10.1016/j.nucengdes.2005.11.024