Development of a neutronics analysis code for pebble-bed HTRs
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
