JIANG Mian heng, XU Hongjie, DAI Zhimin. The future of advanced nuclear fission energy--TMSR nuclear energy systems[J]. Bulletin of Chinese Academy of Sciences, 2012, 27(003): 366-74
[2]
2 William R C, Timothy D B, William G H, et al. Updated generation IV reactors ingrated materials technology program plan, Revision 2[R].USA: Oak Ridge National Laboratory, 2003
[3]
3 Ingersoll D T, Forsberg C W, Williams D F, et al. Status of pre-conceptual design of the advanced high-temperature reactor[R]. USA: Oak Ridge National Laboratory, 2004
[4]
4 Kim H C, Kim Y S, Kim J K, et al. Monte Carlo benchmark calculations for 400MWth PBMR core[C]. 13th International Conference on Emerging Nuclear Energy Systems, Istanbul, Turkey, 03-08 June 2007
[5]
5 de Zwaan S J. The Liquid Salt Temperature of Pebble Bed Reactor[D]. Delft University of Technology, The Netherlands, 2005
[6]
6 Fratoni M. Development and applications of methodologies for the neutronic design of the Pebble Bed Advanced High Temperature Reactor (PB-AHTR)[R]. USA: University of California, Berkeley, 2008
[7]
7 Fran?ois-Paul, Fabien Koenig. Preliminary study of the pebble-bed advanced high temperature reactor[R]. USA: University of California, Berkeley, 2006
[8]
8 SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluations[G], ORNL/TM-2005/39, Version5, Vols. I–III, April 2005
[9]
9 de HART M D. A Two-Dimensional Transport And Depletion Module For Characterization Of Spent Nuclear Fuel[R]. USA: ORNL, 2006
[10]
10 N M Greene. Resonance Self-Shielding By The Bondarenko Method[R]. USA: ORNL, 2006
[11]
11 M L Williams, M Asgaria, D F Hollenbach. A One-Dimensional Neutron Transport Code For Computing Pointwise Energy Spectra[R]. USA: ORNL, 2006
[12]
12 M L Williams, D F Hollenbach. A Program To Produce Multigroup Cross Sections Using Pointwise Energy Spectra From Centrm[R]. USA: ORNL, 2006
[13]
13 D F Hollenbach, L M Petrie, N F Landers. A General Quadratic Version Of The Keno Program[R], Oak Ridge National Laboratory, 2005
[14]
14 I C Gauld, O W Hermann, R M Westfall. ORIGEN-S: SCALE system module to calculate fuel depletion, actinide transmutation, fission product buildup and decay, and associated radiation source terms[R], Oak Ridge National Laboratory, 2006
