[1] Yang W S. Fast reactor physics and computational methods[J]. Nuclear Engineering and Technology, 44, 177-198(2012).
[2] Lee C, Yang W S. MC2-3: multigroup cross section generation code for fast reactor analysis[J]. Nuclear Science and Engineering, 187, 268-290(2017).
[3] Kim K S, Williams M L, Holcomb A M et al. The SCALE/AMPX multigroup cross section processing for fast reactor analysis[J]. Annals of Nuclear Energy, 132, 161-171(2019).
[4] Ruggieri J M, Tommasi J, Lebrat J F et al. ERANOS 2.1: international code system for GEN IV fast reactor analysis[C], 2432-2439(2006).
[5] Rimpault G, Plisson D, Tommasi J et al. The ERANOS code and data system for fast reactor neutronic analyses[C](2002).
[6] Guo H, Garcia E, Faure B et al. Advanced method for neutronic simulation of control rods in sodium fast reactors: numerical and experimental validation[J]. Annals of Nuclear Energy, 129, 90-100(2019).
[7] Roque B, Rizzo A, Pascal V et al. Experimental validation of the new code package APOLLO3-SFR against ZPPR-10A experiment for critical and voided configurations[C](2016).
[8] Hazama T, Chiba G, Sugino K. Development of a fine and ultra-fine group cell calculation code SLAROM-UF for fast reactor analyses[J]. Journal of Nuclear Science and Technology, 43, 908-918(2006).
[9] Bae M H, Choi Y W, Shin A et al. Preliminary Development of SFR Nuclear Code System for Regulatory Evaluation[C](2016).
[10] Lim C, Joo H G, Yang W S. Development of a fast reactor multigroup cross section generation code EXUS-F capable of direct processing of evaluated nuclear data files[J]. Nuclear Engineering and Technology, 50, 340-355(2018).
[11] YANG Xiaoyan, YU Hong, GANG Zhi et al. Loading scheme research on the first criticality of China experimental fast reactor[J]. Atomic Energy Science and Technology, 47, 58-61(2013).
[12] Hu K, Ma X B, Zhang T et al. MGGC2.0: a preprocessing code for the multi-group cross section of the fast reactor with ultrafine group library[J]. Nuclear Engineering and Technology, 55, 2785-2796(2023).
[13] Du X N, Cao L Z, Zheng Y Q et al. A hybrid method to generate few-group cross sections for fast reactor analysis[J]. Journal of Nuclear Science and Technology, 55, 931-944(2018).
[14] Zhou S C, Wu H C, Cao L Z et al. LAVENDER: a steady-state core analysis code for design studies of accelerator driven subcritical reactors[J]. Nuclear Engineering and Design, 278, 434-444(2014).
[15] He M T, Wu H C, Zheng Y Q et al. Beam transient analyses of Accelerator Driven Subcritical Reactors based on neutron transport method[J]. Nuclear Engineering and Design, 295, 489-499(2015).
[16] Zheng Y Q, Qiao L, Zhai Z A et al. SARAX: a new code for fast reactor analysis Part II: verification, validation and uncertainty quantification[J]. Nuclear Engineering and Design, 331, 41-53(2018).
[17] Du X N, Choe J, Tran T Q et al. Neutronic simulation of China Experimental Fast Reactor start-up tests. Part I: SARAX code deterministic calculation[J]. Annals of Nuclear Energy, 136, 107046(2020).
[18] DU Xiannan. Few-group cross section generation method for fast reactor analysis and its verification and validation[D](2018).
[19] Briggs J B, Scott L, Nouri A. The international criticality safety benchmark evaluation project[J]. Nuclear Science and Engineering, 145, 1-10(2003).
[20] Brown F, Kiedrowski B, Bull J. MCNP5-1.60 release notes[R]. Report No. LA-UR-10e06235(2010).
[21] Hadwick M, Obložinský P, Herman M et al. ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology[J]. Nuclear Data Sheets, 107, 2931-3059(2006).
[22] Lee C, Jung Y, Yang W. MC2-3: multigroup cross section generation code for fast reactor analysis nuclear[R](2018).
[23] Perey C, Perey F, Harvey J et al. 56Fe resonance parameters for neutron energies up to 850 keV[R](1990).