[1] YUAN Xudong, MA Huiqiang, CHEN Zhenping et al. Study on activation-induced dose calculation of reactor structural materials[J]. Nuclear Power Engineering, 42, 103-109(2021).

[2] Wilson P P H, Tsige-Tamirat H, Khater H Y et al. Validation of the alara activation code[J]. Fusion Technology, 34, 784-788(1998).

[3] Wilson P P H. ALARA: analytic and laplacian adaptive radioactivity analysis[D](1999).

[4] Forrest R A. FISPACT-2007: user manual[R]. UKAEA FUS534(2007).

[5] Zhang J Y, Ma Y D, Peng Y et al. ABURN: a material activation calculation code based on CRAM method[J]. Fusion Engineering and Design, 125, 659-663(2017).

[6] Li J, She D, Shi L. Research on MMPA algorithm for solving detailed depletion chain with the NUIT code[J]. Journal of Nuclear Engineering and Radiation Science, 4, 021007(2018).

[7] Weifeng LYU, CHEN Mingliang, HUANG Qianqian et al. Development on calculation code CPAP for radioactive activation product of pressurized water reactor nuclear power plant[J]. Nuclear Techniques, 43, 040005(2020).

[8] PEI Lucheng, ZHANG Xiaoze[M]. Monte Carlo method and its application to particle transport problems(1980).

[9] YU Ganglin, WANG Kan, WANG Yuhong. MCBurn—a coupling package of program MCNP and ORIGEN[J]. Atomic Energy Science and Technology, 37, 250-254(2003).

[10] Moore R L, Schnitzler B G, Wemple C A et al. MOCUP: MCNP-ORIGEN2 coupled utility program[R]. INEL-95/0523(1995).

[11] Trellue H R. Development of monteburns: a code that links MCNP and ORIGEN2 in an automated fashion for burnup calculations[D]. LA-13514-T Thesis(1998).

[12] Brown F B. MCNP6 optimization and testing for criticality safety calculations[J]. Transactions of the American Nuclear Society, 112, 464-466(2015).

[13] Leppänen J, Pusa M, Viitanen T et al. The Serpent Monte Carlo code: status, development and applications in 2013[J]. Annals of Nuclear Energy, 82, 142-150(2015).

[14] LI Gang, ZHANG Baoyin, DENG Li et al. Development of Monte Carlo particle transport code JMCT[J]. High Power Laser and Particle Beams, 25, 158-162(2013).

[15] SUN Guangyao, SONG Jing, ZHENG Huaqing et al. Verification of neutron transport calculation in super Monte Carlo calculation software SuperMC2.0[J]. Atomic Energy Science and Technology, 47, 520-525(2013).

[16] He Q M, Li J, Shu H L et al. Particle-transport/depletion/activation/source-term coupling analysis for CFETR with NECP-MCX[J]. Fusion Engineering and Design, 188, 113399(2023).

[17] YU Hui, QUAN Guoping, QIN Yao et al. Development and application of COSINE reactor Monte Carlo code cosRMC[J]. Nuclear Power Engineering, 42, 218-223(2021).

[18] Ding S, Liu Y, Kan W et al. Development of burnup methods and capabilities in Monte Carlo code RMC[J]. Annals of Nuclear Energy, 51, 289-294(2013).

[19] SHE Ding, WANG Kan, YU Ganglin. Development of burnup calculation function in reactor Monte Carlo code RMC[J]. Nuclear Power Engineering, 33, 1-5, 11(2012).

[20] TANG Xiao, LIANG Jingang, WANG Kan et al. Verification of RMC critical calculation based on BEAVRS full-stack benchmark problem[J]. Nuclear Power Engineering, 35, 235-238(2014).

[21] Pashchenko A B, Wienke H, Kopecky J et al. FENDL/A-2.0. Neutron activation cross section data library for fusion applications[J]. International Atomic Energy Agency Nuclear Data(1997).

[22] Conlin J L, Kahler A C, Mccartney A P. Open source release of NJOY2016 and NJOY21[J]. Transactions of the American Nuclear Society, 116, 693-696(2017).