[1] Yu Hongxing, Ma Yugao, Zhang Zhuohua, . Initiation and development of heat pipe cooled reactor[J]. Nuclear Power Engineering, 40, 1-8(2019).
[2] Wang Ao, Shen Fengyang, Hu Gu, . A survey of heatpipe space nuclear reactor power supply[J]. Nuclear Techniques, 43, 060002(2020).
[3] McClure P R, Poston D I, Dasari V R, et al. Design of megawatt power level heat pipe reacts[R]. Los Alamos: Los Alamos National Labaty, 2015.
[4] Sterbentz J W, Werner J E, McKellar M G, et al. Special purpose nuclear react (5 MW) f reliable power at remote sites assessment rept[R]. Idaho Falls: Idaho National Labaty, 2017.
[5] Sterbentz J W, Werner J E, Hummel A J, et al. Preliminary assessment of two alternative ce design concepts f the special purpose react[R]. Idaho Falls: Idaho National Labaty, 2018.
[6] Qu Shen, Cao Liangzhi, Zheng Qi, . Development of high-temperature nuclear database and preliminary physical computation of a heat pipe reactor[J]. Modern Applied Physics, 8, 041202(2017).
[7] Li Guanxing, Zhou Bangxin, Xiao Min, . Overall development strategy of China’s new-generation nuclear fuel[J]. Strategic Study of CAE, 21, 6-11(2019).
[8] Fütterer M A, D’Agata E, Laurie M, et al. Next generation fuel irradiation capability in the High Flux Reactor Petten[J]. Journal of Nuclear Materials, 392, 184-191(2009).
[9] Greenquist I, Powers J J. Sensitivity uncertainty of the IFR1 BISON benchmark[R]. Oak Ridge: Oak Ridge National Labaty, 2022.
[10] IAEA. Thermophysical properties of materials f nuclear engineering: a tutial collection of data[M]. Vienna: IAEA, 2008: 92110.
[11] Wang Kan, Li Zeguang, She Ding, et al. RMC—A Monte Carlo code for reactor core analysis[J]. Annals of Nuclear Energy, 82, 121-129(2015).
[12] Liu Xiaobo, Hu Zehua. Monte Carlo calculation of critical benchmarking models for testing ENDF/B-VIII. 0 nuclear data[J]. High Power Laser and Particle Beams, 34, 026003(2022).
[13] Hu Yun, Xu Mi. Development of metallic fuel for fast reactor[J]. Atomic Energy Science and Technology, 42, 810-815(2008).
[14] Gao Yucui, Cao Liangzhi, Yang Yongwei, et al. Physical study of an ultra-long-life small modular fast reactor loaded with U-Pu-Zr fuel[J]. Annals of Nuclear Energy, 142, 107390(2020).
[15] Luzzi L, Cammi A, Di Marcello V, et al. Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor[J]. Nuclear Engineering and Design, 277, 173-187(2014).
[16] Liu Bin, Wang Kai, Tu Jing, et al. Transmutation of minor actinides in the pressurized water reactors[J]. Annals of Nuclear Energy, 64, 86-92(2014).
[17] Yang W S, Kim Y, Hill R N, et al. Long-lived fission product transmutation studies[J]. Nuclear Science and Engineering, 146, 291-318(2004).