[1]FORSBERG C, HU L, PETERSON P, et al. Fluoride-salt-cooled high-temperature reactor (FHR) for power and process heat[R]. USA: MIT, 2014.
[2]SERP J, ALLIBERT M, BENEŠ O, et al. The molten salt reactor (MSR) in Generation Ⅳ: Overview and perspectives[J]. Progress in Nuclear Energy, 2014, 77: 308-319.
[3]江绵恒,徐洪杰,戴志敏. 未来先进核裂变能——TMSR核能系统[J]. 中国科学院院刊,2012,27(3):366-374.JIANG Mianheng, XU Hongjie, DAI Zhimin. Advanced fission energy program—TMSR nuclear energy system[J]. Bulletin of Chinese Academy of Sciences, 2012, 27(3): 366-374(in Chinese).
[4]黄豫,刘卫,肖德涛,等. 熔盐堆中氚的控制和监测[J]. 核技术,2011,34(8):632-636.HUANG Yu, LIU Wei, XIAO Detao, et al. Control and monitoring of tritium in molten salt reactor[J]. Nuclear Techniques, 2011, 34(8): 632-636(in Chinese).
[5]HOLCOMB D E, FLANAGAN G F, MAYS G T, et al. Fluoride salt-cooled high-temperature reactor technology development and demonstration roadmap[R]. USA: ORNL, 2013.
[6]FORSBERG C W, LAM S, CARPENTER D M, et al. Tritium control and capture in salt-cooled fission and fusion reactors: Status, challenges, and path forward[C]∥Integrated Research Project Workshop Fluoride-salt-cooled High-temperature Reactor (FHR) Workshop. USA: MIT, 2016.
[7]STEMPIEN J D, BALLINGER R G, FORSBERG C W. An integrated model of tritium transport and corrosion in fluoride salt-cooled high-temperature reactors (FHRs), Part Ⅰ: Theory and benchmarking[J]. Nuclear Engineering and Design, 2016, 310: 258-272.
[8]秦浩,王成龙,张大林,等. 氟盐冷却高温堆氚输运特性数值研究[J]. 原子能科学技术,2018,52(3):434-440.QIN Hao, WANG Chenglong, ZHANG Dalin, et al. Numerical analysis of tritium transport characteristics in fluoride-salt-cooled high-temperature reactor[J]. Atomic Energy Science and Technology, 2018, 52(3): 434-440(in Chinese).
[9]FORSBERG C W. Fluoride-salt-cooled high temperature reactors (FHRs) for base-load and peak electricity, grid stabilization, and process heat[R]. USA: MIT, 2013.
[10]王成龙. 移动式氟盐高温堆物理热工安全特性研究[D]. 西安:西安交通大学能源与动力工程学院,2016.
[11]肖瑶. 氟盐冷却高温堆热工水力特性及安全审评关键问题研究[D]. 西安:西安交通大学,2014.
[12]SINAP. Pre-conceptual design of a 2 MW pebble-bed fluoride salts coolant high temperature test reactor (2 MW PB-FHR)[R]. Shanghai: Shanghai Institute of Applied Physics, 2012.
[13]苏光辉,秋穗正,田文喜. 核动力系统热工水力计算方法[M]. 北京:清华大学出版社,2013. |