Citation: | Wang Yanpei, Tang Changbing, Li Quan, Li Tao, Li Chenxi, Qiu Bowen, Fan Hang, Li Yuanming. Research on the Coupling Experiment of Asymmetric Thermal Stress in Solid Core[J]. Nuclear Power Engineering, 2025, 46(1): 152-159. doi: 10.13832/j.jnpe.2025.01.0152 |
[1] |
余红星,马誉高,张卓华,等. 热管冷却反应堆的兴起和发展[J]. 核动力工程,2019, 40(4): 1-8.
|
[2] |
范唯唯. 中国发布《2017-2045 年航天运输系统发展路线图》[J]. 空间科学学报,2018, 38(1): 6.
|
[3] |
柴晓明,马誉高,韩文斌,等. 热管堆固态堆芯三维核热力耦合方法与分析[J]. 原子能科学技术,2021, 55(S2): 189-195.
|
[4] |
王金雨,余红星,柴晓明,等. 热管反应堆燃料经济性影响因素初步探索[J]. 核动力工程,2020, 41(3): 197-201.
|
[5] |
POSTON D I, KAPERNICK R J, GUFFEE R M, et al. Design of a Heatpipe-cooled Mars-surface fission reactor[J]. AIP Conference Proceedings, 2002, 608(1): 1096-1106.
|
[6] |
MCCLURE P R, REID R S, DIXON D D. Advantages and applications of megawatt-sized heat-pipe reactors: No. LA-UR-12-00257; LA-UR-12-257.[R]. La Grange Park: American Nuclear Society, 2012.
|
[7] |
MCCLURE P R, POSTON D I, DASARI V R, et al. Design of megawatt power level heat pipe reactors: LA-UR-15-28840[R]. Los Alamos: Los Alamos National Laboratory, 2015.
|
[8] |
MCCLURE P R, POSTON D I, DIXON D D. Final results of Demonstration Using Flattop Fissions (DUFF) experiment:No. LA-UR-12-25165[R]. Los Alamos: Los Alamos National Lab. , 2012.
|
[9] |
YAN B H, WANG C, LI L G. The technology of micro heat pipe cooled reactor: a review[J]. Annals of Nuclear Energy, 2020, 135: 106948. doi: 10.1016/j.anucene.2019.106948
|
[10] |
HU G, ZHAO S Z, SUN Z Y, et al. A heat pipe cooled modular reactor concept for manned lunar base application[C]//Proceedings of 2013 21st International Conference on Nuclear Engineering. Chengdu: American Society of Mechanical Engineers, 2013: V002T05A031.
|
[11] |
葛攀和,郭键,高剑,等. 星表核反应堆电源系统热工概念设计[J]. 载人航天,2017, 23(6): 784-789.
|
[12] |
张文文,刘逍,田文喜,等. 兆瓦级空间热管反应堆动力系统概念设计[J]. 原子能科学技术,2017, 51(12): 2160-2164.
|
[13] |
STRASSER A, SUNDERLAND D. A review of recent LWR fuel failures[C]//Fuel Failure in Normal Operation of Water Reactors: Experience, Mechanisms and Management. Dimitrovgrad: IAEA, 1993: 17-25.
|
[14] |
刘逍,田智星,王成龙,等. 高温热管传热特性实验研究[J]. 核动力工程,2020, 41(S1): 106-111.
|
[15] |
路怀玉,唐昌兵,李垣明,等. 热管反应堆燃料元件的堆内行为演化模拟研究[J]. 核动力工程,2019, 40(S2): 82-87.
|
[16] |
MIHAILA B, STAN M, RAMIREZ J, et al. Simulations of coupled heat transport, oxygen diffusion, and thermal expansion in UO2 nuclear fuel elements[J]. Journal of Nuclear Materials, 2009, 394(2-3): 182-189. doi: 10.1016/j.jnucmat.2009.09.007
|