High Power Laser and Particle Beams, Volume. 35, Issue 7, 076003(2023)
Preliminary study of lead-bismuth reactor system analysis code development
[6] Emonot P, Souyri A, Gandrille J L, et al. CATHARE-3: A new system code for thermal-hydraulics in the context of the NEPTUNE project[J]. Nuclear Engineering and Design, 241, 4476-4481(2011).
[9] [9] D’Angelo A, Gabrielli F. Benchmark on beam interruptions in an acceleratdriven system, final rept on phase II calculations[R]. Paris: OECD Publications, 2004: 177.
[10] [10] Tian Ruifeng, Liu Pingan. Numerical heat transfer fluid flow[M]. Harbin: Harbin Engineering University Press, 2015: 86260
[11] [11] Wang Guimei. Thermalhydraulic optimal design study of primary heat exchanger f lead alloy cooled natural circulation react[D]. Hefei: University of Science Technology of China, 2014: 1928
[12] Chen Changyou. A numerical method of solving the point reactor neutron kinetics equations[J]. Chinese Journal of Nuclear Science and Engineering, 25, 20-23,29(2005).
[13] [13] D’Angelo A, Gabrielli F. Benchmark on beam interruptions in an acceleratdriven system, final rept on phase I calculations[R]. Paris: OECD Publications, 2003: 128.
Get Citation
Copy Citation Text
Yong Luo, Qiwen Pan, Shangdong Yang, Zhixing Gu. Preliminary study of lead-bismuth reactor system analysis code development[J]. High Power Laser and Particle Beams, 2023, 35(7): 076003
Category: Nuclear Science and Engineering
Received: Nov. 2, 2022
Accepted: Mar. 21, 2023
Published Online: Jul. 24, 2023
The Author Email: Gu Zhixing (guzhixing17@163.com)