Citation: | Qian Yalan, Lin Qian, Yang Zijiang, Chen Kang, Zhan Wenhui, Tang Chuntao, Yang Bo. Research on Characteristics of Secondary Side Passive Residual Heat Removal System of Lead-bismuth Reactor under SBO[J]. Nuclear Power Engineering, 2024, 45(4): 32-37. doi: 10.13832/j.jnpe.2024.04.0032 |
[1] |
吴宜灿,王明煌,黄群英,等. 铅基反应堆研究现状与发展前景[J]. 核科学与工程,2015, 35(2): 213-221.
|
[2] |
刘玉康,文青龙,乔鹏瑞,等. 全厂断电事故工况下小型铅铋快堆余热排出能力评价[J]. 原子能科学技术,2021, 55(11): 2028-2035.
|
[3] |
陈学锋. 核电厂全厂断电事故分析[J]. 中国核电,2011, 4(1): 46-51.
|
[4] |
盛美玲,金鸣,柏云清,等. 中国铅合金冷却研究堆事故余热排出系统概念设计与分析[J]. 核科学与工程,2014, 34(1): 91-96.
|
[5] |
夏少雄,王家群,潘晓磊,等. 中国铅基研究堆非能动余热排出系统可靠性分析[J]. 核技术,2015, 38(2): 020605.
|
[6] |
International Atomic Energy Agency. Advances in small modular reactor technology developments: 20-02510E[R]. Vienna: IAEA, 2020.
|
[7] |
吴国伟. 铅基堆非能动余热排出系统的设计研究[D]. 合肥: 中国科学技术大学,2017.
|
[8] |
European Seventh Framework Programme. Conceptual design of the DHR system of the ETDR (ALFRED): FP7-249668[R]. European Union, 2012.
|
[9] |
GOLOVIN A O, SIVAK Z V, LEONCHUK M P. Analysis of safety aspects of the svbr-75/100 power installation as applied to regional nuclear cogeneration plant[J]. Dysnai, 2003: 101.
|
[10] |
PETROCHENKO V, TOSHINSKY G, KOMLEV O. SVBR-100 nuclear technology as a possible option for developing countries[J]. World Journal of Nuclear Science and Technology, 2015, 5(3): 221-232. doi: 10.4236/wjnst.2015.53022
|
[11] |
International Atomic Energy Agency. Liquid metal coolants for fast reactors cooled by sodium, lead, and lead-bismuth eutectic: NP-T-1.6[R]. Vienna: IAEA, 2012.
|
[12] |
MELONI P, WAGNER A D, CASTIGLIA F, et al. Investigation of Relap capability to simulate the LBE cooling system thermal-hydraulic[J]. Centro Ricerche Bologna, 2004, 1: 637-647.
|
[13] |
薛冰,刘晓晶,何兆忠. 10MW固态燃料熔盐堆热阱丧失事故安全分析[J]. 核科学与工程,2019, 39(6): 966-974.
|
[14] |
卢永刚. 铅铋冷却快堆主循环泵优化设计与可靠性分析[D]. 镇江: 江苏大学,2019.
|
[15] |
石康丽. 铅冷快堆始发事件及瞬态安全特性初步研究[D]. 合肥: 中国科学技术大学,2017.
|
[16] |
TOSHINSKII G. Lead-bismuth cooled fast reactors[M]. Riga: LAMBERT Academic Publishing, 2017.
|