Author:
Zhou Lei,Zhang Dalin,Wang Shibao,Liu Yapeng,Wang Chenglong,Tian Wenxi,Qiu Suizheng,Su G.H.
Funder
K C Wong Education Foundation
National Natural Science Foundation of China
Subject
Nuclear Energy and Engineering
Reference24 articles.
1. A summary of sodium-cooled fast reactor development;Aoto;Prog. Nucl. Energy,2014
2. Boyack, B.E., Motta, A.T., Peddicord, K.L., et al., 2001. Phenomenon Identification and Ranking Tables (PIRTs) for Loss-of-Coolant Accidents in Pressurized and Boiling Water Reactors Containing High Bumup Fuel.
3. CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor;Chen;Ann. Nucl. Energy,2018
4. N. Doda H. Ohshima H. Kamide et al. Development of PIRT for Fast Reactor under Natural Circulation Decay Heat Removal Operations 2011 Makuhari, Chiba, Japan
5. Preliminary phenomena identification and ranking tables on the subject of the High Temperature Gas-cooled Reactor-Pebble Bed Module thermal fluids and accident analysis;Gou;Nucl. Eng. Des.,2018
Cited by
5 articles.
订阅此论文施引文献
订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献