Author:
Wang Wanhong,Chen Yangli,Ma Weimin
Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference39 articles.
1. Quantifying reactor safety margins Part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodology;Boyack;Nucl. Eng. Des.,1990
2. Boyack, B.E., Duffey, R., Griffith, P., Lellouche, G., Rohatgi, U.S., Wilson, G., Wulff, W., Zuber, N., 1989. Quantifying Reactor Safety Margins: Application of Code Scaling, Applicability, and Uncertainty Evaluation Methodology to a Large-Break, Loss-of-Coolant Accident (NUREG/CR-5249, Rev. No. 4). Nuclear Regulatory Commission.
3. Blake, L., Gavrus, G., Vecchiarelli, J., Stoklosa, J., 2010. Best Estimate Plus Uncertainty Analysis of LBLOCA for a Pickering B CANDU reactor. Proc. of the ASME 2010 3rd Joint US-European Fluids Engineering Summer Meeting and 8th International Conference on Nanochannels, Microchannels, and Minichannels (FEDSM-ICNMM2010). Montreal, CA. August 1-5.
4. Preliminary results of a comparative as-sessment of ATHLET-CD and MELCOR by simulating the experiment PHEBUS FPT1;Bratfisch,2019
5. Best estimate plus uncertainty analysis of departure from nucleate boiling limiting case with CASL core simulator VERA-CS in response to PWR main steam line break event;Brown;Nucl. Eng. Des.,2016
Cited by
6 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