A nodal sensitivity study of MELCOR simulation for severe accidents in a pressurized water reactor
Author:
Funder
Swedish Radiation Safety Authority
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference25 articles.
1. A sensitivity study of MELCOR nodalization for simulation of in-vessel severe accident progression in a boiling water reactor;Chen;Nucl. Eng. Des.,2019
2. Analysis of the accident in the Fukushima Daiichi nuclear power station Unit 3 with MELCOR_2.1;Fernandez-Moguel;Ann. Nucl. Energy,2015
3. Galushin, S., Kudinov, P., 2018. Sensitivity analysis of the vessel lower head failure in Nordic BWR using MELCOR code. Proc. of the 14th Conference on Probabilistic Safety Assessment and Management (PSAM-14). Los Angeles, CA. September 16-21.
4. The establishment of MELCOR/SNAP model of Chinshan nuclear power plant for Ultimate Response Guideline;Hsu;Nucl. Eng. Des.,2017
5. Performance of a passive cooling system for spent fuel pool using two-phase thermosiphon evaluated by RELAP5/MELCOR coupling analysis;Huang;Annuals of Nuclear Energy,2019
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