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Abstract:
MELCOR is widely used and sufficiently trusted for severe accident analysis. However, the occurrence of Fukushima has increased the focus on severe accident codes and their use. A MELCOR core degradation calculation was conducted at the University of Wisconsin-Madison under the help of Sandia. The calculation results were checked by comparing with a past CORA experiment MELCOR calculation results included the flow rate of argon and steam, the generation rate of hydrogen. Through this work, the performance of MELCOR COR package was reviewed in detail. This paper compares the hydrogen generation rates predicted by MELCOR to the CORA test data. While agreement is reasonable it could be improved. Additionally, the MELCOR zirconium oxidation model was analyzed. (C) 2014 Elsevier B.V. All rights reserved.
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NUCLEAR ENGINEERING AND DESIGN
ISSN: 0029-5493
Year: 2014
Volume: 276
Page: 191-201
0 . 9 5 2
JCR@2014
1 . 8 6 9
JCR@2020
ESI Discipline: ENGINEERING;
ESI HC Threshold:144
JCR Journal Grade:2
CAS Journal Grade:4
Cited Count:
WoS CC Cited Count: 17
SCOPUS Cited Count: 27
ESI Highly Cited Papers on the List: 0 Unfold All
WanFang Cited Count:
Chinese Cited Count:
30 Days PV: 1
Affiliated Colleges: