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.
| Original language | English |
|---|---|
| Pages (from-to) | 191-201 |
| Number of pages | 11 |
| Journal | Nuclear Engineering and Design |
| Volume | 276 |
| DOIs | |
| State | Published - Sep 2014 |
Keywords
- CORA
- Core degradation
- Hydrogen generating rate
- MELCOR
- Oxidation model
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