کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
296308 | 511721 | 2014 | 11 صفحه PDF | دانلود رایگان |
• Oxidation model of MELCOR is analyzed and the improving suggestion is provided.
• MELCOR core degradation calculating results are compared with CORA experiment.
• Flow rate of argon and steam, the generating rate of hydrogen is calculated and compared.
• Temperature spatial variation and temperature history is calculated and presented.
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.
Journal: Nuclear Engineering and Design - Volume 276, September 2014, Pages 191–201