Comparison of Hydrogen Generation Rate between CORA-13 Test and MELCOR Simulation: Clad Solid-Phase Oxidation Models Using Self-Developed Code MYCOAC-Reference-Cited by-同舟云学术

Comparison of Hydrogen Generation Rate between CORA-13 Test and MELCOR Simulation: Clad Solid-Phase Oxidation Models Using Self-Developed Code MYCOAC

Published:2015-10 Issue:1 Volume:192 Page:25-34
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Wang Jun¹²,Corradini Michael L.²,Haskin Troy²,Zhang Yapei¹,Lu Qing³,Tian Wenxi¹,Su Guanghui¹,Qiu Suizheng¹

Affiliation:

1. Xi’an Jiaotong University, State Key Laboratory of Multiphase Flow in Power Engineering, Xi’an, 710049, China

2. University of Wisconsin–Madison, College of Engineering, Madison, Wisconsin 53706

3. Nuclear Power Institute of China, Chengdu, 610041, China

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT14-96

Reference11 articles.

1. R. GAUNT et al. “Fukushima Daiichi Accident Study,” SAND 2012-6173, Sandia National Laboratories (Aug. 2012).

2. L. L. HUMPHRIES et al. “MELCOR Computer Code Manuals,” NUREG/CR-6119, Vol. 2, Rev. 4, U.S. Nuclear Regulatory Commission (2008).

3. M. FIMHABER et al. “CORA-13 Experiment on Severe Fuel Damage Comparison Report,” GRS-106, KFK 5287, NEA/CSNI/R (93) 17.3-923875-67-89, Nuclear Energy Agency, Committee on the Safety of Nuclear Installations (1993).

4. R. O. GAUNTT et al. “MELCOR Computer Code Manuals,” NUREG/CR-6119, Vol. 3, Rev. 0, SAND2001-0929P, Sandia National Laboratories (2001).

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