Published November 2015 | Version v1
Journal article

Simulation of the PHEBUS FPT-1 experiment using MELCOR and exploration of the primary core degradation mechanism

  • 1. College of Engineering, The University of Wisconsin-Madison, Madison 53706 (United States)
  • 2. State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049 (China)
  • 3. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084 (China)

Description

Highlights: • Core degradation evaluation is an important process in risk analysis. • PHEBUS experiment was simulated using MELCOR. • The results confirm the validity of MELCOR's simulation of the PHEBUS experiment. • These results are used to analyze the mode and behavior of core degradation. - Abstract: Core degradation evaluation of probability, progression and consequences of a core degradation accident is critical for evaluation of risk as well as its mitigation. However, research and modeling of severe accidents to date are limited, and their accuracy in predicting severe accident consequences is still insufficient. It is therefore important to explore the mechanisms of core degradation and to develop mitigation measures for severe accidents. PHEBUS FPT1 is a typical and classic core degradation experiment. MELCOR is a world famous severe accident analysis code developed by Sandia National Lab that has seen wide application, a broad user base, and a number of supporting experiments. The PHEBUS experiment was simulated using MELCOR in this paper. Experimental data on, thermal power and steam mass flow rates are used to determine average pressure, energy distribution, molten mass, temperature of the fuel, and hydrogen generation. Data from the PHEBUS experiment and Cho's calculations are used to compare the average pressure, several fuel temperatures and the hydrogen generation rate. The results confirm the validity of MELCOR's simulation of the PHEBUS experiment. The temperature distribution of the core is provided. These results are used to determine the mode and behavior of core degradation with the intent of building a foundation for further research

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2015.05.015

Additional details

Identifiers

DOI
10.1016/j.anucene.2015.05.015;
PII
S0306-4549(15)00273-X;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
85
Journal Page Range
p. 193-204
ISSN
0306-4549
CODEN
ANENDJ

Optional Information

Copyright
Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.