Simulation of the PHEBUS FPT-1 experiment using MELCOR and exploration of the primary core degradation mechanism
Creators
- 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.2015.05.015Additional 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
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47019382
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ACCURACY; COMPUTERIZED SIMULATION; ENERGY SPECTRA; EXPERIMENTAL DATA; FLOW RATE; INTERSTITIAL HYDROGEN GENERATION; PHEBUS REACTOR; PRESSURE DEPENDENCE; PROBABILITY; REACTOR ACCIDENTS; REACTOR CORES; RISK ASSESSMENT; STEAM; TEMPERATURE DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; PHYSICAL RADIATION EFFECTS; POOL TYPE REACTORS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; SPECTRA; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.