Investigation on influence of crust formation on VULCANO VE-U7 corium spreading with MPS method
- 1. Cooperative Major in Nuclear Energy, Graduate School of Advanced Science and Engineering, Faculty of Science and Engineering, Waseda University, 3-4-1 Okubo, Shinjuku-ku, Tokyo 169-8555 (Japan)
- 2. Central Research Institute of Electric Power Industry (Japan)
- 3. Graduate School of Engineering, Osaka University (Japan)
Description
Highlights: • The new crust formation model was developed for the MPS spreading analysis code. • The VULCANO VE-U7 corium spreading experiment was analyzed by the developed code. • The termination of the spreading was governed by the crust formation at the leading edge. - Abstract: In a severe accident of a light water reactor, the corium spreading behavior on a containment floor is important as it may threaten the containment vessel integrity. The Moving Particle Semi-implicit (MPS) method is one of the Lagrangian particle methods for simulation of incompressible flow. In this study, the MPS method is further developed to simulate corium spreading involving not only flow, but also heat transfer, phase change and thermo-physical property change of corium. A new crust formation model was developed, in which, immobilization of crust was modeled by stopping the particle movement when its solid fraction is above the threshold and is in contact with the substrate or any other immobilized particles. The VULCANO VE-U7 corium spreading experiment was analyzed by the developed MPS spreading analysis code to investigate influences of different particle sizes, the corium viscosity changes, and the "immobilization solid fraction" of the crust formation model on the spreading and its termination. Viscosity change of the corium was influential to the overall progression of the spreading leading edge, whereas termination of the spreading was primarily determined by the immobilization of the leading edge (i.e., crust formation). The progression of the leading edge and termination of the spreading were well predicted, but the simulation overestimated the substrate temperature. Further investigations may be necessary for the future study to see if thermal resistance at the corium-substrate boundary has significant influence on the overall spreading behavior and its termination.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2017.04.002Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2017.04.002;
- PII
- S0306-4549(16)31087-8;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 107
- Journal Page Range
- p. 119-127
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48086730
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTAINMENT; CORIUM; HEAT TRANSFER; INCOMPRESSIBLE FLOW; PARTICLE SIZE; REACTOR ACCIDENT SIMULATION; SEVERE ACCIDENTS; SUBSTRATES; VISCOSITY; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; ENERGY TRANSFER; FLUID FLOW; REACTORS; SIMULATION; SIZE
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.