The challenge of modeling fuel–coolant interaction: Part II – Steam explosion
- 1. Institut de Radioprotection et de Sûreté Nucléaire, IRSN/PSN-RES/SAG, BP 3, 13115 Saint-Paul-Lez-Durance Cedex (France)
- 2. Communication and Systèmes, 22 avenue Galilée, 92350 Le Plessis Robinson (France)
Description
Highlights: • We present the status modeling of steam explosion in the computer code MC3D (a first paper is devoted to premixing stage of FCI). • We also propose a general state of the art, highlighting recent improvements in understanding and modeling, remaining difficulties, controversies and needs. • We highlight the need for improving the understanding of the melt fragmentation and oxidation. • The verification basis is presented. - Abstract: In the course of a severe accident in a nuclear power plant cooled or moderated by water, the core might melt and flow down into the water. Under certain circumstances, a steam explosion might develop during the mixing of the melt and the water. Such an explosion, if occurring in the reactor pit of a PWR or BWR, might challenge the containment integrity and is thus an important issue for nuclear safety. This paper aims at presenting both a status of research and understanding of the phenomenon and the main characteristics of the models developed in the 3-dimensional computer code MC3D. We make a particular emphasis on the underlying difficulties, uncertainties and needs for further improvements. We discuss more particularly the two major phenomena that are the fine fragmentation and the pressurization process. We also give insights on the impact of melt solidification on the fragmentation and on the issue of oxidation. The verification basis of the models is discussed and finally, an example of 3D calculation is presented to highlight the current code capabilities
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2014.08.028Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2014.08.028;
- PII
- S0029-5493(14)00503-2;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 280
- Journal Page Range
- p. 528-541
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46100815
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; COOLANTS; EXPLOSIONS; FRAGMENTATION; FUEL-COOLANT INTERACTIONS; MIXING; NUCLEAR POWER PLANTS; OXIDATION; PWR TYPE REACTORS; SIMULATION; STEAM
- Descriptors DEC
- CHEMICAL REACTIONS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.