A method for predicting configuration of corium pool in lower plenum of reactor vessel
Creators
- 1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)
Description
A method is designed to predict the configuration of the corium pool in the lower plenum of reactor vessel. It takes into account both thermo-chemical reaction of corium and the influence of different paths of corium relocated from core region into the lower plenum. The prediction by this method is consistent with MASCA experimental results and is applied to investigate the corium configuration of a reactor which is subjected to a hypothetical station blackout (SBO) accident. It is shown that for the sideward relocation, the configuration shows a three-lay corium pool. The composition in each layer is calculated based on the thermo-chemical data of the materials. The method is designed to predict the integrity of the reactor vessel under IVR condition. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 37
- Journal Issue
- 3
- Journal Page Range
- p. 138-141
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 50036383
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CALCULATION METHODS; CHEMICAL REACTIONS; CONFIGURATION; CORIUM; DESIGN; REACTOR ACCIDENTS; REACTOR VESSELS; SEVERE ACCIDENTS; STATION BLACKOUT
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CONTAINERS; REACTOR ACCIDENTS
Optional Information
- Notes
- 2 figs., 3 tabs., 10 refs.; http://dx.doi.org/10.13832/j.jnpe.2016.03.0138