Published June 2016 | Version v1
Journal article

A method for predicting configuration of corium pool in lower plenum of reactor vessel

  • 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

Optional Information

Notes
2 figs., 3 tabs., 10 refs.; http://dx.doi.org/10.13832/j.jnpe.2016.03.0138