Published August 1986
| Version v1
Report
Modelling of molten fuel relocation phenomena in a degraded BWR core
- 1. Rensselaer Polytechnic Institute, Troy, NY
Description
A model of fuel melting and relocation has been developed for the analysis of core meltdown accidents of light water nuclear reactors. Both the description of the model and the results of extensive numerical testing and assessment are presented in this paper. The numerical results shown include the test runs for the stand-alone model, as well as the calculations performed following the implementation of this model into the MELRPI code. The latter results are compared with those obtained for the previous version of MELRPI, showing the effect of the new mechanistic model for molten fuel relocation on the accuracy of predicting the timing of core and reactor pressure vessel failure
Additional details
Publishing Information
- Imprint Title
- Proceedings of the topical meeting on reactor physics and safety: Sessions 11-16. Volume 2
- Journal Page Range
- p. 651-660.
- Report number
- NUREG/CP--0080-Vol.2
Conference
- Title
- Advances in reactor physics and safety meeting.
- Dates
- 17-19 Sep 1986.
- Place
- Saratoga Springs, NY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18028518
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCURACY; BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; CORIUM; FAILURES; FUEL ELEMENT FAILURE; M CODES; MATHEMATICAL MODELS; MELTDOWN; PRESSURE VESSELS; REACTOR CORE DISRUPTION; REACTOR SAFETY; TIME DEPENDENCE
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS