Published December 1984 | Version v1
Report Metadata-only

An analysis of core meltdown accidents for BWRs

Creators

  • 1. Rensselaer Polytechnic Inst., Troy, NY (USA). Dept. of Nuclear Engineering

Description

A new computer code for the analysis of BWR degraded core phenomena, MELRPI, has been developed. The MELRPI code uses a machanistic approach to modeling such phenomena, as heat transfer, coolant thermal-hydraulics for a partially or fully uncovered core, metal oxidation, and the melting/relocation of individual core materials. The purpose of this paper is to highlight differences between MELRPI and the MARCH code, including both the modeling concepts and results. The TQUV BWR accident scenario was used for the numerical comparison. It has been shown that these two codes yield considerably different results. (orig./HP)

Additional details

Publishing Information

Imprint Title
5th international meeting on thermal nuclear reactor safety. Proceedings. Vol. 2
Imprint Pagination
664 p.
Journal Page Range
p. 958-967.
Report number
KFK--3880/2

Conference

Title
5. international meeting on thermal nuclear reactor safety.
Dates
9-13 Sep 1984.
Place
Karlsruhe (Germany, F.R.).

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
16068330
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; COMPUTER CALCULATIONS; FAILURES; FUEL CANS; HEAT TRANSFER; HYDROGEN; MELTDOWN; NUMERICAL SOLUTION; ZIRCALOY
Descriptors DEC
ACCIDENTS; ALLOYS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; NONMETALS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS