Published 1989 | Version v1
Book Metadata-only

The analysis of core meltdown progression in BWRs

Creators

  • 1. Rensselaer Polytechnic Inst., Troy, NY (USA). Dept. of Nuclear Engineering and Engineering Physics
  • 2. Empire State Electric Energy Research Corp., New York (USA)

Description

In particular, basic modeling concepts used in the current version of the APRIL computer code (MOD2) are presented concerning degraded core thermal-hydraulics, melt relocation in the reactor pressure vessel (RPV), vessel failure, and hydrogen production. Also, the results of APRIL.MOD2 calculations for a hypothetical ATWS accident in a BWR are given. The accident scenario used is the same as that previously analyzed in an ESEERCO-sponsored code-comparison project. The results of two codes used in this project, i.e., MAAP and MARCH/STCP are compared against the present APRIL.MOD2 calculations. The often substantial differences observed in the predicted accident progression are discussed. (orig./DG)

Additional details

Publishing Information

Publisher
Braun.
Imprint Place
Karlsruhe (Germany, F.R.)
ISBN
3-7650-1115-0
Imprint Title
Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 1
Imprint Pagination
745 p.
Journal Page Range
p. 708-713.

Conference

Title
4. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4).
Dates
10-13 Oct 1989.
Place
Karlsruhe (Germany, F.R.).

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
22029367
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ATWS; BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; CORIUM; FRACTURES; HYDRAULICS; HYDROGEN; INTERSTITIAL HYDROGEN GENERATI; MELTDOWN; PRESSURE VESSELS; REACTOR COMPONENTS; SOURCE TERMS
Descriptors DEC
ACCIDENTS; CONTAINERS; DESIGN BASIS ACCIDENTS; ELEMENTS; ENRICHED URANIUM REACTORS; EVALUATION; FAILURES; NONMETALS; PHYSICAL RADIATION EFFECTS; POWER REACTORS; RADIATION EFFECTS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS