Published August 1983 | Version v1
Book Metadata-only

Modelling of whole-core release of fission products in PWR core melt accidents

Creators

  • 1. UKAEA, Safety and Reliability Directorate, Culcheth, Warrington

Description

The computer code FISREL combines the thermal history of a reactor core with experimentallybased release rate constants to calculate wholecore release histories of fission products in PWR core melt accidents. Predictions of the code for releases of volatile fission products during large-break, small-break and transient initiated sequences are presented, and the sensitivities of results to input data examined. A preliminary assessment of the limitations imposed by mass transport on release of vaporized materials in high pressure sequences is given, and the implications of the results for primary system transport are discussed

Additional details

Publishing Information

Publisher
Stone and Webster Engineering Corporation.
Imprint Place
Boston, MA (USA)
Imprint Title
Light water reactor severe accident evaluation
Journal Page Range
p. 13.4-1-13.4-7.

Conference

Title
International meeting on light-water reactor severe accident evaluation.
Dates
28 Aug - 1 Sep 1983.
Place
Cambridge, MA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17069562
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; F CODES; FISSION PRODUCT RELEASE; HEAT TRANSFER; HYDRAULICS; MELTDOWN; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY; SENSITIVITY ANALYSIS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS