Published 1983 | Version v1
Book Metadata-only

Modelling of whole-core release of fission products in PWR core melt accidents: Chapter 13

Creators

  • 1. UKAEA, Safety and Reliability Directorate, Culcheth, Warrington WA3 4NE

Description

The computer code FISREL combines the thermal history of a reactor core with experimentally-based release rate constants to calculate whole-core 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
American Nuclear Society.
Imprint Place
LaGrange Park, IL (USA)
ISBN
0-89448-112-6
Imprint Title
Proceedings of the international meeting on light water severe accident evaluation
Journal Page Range
p. 4.1-4.7.

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
18013602
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; EVAPORATION; F CODES; FISSION PRODUCT RELEASE; MASS TRANSFER; MELTDOWN; PRESSURE DEPENDENCE; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR CORES; SENSITIVITY ANALYSIS; THERMAL ANALYSIS; TRANSIENTS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS