Published August 1983
| Version v1
Book
BWR degraded core heatup analysis
Description
As part of EPRI's effort in support of the industry degraded core rulemaking (IDCOR) program, EPRI and its contractor S. Levy, Inc. have developed the best estimate BWR Core Heatup Code for analysis of the core heatup phase of a postulated BWR degraded core accident caused by prolonged loss of adequate core cooling. The core heatup phase is where much of the hydrogen and volatile fission product sources are expected to be generated. A description of the BWR core heatup code is provided together with calculated results for a postulated degraded core accident scenario
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. 2.4-1-2.4-3.
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
- 17069356
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; C CODES; COMPUTERIZED SIMULATION; EPRI; HEAT TRANSFER; HEATING; HYDRAULICS; LOSS OF COOLANT; MELTDOWN; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR SAFETY; TEMPERATURE DEPENDENCE
- 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