An assessment of effectiveness of core exit temperatures with respect to PWR core damage state using RELAP/SCDAPSIM/MOD3.4
Creators
- 1. Innovative Systems Software, 1284 South Woodruff Avenue, Idaho Falls, ID 83404 (United States)
Description
Core exit temperature measurements play a very important role in the development and implementation of Severe Accident Management Guidelines. For example, the transition from Emergency Operating Procedures to the Severe Accident Management Guidelines may be triggered by core exit temperatures exceeding set limits. Core exit temperatures may also be used to determine if core cooling has been re-established when different management techniques have been applied. However, core exit temperatures may not always be reliable indicators of the state of the core. For that reason, a systematic study of the relationship between core exit temperatures and the state of the core for different accident conditions and different reactor designs has been started using the detailed system thermal hydraulic and severe accident analysis code package, RELAP/SCDAPSIM. In this paper, the results of the first part of the study is presented and discussed. The paper includes (a) a brief description of the RELAP/SCDAPSIM package, (b) insights from two full plant calculations, a Station Blackout transient for the Surry PWR and the TMI-2 accident analysis, and (c) the results from a series of sensitivity studies to relate core exit temperatures to core damage states for idealized core uncovery, heating, and reflooding scenarios for a typical PWR fuel assembly
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2007.12.011Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2007.12.011;
- PII
- S0029-5493(08)00041-1;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 238
- Journal Issue
- 7
- Journal Page Range
- p. 1547-1560
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40005558
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COOLING; DAMAGE; DESIGN; FUEL ASSEMBLIES; HEATING; IMPLEMENTATION; MANAGEMENT; OUTAGES; PWR TYPE REACTORS; REACTOR ACCIDENTS; RECOMMENDATIONS; SENSITIVITY ANALYSIS; TEMPERATURE MEASUREMENT; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.