Assessment of the GOTHIC and RELAP5/MOD3 computer codes against BWR-related experiments from the Full Scale Test Facility (FSTF)
- Yankee Atomic Electric Co., Bolton, MA (United States)
Many methods, or computer codes, are used for analyzing the thermal-hydraulic response of containments to postulated accident sequences. Among the codes generally available for this purpose are the GOTHIC and RELAP5 computer codes. However, these codes have not been tested well in the area of Boiling Water Reactor (BWR) containment responses. The purpose of this paper is to evaluate the limitations and capabilities of these two codes in analyzing BWR containment response. Test data from the Full Scale Test Facility (FSTF), which simulates accident response of BWR containments, are used. Assessment results of two tests (Tests M2 and M8) are presented. Comparison of the calculated and measured drywell and wetwell response (pressure, temperature) is made and capabilities and limitations of each code in being able to predict the test phenomena are discussed.
- OSTI ID:
- 400856
- Report Number(s):
- CONF-950828-; TRN: 96:030286
- Resource Relation:
- Conference: 1995 National heat transfer conference, Portland, OR (United States), 5-9 Aug 1995; Other Information: PBD: 1995; Related Information: Is Part Of Heat transfer -- Portland 1995; El-Genk, M.S. [ed.] [Univ. of New Mexico, Albuquerque, NM (United States)]; PB: 378 p.; AIChE Symposium Series, Volume 91, Number 306
- Country of Publication:
- United States
- Language:
- English
Similar Records
RELAP-7 Application and Enhancement for FLEX Strategies and ATF Behavior under Extended Loss of AC Power Conditions
Mitigation of internally initiated severe accidents for a BWR Mark-II power plant