Comparative analysis of RBMK core channel void fraction determined by RELAP5, KOBRA, and a new drift flux correlation
- 1. Rossijskij Nauchnyj Tsentr ''Kurchatovskij Inst.'', Moscow (Russian Federation)
- 2. GP International, Inc., Columbia, MD (United States)
Description
Simpler algebraic void fraction functions are derived from complicated thermohydraulics codes, such as RELAP5/MOD3, RELAP5/MOD2, and KOBRA. This is a void fraction equation as a function of pressure, vapour volumetric flux, and liquid volumetric flux. It provides a common basis for fruitful comparative analysis of void fraction between complicated code calculations. The comparative analysis also includes the void fraction calculated by a newly developed drift flux correlation and several sets of experimental data. In this paper, good agreement and large deviation are clearly observed for a wide range of thermohydraulic conditions. It is also concluded that simpler drift flux model gives void fraction with accuracy similar to complicated RELAP5/MOD3 code without outstanding numerical problem. A numerical oscillatory problem is encountered in RELAP5/MOD3 calculations. Further investigation is needed to understand the causes of large deviation and numerical oscillation. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 168
- Journal Issue
- 1-3
- Journal Page Range
- p. 119-127.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Switzerland
- INIS RN
- 28057308
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTER CODES; COMPUTERIZED SIMULATION; DRIFT INSTABILITY; LWGR TYPE REACTORS; VOID FRACTION
- Descriptors DEC
- EVALUATION; GRAPHITE MODERATED REACTORS; INSTABILITY; PLASMA INSTABILITY; REACTORS; SIMULATION; WATER COOLED REACTORS