RELAP5 simulation of the ROSA-IV/LSTF SB-CL-18 test using countercurrent flow limitation modeling
- 1. Babcock ampersand Wilcox Co., Lynchburg, VA (United States)
Description
The Wallis form of countercurrent flow limitation (CCFL) model was implemented in RELAP5/MOD2-B ampersand W, and the code was assessed against the ROSA-IV 5% cold-leg small-break loss-of-coolant accident (SBLOCA) test SB-CL-18. The objective of this study was to demonstrate that the code can predict system thermal-hydraulic responses, including CCFL considerations, during an SBLOCA in a pressurized water reactor (PWR). The CCFL correlation was added to RELAP5/MOD2-B ampersand W, similar to the implementation in RELAP5/MOD3. The RELAP5/MOD3 model was found to produce intermittent, nonphysical flow behavior. It was found that such behavior occurred when the momentum equations predicted countercurrent flow, and the CCFL correlation indicated cocurrent flow. RELAP5/MOD2-B ampersand W uses an interative approach to resolve this behavior. When inconsistent flow patterns are predicted by the momentum solution and CCFL correlation, the interphase drag term is progressively adjusted until both solutions predict consistent flow behavior
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 69
- Journal Page Range
- p. 557-558.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 14-18 Nov 1993.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26026006
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COUNTER CURRENT; FLOW RATE; HYDRAULICS; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS; R CODES; REACTOR EXPERIMENTAL FACILITIES; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-931160--.