Independent assessment of TRAC-PF1 (Version 7. 0), RELAP5/MOD1 (Cycle 14), and TRAC-BD1 (Version 12. 0) codes using separate-effects experiments

Technical Report · Thu Aug 01 00:00:00 EDT 1985

DOI:https://doi.org/10.2172/6187959· OSTI ID:6187959

Saha, P; Jo, J H; Neymotin, L; Rohatgi, U S; Slovik, G C; Yuelys-Miksis, C

This report presents the results of independent code assessment conducted at BNL. The TRAC-PF1 (Version 7.0) and RELAP5/MOD1 (Cycle 14) codes were assessed using the critical flow tests, level swell test, countercurrent flow limitation (CCFL) tests, post-CHF test, steam generator thermal performance tests, and natural circulation tests. TRAC-BD1 (Version 12.0) was applied only to the CCFL and post-CHF tests. The TRAC-PWR series of codes, i.e., TRAC-P1A, TRAC-PD2, and TRAC-PF1, have been gradually improved. However, TRAC-PF1 appears to need improvement in almost all categories of tests/phenomena attempted to BNL. Of the two codes, TRAC-PF1 and RELAP5/MOD1, the latter needs more improvement particularly in the areas of: CCFL, Level swell, CHF correlation and post-CHF heat transfer, and Numerical stability. For the CCFL and post-CHF tests, TRAC-BD1 provides the best overall results. However, the TRAC-BD1 interfacial shear package for the countercurrent annular flow regime needs further improvement for better prediction of CCFL phenomenon. 47 refs., 87 figs., 15 tabs.

• Research Organization: Brookhaven National Lab. (BNL), Upton, NY (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6187959
• Report Number(s): NUREG/CR-4359; BNL-NUREG-51919; ON: TI86006331
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
HEAT TRANSFER
HYDRAULICS
COMPUTER CODES
EVALUATION
FLUID FLOW
MATHEMATICAL MODELS
NATURAL CONVECTION
STEAM GENERATORS
ACCIDENTS
BOILERS
CONVECTION
ENERGY TRANSFER
FLUID MECHANICS
MASS TRANSFER
MECHANICS
REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled