Thermal/hydraulic analysis research program quarterly report, January-March 1983. [PWR]
The RELAP5 independent assessment project at Sandia National Laboratories is part of a multi-faceted effort sponsored by the NRC to determine the ability of various system codes to predict the detailed thermal-hydraulic response of LWRs during accident and off-normal conditions. The version used for the FY 1982 assessment project was RELAP5/MOD1/CYCLE14. The RELAP5 code is being assessed at SNLA against test data from various integral and separate effects experimental test facilities. The results for Semiscale natural circulation tests S-NC-2 and S-NC-7 show that RELAP5/MOD1 qualitatively describes all modes of natural circulation correctly, but with quantitative disagreement on both the absolute magnitude of the two-phase natural circulation, and on the mass inventories at which various mode transitions occur. The results for LOFT test L5-1/L8-2 show that the primary side response for this set of intermediate break transients is well predicted by both cycle 14 and cycle 18 of MOD1. The B and W steam generator results show that cycle 18 of RELAP5/MOD1 cannot correctly calculate man of the important parameters for steady-state OTSG conditions.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5786804
- Report Number(s):
- NUREG/CR-3329-1; SAND-83-1171; ON: DE83016688
- Country of Publication:
- United States
- Language:
- English
Similar Records
RELAP5 assessment: semiscale natural circulation tests S-NC-3, S-NC-4, and S-NC-8
RELAP5 assessment: LOFT small-break L3-6/L8-1. [PWR]
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ACCIDENTS
COMPUTER CALCULATIONS
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INFORMATION
MECHANICS
NUMERICAL DATA
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
TEST FACILITIES
THEORETICAL DATA
WATER COOLED REACTORS
WATER MODERATED REACTORS