Thermal/hydraulic analysis research program. Quarterly report, April-June 1983. Volume 2. [PWR]

Technical Report · Thu Sep 01 00:00:00 EDT 1983

OSTI ID:5348377

Thompson, S L

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 latest publicly released version available at the time this project was begun. The RELAP5 code is being assessed at SNLA against test data from various integral and separate effects experimental test facilities. At the request of the NRC contract monitor, the FY 1983 project was expanded to include TRAC-PF1 and RELAP5 plant analyses. A design-basis 200% cold leg break accident for the Sequoyah UHI plant had been analyzed at Sandia for a different NRC project; the analysis began on the TRAC-PD2 code and was completed with the TRAC-PF1 code, using a detailed fine nodalization, particularly in the 3-D vessel.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5348377
• Report Number(s): NUREG/CR-3329-Vol.2; ON: DE84004284
• Country of Publication: United States
• Language: English

Related Subjects

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Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LOSS OF COOLANT
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