RELAP5 assessment: LOFT intermediate breaks L5-1 and L8-2. [PWR]
Technical Report
·
OSTI ID:5539379
The RELAP5 independent assessment project at Sandia National Laboratories is part of an overall effort funded by the NRC to determine the ability of various systems codes to predict the detailed thermal/hydraulic response of LWRs during accident and off-normal conditions. The RELAP5 code is being assessed at SNLA against test data from various integral and separate effects test facilities. As part of this assessment matrix, an intermediate break transient (L5-1) and a core uncovery transient (L8-2) performed at the LOFT facility have been analyzed. Transient calculations were done with both cycle 14 and cycle 18 of RELAP5/MOD1 and a comparison of the predictions was made. The results show that RELAP5/MOD1 did very well calculating the overall behavior for these intermediate break experiments, although there were a few quantitative disagreements.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5539379
- Report Number(s):
- NUREG/CR-3406; SAND-83-1575; ON: DE84001513
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
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Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
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220900* -- Nuclear Reactor Technology-- Reactor Safety
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COMPUTER CALCULATIONS
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RESEARCH AND TEST REACTORS
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WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FLOW RATE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
NUMERICAL DATA
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS