TRAC-PF1/MOD1 independent assessment: NEPTUNUS pressurizer test Y05. [PWR]
The TRAC independent assessment project at Sandia National Laboratories is part of an overall effort funded by the NRC to determine the capability of various system codes to predict the detailed thermal/hydraulic response of light water reactors during accident and off-normal conditions. The TRAC computer code is being assessed at SNLA against test data from various integral and separate effects test facilities. As part of this assessment effort, a separate effects component test performed in the NEPTUNUS pressurizer test facility, located at the Laboratory for Thermal Power Engineering at Delft University of Technology, was analyzed with TRAC-PF1/MOD1. The test simulated insurges, combined with spray flow, and outsurges from a pressurizer, and was selected for code assessment because the capability of the computer codes used in safety analyses to calculate the correct pressurizer response is an important concern of the NRC. The TRAC-PF1/MOD1 results showed that somewhat higher pressures and fluid temperatures were calculated during insurges with spray flow than were measured in the test. A contributing factor to the calculation of high pressures and fluid temperatures appears to be that the interfacial heat transfer from superheated vapor to subcooled liquid was too low.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5950816
- Report Number(s):
- NUREG/CR-3919; SAND-84-1534; ON: TI85007317
- Country of Publication:
- United States
- Language:
- English
Similar Records
TRAC-PF1/MOD1 developmental assessment
Thermal/hydraulic analysis research program. Quarterly report, April-June 1984. Volume 2 of 4. [PWR]
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Nonbreeding
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FLOW RATE
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