Prediction of the semiscale blowdown heat transfer test S-02-8 (NRC Standard Problem Five). [PWR]
Standard Problem Five was the prediction of test S-02-8 in the Semiscale Mod-1 experimental program. The Semiscale System is an electrically heated experiment designed to produce data on system performance typical of PWR thermal-hydraulic behavior. The RELAP4 program used for these analyses is a digital computer program developed to predict the thermal-hydraulic behavior of experimental systems and water-cooled nuclear reactors subjected to postulated transients. The RELAP4 predictions of Standard Problem 5 were in good overall agreement with the measured hydraulic data. Fortunately, sufficient experience has been gained with the semiscale break configuration and the critical flow models in RELAP4 to accurately predict the break flow and, hence the overall system depressurization. Generally, the hydraulic predictions are quite good in regions where homogeneity existed. Where separation effects occurred, predictions are not as good, and the data oscillations and error bands are larger. A large discrepancy existed among the measured heater rod temperature data as well as between these data and predicted values. Several potential causes for these differences were considered, and several post test analyses were performed in order to evaluate the discrepancies.
- Research Organization:
- Energy, Inc., Idaho Falls, ID (USA)
- OSTI ID:
- 7132149
- Report Number(s):
- EPRI-NP-212; TRN: 77-004311
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BLOWDOWN
HEAT TRANSFER
PWR TYPE REACTORS
COMPUTER CALCULATIONS
LOSS OF COOLANT
MOCKUP
REACTOR SAFETY
SIMULATION
ACCIDENTS
ENERGY TRANSFER
REACTOR ACCIDENTS
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WATER COOLED REACTORS
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220900* - Nuclear Reactor Technology- Reactor Safety
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Nonbreeding
Light-Water Moderated
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