skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Prediction of the semiscale blowdown heat transfer test S-02-8 (NRC Standard Problem Five). [PWR]

Abstract

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.

Authors:
; ; ; ;
Publication Date:
Research Org.:
Energy, Inc., Idaho Falls, ID (USA)
OSTI Identifier:
7132149
Report Number(s):
EPRI-NP-212
TRN: 77-004311
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 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; REACTORS; SAFETY; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Fujita, N., Irani, A. A., Mecham, D. C., Sawtelle, G. R., and Moore, K. V. Prediction of the semiscale blowdown heat transfer test S-02-8 (NRC Standard Problem Five). [PWR]. United States: N. p., 1976. Web. doi:10.2172/7132149.
Fujita, N., Irani, A. A., Mecham, D. C., Sawtelle, G. R., & Moore, K. V. Prediction of the semiscale blowdown heat transfer test S-02-8 (NRC Standard Problem Five). [PWR]. United States. https://doi.org/10.2172/7132149
Fujita, N., Irani, A. A., Mecham, D. C., Sawtelle, G. R., and Moore, K. V. 1976. "Prediction of the semiscale blowdown heat transfer test S-02-8 (NRC Standard Problem Five). [PWR]". United States. https://doi.org/10.2172/7132149. https://www.osti.gov/servlets/purl/7132149.
@article{osti_7132149,
title = {Prediction of the semiscale blowdown heat transfer test S-02-8 (NRC Standard Problem Five). [PWR]},
author = {Fujita, N. and Irani, A. A. and Mecham, D. C. and Sawtelle, G. R. and Moore, K. V.},
abstractNote = {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.},
doi = {10.2172/7132149},
url = {https://www.osti.gov/biblio/7132149}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Oct 01 00:00:00 EDT 1976},
month = {Fri Oct 01 00:00:00 EDT 1976}
}