Comparison of computer codes (CE-THERM, FRAP-T5, GT3-FLECHT, and TRUMP-FLECHT) with data from the NRU-LOCA thermal hydraulic tests
Abstract
The LOCA Simulation Program in the NRU reactor is the first set of experiments to provide data on the behavior of full-length, nuclear-heated PWR fuel bundles during the heatup, reflood, and quench phases of a loss-of-coolant accident (LOCA). This paper compares the temperature time histories of 4 experimental test cases with 4 computer codes: CE-THERM, FRAP-T5, GT3-FLECHT, and TRUMP-FLECHT. The preliminary comparisons between prediction and experiment show that the state-of-the art fuel codes have large uncertainties and are not necessarily conservative in predicting peak temperatures, turn around times, and bundle quench times.
- Authors:
- Publication Date:
- Research Org.:
- Battelle Pacific Northwest Labs., Richland, WA (USA)
- OSTI Identifier:
- 6204333
- Report Number(s):
- PNL-SA-9328; CONF-810801-56
ON: DE81028136; TRN: 81-015162
- DOE Contract Number:
- AC06-76RL01830
- Resource Type:
- Conference
- Resource Relation:
- Conference: 6. international conference on structural mechanics in reactor technology, Paris, France, 17 Aug 1981
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LOSS OF COOLANT; COMPUTERIZED SIMULATION; PWR TYPE REACTORS; C CODES; COMPARATIVE EVALUATIONS; COMPUTER CODES; F CODES; FUEL ELEMENT CLUSTERS; G CODES; NRU REACTOR; T CODES; ACCIDENTS; FUEL ASSEMBLIES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; NATURAL URANIUM REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
Citation Formats
Mohr, C L, Rausch, W N, and Hesson, G M. Comparison of computer codes (CE-THERM, FRAP-T5, GT3-FLECHT, and TRUMP-FLECHT) with data from the NRU-LOCA thermal hydraulic tests. United States: N. p., 1981.
Web.
Mohr, C L, Rausch, W N, & Hesson, G M. Comparison of computer codes (CE-THERM, FRAP-T5, GT3-FLECHT, and TRUMP-FLECHT) with data from the NRU-LOCA thermal hydraulic tests. United States.
Mohr, C L, Rausch, W N, and Hesson, G M. 1981.
"Comparison of computer codes (CE-THERM, FRAP-T5, GT3-FLECHT, and TRUMP-FLECHT) with data from the NRU-LOCA thermal hydraulic tests". United States.
@article{osti_6204333,
title = {Comparison of computer codes (CE-THERM, FRAP-T5, GT3-FLECHT, and TRUMP-FLECHT) with data from the NRU-LOCA thermal hydraulic tests},
author = {Mohr, C L and Rausch, W N and Hesson, G M},
abstractNote = {The LOCA Simulation Program in the NRU reactor is the first set of experiments to provide data on the behavior of full-length, nuclear-heated PWR fuel bundles during the heatup, reflood, and quench phases of a loss-of-coolant accident (LOCA). This paper compares the temperature time histories of 4 experimental test cases with 4 computer codes: CE-THERM, FRAP-T5, GT3-FLECHT, and TRUMP-FLECHT. The preliminary comparisons between prediction and experiment show that the state-of-the art fuel codes have large uncertainties and are not necessarily conservative in predicting peak temperatures, turn around times, and bundle quench times.},
doi = {},
url = {https://www.osti.gov/biblio/6204333},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Jul 01 00:00:00 EDT 1981},
month = {Wed Jul 01 00:00:00 EDT 1981}
}
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