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Title: Prototypic Thermal-Hydraulic Experiment in NRU to Simulate Loss-of-Coolant Accidents

Abstract

Quick-look test results are reported for the initial test series of the Loss-of-Coolant Accident (LOCA) Simulation in the National Research Universal {NRU) test program, conducted by Pacific Northwest Laboratory (PNL) for the U.S. Nuclear Regulatory Commission (NRC). This test was devoted to evaluating the thermal-hydraulic characteristics of a full-length light water reactor (LWR) fuel bundle during the heatup, reflood, and quench phases of a LOCA. Experimental results from 28 tests cover reflood rates of 0.74 in./sec to 11 in./sec and delay times to initiate reflood of 3 sec to 66 sec. The results indicate that current analysis methods can predict peak temperatures within 10% and measured quench times for the bundle were significantly less than predicted. For reflood rates of 1 in./sec where long quench times were predicted (>2000 sec}, measured quench times of 200 sec were found.

Authors:
; ; ; ; ; ; ;
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
Office of Nuclear Regulatory Research
OSTI Identifier:
1080074
Report Number(s):
PNL-3681; NUREG/CR-1882
DOE Contract Number:  
DE-AC06-76RL01830
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS

Citation Formats

Mohr, C. L., Hesson, G. M., Russcher, G. E., Marsh, R. K., King, L. L., Wildung, N. J., Rausch, W. N., and Bennett, W. D. Prototypic Thermal-Hydraulic Experiment in NRU to Simulate Loss-of-Coolant Accidents. United States: N. p., 1981. Web. doi:10.2172/1080074.
Mohr, C. L., Hesson, G. M., Russcher, G. E., Marsh, R. K., King, L. L., Wildung, N. J., Rausch, W. N., & Bennett, W. D. Prototypic Thermal-Hydraulic Experiment in NRU to Simulate Loss-of-Coolant Accidents. United States. doi:10.2172/1080074.
Mohr, C. L., Hesson, G. M., Russcher, G. E., Marsh, R. K., King, L. L., Wildung, N. J., Rausch, W. N., and Bennett, W. D. Wed . "Prototypic Thermal-Hydraulic Experiment in NRU to Simulate Loss-of-Coolant Accidents". United States. doi:10.2172/1080074. https://www.osti.gov/servlets/purl/1080074.
@article{osti_1080074,
title = {Prototypic Thermal-Hydraulic Experiment in NRU to Simulate Loss-of-Coolant Accidents},
author = {Mohr, C. L. and Hesson, G. M. and Russcher, G. E. and Marsh, R. K. and King, L. L. and Wildung, N. J. and Rausch, W. N. and Bennett, W. D.},
abstractNote = {Quick-look test results are reported for the initial test series of the Loss-of-Coolant Accident (LOCA) Simulation in the National Research Universal {NRU) test program, conducted by Pacific Northwest Laboratory (PNL) for the U.S. Nuclear Regulatory Commission (NRC). This test was devoted to evaluating the thermal-hydraulic characteristics of a full-length light water reactor (LWR) fuel bundle during the heatup, reflood, and quench phases of a LOCA. Experimental results from 28 tests cover reflood rates of 0.74 in./sec to 11 in./sec and delay times to initiate reflood of 3 sec to 66 sec. The results indicate that current analysis methods can predict peak temperatures within 10% and measured quench times for the bundle were significantly less than predicted. For reflood rates of 1 in./sec where long quench times were predicted (>2000 sec}, measured quench times of 200 sec were found.},
doi = {10.2172/1080074},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1981},
month = {4}
}