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Title: Results of the four PBF (Power Burst Facility) severe fuel damage tests

Abstract

Four in-pile severe fuel damage tests have been conducted in the Power Burst Facility as part of the United States Nuclear Regulatory Commission's (USNRC) Severe Accident and Source Term Research Program. The tests included 1-m long bundles of PWR fuel pins and simulated the thermal-hydraulic and fuel damage conditions of severe core damage accident. Tests were run with both low and high burnup fuel, low and high coolant flow and with slow and rapid cooldown. One test included Ag-In-Cd control rods. The various types of fuel damage that occurred in the four tests are presented and the measured hydrogen generation, fission product release, and aerosol behavior are described. The principal benefits of the test program have been to improve the USNRC's severe accident analysis capability. Some of the computer models affected by the test results are discussed in the paper.

Authors:
Publication Date:
Research Org.:
EG and G Idaho, Inc., Idaho Falls (USA)
OSTI Identifier:
5457185
Report Number(s):
EGG-M-21987; CONF-8710111-35
ON: DE88006792; TRN: 88-013111
DOE Contract Number:  
AC07-76ID01570
Resource Type:
Conference
Resource Relation:
Conference: 15. water reactor safety information meeting, Gaithersburg, MD, USA, 26 Oct 1987; Other Information: Portions of this document are illegible in microfiche products
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FUEL ELEMENTS; DAMAGE; PWR TYPE REACTORS; REACTOR CORE DISRUPTION; REACTOR SAFETY; AEROSOLS; BURNUP; CADMIUM; CONTROL ELEMENTS; CORIUM; DEPOSITS; FISSION PRODUCT RELEASE; HEAT TRANSFER; HYDRAULICS; HYDROGEN; INDIUM; IODINE; PBF REACTOR; REACTOR COOLING SYSTEMS; RESEARCH PROGRAMS; SILVER; SOURCE TERMS; ACCIDENTS; COLLOIDS; COOLING SYSTEMS; DISPERSIONS; ELEMENTS; ENERGY SYSTEMS; ENERGY TRANSFER; FLUID MECHANICS; HALOGENS; MECHANICS; METALS; NONMETALS; PULSED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SOLS; TANK TYPE REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled; 220600 - Nuclear Reactor Technology- Research, Test & Experimental Reactors

Citation Formats

Osetek, D.J. Results of the four PBF (Power Burst Facility) severe fuel damage tests. United States: N. p., 1987. Web.
Osetek, D.J. Results of the four PBF (Power Burst Facility) severe fuel damage tests. United States.
Osetek, D.J. Thu . "Results of the four PBF (Power Burst Facility) severe fuel damage tests". United States.
@article{osti_5457185,
title = {Results of the four PBF (Power Burst Facility) severe fuel damage tests},
author = {Osetek, D.J.},
abstractNote = {Four in-pile severe fuel damage tests have been conducted in the Power Burst Facility as part of the United States Nuclear Regulatory Commission's (USNRC) Severe Accident and Source Term Research Program. The tests included 1-m long bundles of PWR fuel pins and simulated the thermal-hydraulic and fuel damage conditions of severe core damage accident. Tests were run with both low and high burnup fuel, low and high coolant flow and with slow and rapid cooldown. One test included Ag-In-Cd control rods. The various types of fuel damage that occurred in the four tests are presented and the measured hydrogen generation, fission product release, and aerosol behavior are described. The principal benefits of the test program have been to improve the USNRC's severe accident analysis capability. Some of the computer models affected by the test results are discussed in the paper.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1987},
month = {1}
}

Conference:
Other availability
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