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

Title: Relocation and freezing of liquefied fuel-rod material. [PWR]

Abstract

Severe degraded core cooling accidents, such as occurred at TMI-2 can potentially reach temperatures in excess of cladding melting. When the molten cladding is in contact with UO/sub 2/ fuel, the UO/sub 2/ will be dissolved contributing significantly to the total amount of liquefied material flowing down the rod and eventually freezing in a lower, cooler region of the core. The primary objectives of this paper are to evaluate the relocation and freezing characteristics of liquefied fuel rod material over a wide range of system conditions, physical characteristics of the fuel rod and liquefied material, and material thermo-physical properties to determine the relative influence of the controlling parameters. First the analytical model used in the analysis is briefly reviewed. The results of the analyses are then presented and discussed, and this is followed by the conclusions.

Authors:
;
Publication Date:
Research Org.:
EG and G Idaho, Inc., Idaho Falls (USA)
OSTI Identifier:
7094067
Report Number(s):
EGG-M-04982; CONF-820717-4
ON: DE83000557
DOE Contract Number:  
AC07-76ID01570
Resource Type:
Conference
Resource Relation:
Conference: PAHR information exchange conference, Karlsruhe, F.R. Germany, 28 Jul 1982; Other Information: Portions of document are illegible
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; MELTDOWN; HEAT TRANSFER; HYDRAULICS; PWR TYPE REACTORS; CORIUM; LIQUID FLOW; REACTOR SAFETY; SOLIDIFICATION; URANIUM DIOXIDE; ZIRCONIUM OXIDES; ACCIDENTS; ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; MECHANICS; OXIDES; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTORS; SAFETY; TRANSITION ELEMENT COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM COMPOUNDS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Moore, R L, and Broughton, J M. Relocation and freezing of liquefied fuel-rod material. [PWR]. United States: N. p., 1982. Web.
Moore, R L, & Broughton, J M. Relocation and freezing of liquefied fuel-rod material. [PWR]. United States.
Moore, R L, and Broughton, J M. 1982. "Relocation and freezing of liquefied fuel-rod material. [PWR]". United States.
@article{osti_7094067,
title = {Relocation and freezing of liquefied fuel-rod material. [PWR]},
author = {Moore, R L and Broughton, J M},
abstractNote = {Severe degraded core cooling accidents, such as occurred at TMI-2 can potentially reach temperatures in excess of cladding melting. When the molten cladding is in contact with UO/sub 2/ fuel, the UO/sub 2/ will be dissolved contributing significantly to the total amount of liquefied material flowing down the rod and eventually freezing in a lower, cooler region of the core. The primary objectives of this paper are to evaluate the relocation and freezing characteristics of liquefied fuel rod material over a wide range of system conditions, physical characteristics of the fuel rod and liquefied material, and material thermo-physical properties to determine the relative influence of the controlling parameters. First the analytical model used in the analysis is briefly reviewed. The results of the analyses are then presented and discussed, and this is followed by the conclusions.},
doi = {},
url = {https://www.osti.gov/biblio/7094067}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jan 01 00:00:00 EST 1982},
month = {Fri Jan 01 00:00:00 EST 1982}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share: