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}
}