Study of the U/sub 3/O/sub 8/-Al thermite reaction and strength of reactor fuel tubes

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:5421243

Peacock, H B

Research and test reactors are presently operated with aluminum-clad fuel elements containing highly enriched uranium-aluminum alloy cores. To lower the enrichment and still maintain reactivity, the uranium content of the fuel element will need to be higher than currently achievable with alloy fuels. This will necessitate conversion to other forms such as U/sub 3/O/sub 8/-aluminum cermets. Above the aluminum melting point, U/sub 3/O/sub 8/ and aluminum undergo an exothermic thermite reaction and cermet fuel cores tend to keep their original shape. Both factors could affect the course and consequences of a reactor accident, and prompted an investigation of the behavior of cermet fuels at elevated temperatures. Tests were carried out using pellets and extruded tube-sections with 53 wt % U/sub 3/O/sub 8/ in aluminum. This content corresponds to a theoretical uranium density of 1.9 g/cc. Results indicate that the thermite reaction occurs at about 900/sup 0/C in air without a violent effect. The heat of reaction was approximately 123 cal/g of U/sub 3/O/sub 8/-aluminum fuel. Tensile and compressive strength of the fuel tube section is low above 660/sup 0/C. In tension, sections failed at about the aluminum melting point. In compression with 2-psi average axial stress, failure occurred at 917/sup 0/C, while 7 psi average axial stress produced failure at 669/sup 0/C.

• Research Organization: Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
• DOE Contract Number: AC09-76SR00001
• OSTI ID: 5421243
• Report Number(s): DP-MS-83-80; CONF-8310176-8; ON: DE84000959
• Resource Relation: Conference: International meeting on reduced enrichment for research and test reactors, Tokai, Japan, 24 Oct 1983
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
CHEMICAL REACTIONS
RESEARCH AND TEST REACTORS
ALUMINIUM
CERMETS
COMPRESSION STRENGTH
HIGH TEMPERATURE
TENSILE PROPERTIES
TUBES
URANIUM OXIDES U3O8
VERY HIGH TEMPERATURE
ACCIDENTS
ACTINIDE COMPOUNDS
CHALCOGENIDES
COMPOSITE MATERIALS
ELEMENTS
MATERIALS
MECHANICAL PROPERTIES
METALS
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
URANIUM COMPOUNDS
URANIUM OXIDES
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors