Production Test IP-653-D: Irradiation service request HAPO 300, irradiation of a tungsten matrix UO{sub 2} cermet plate in the KW snout facility

Technical Report · Mon Jan 20 00:00:00 EST 1964

DOI:https://doi.org/10.2172/10161554· OSTI ID:10161554

Cox, J H

Cemets are attractive as fuel for nuclear reactors because of their relatively high thermal conductivity and their apparent ability to withstand very high temperatures for prolonged periods of time. A number of cermet fuel specimens have been successfully irradiated at temperatures greater than 2000 C for periods of up to six weeks. Two cermet fuel plates described herein have successfully operated, in the snout facility, at {approximately}3000 C for four hours each. This continuation of the program for twelve more capsules is to investigate the diffusion characteristics of UO{sub 2} and fission products from the tungsten matrix and to study the dimensional stability of the system. The in-reactor test described in this report and in conjunction with extensive out-of-reactor studies will provide a firm basis for building cermet fuel technology.

• Research Organization: General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10161554
• Report Number(s): HW-80409; ON: DE94014205
• Resource Relation: Other Information: DN: Declassified; PBD: 20 Jan 1964
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
HANFORD PRODUCTION REACTORS
NUCLEAR FUELS
FUEL PLATES
IRRADIATION
CERMETS
IRRADIATION CAPSULES
TESTING
TUNGSTEN
URANIUM DIOXIDE
THERMAL CONDUCTIVITY
050700
220600
FUELS PRODUCTION AND PROPERTIES
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS