Actions for IN REACTOR PERFORMANCE OF DEFECTED ZIRCALOY-CLAD U3Si FUEL ELEMENTS IN PRESSURIZED AND BOILING WATER COOLANTS

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IN REACTOR PERFORMANCE OF DEFECTED ZIRCALOY-CLAD U3Si FUEL ELEMENTS IN PRESSURIZED AND BOILING WATER COOLANTS

Author
Feraday, M. A.
Published
Canada : [publisher not identified], 1968.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1968.
Physical Description
microfiche : negative ; 11 x 15 cm
Additional Creators
Allison, G M, Ambler, J. F. R, Chalder, G H, and Lipsett, J. J

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Summary
The results of two in-reactor defect tests of Zircaloy-clad U{sub 3}Si are reported. In the first test, a previously irradiated element (~5300 MWd/tonne U) was defected then exposed to first pressurized water then boiling water at ~270 degC. In the second test, an unirradiated element containing a central void was defected, water-logged, then exposed to pressurized water for 50 minutes. Both tests were terminated because of high activity in the loop coolant detected by both gamma and delayed neutron monitors. Post-irradiation examination showed that both elements had suffered major sheath failures which were attributed to the volume increase accompanying the formation of large quantities of corrosion product formed by the reaction of water with the hot central part of the fuel. It was concluded that the corrosion resistance of U{sub 3}Si at 300 degC is not seriously affected by irradiation, but the corrosion rate increases rapidly with temperature.
Report Numbers
AECL-3106; EXP-NRX-61607
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
OSTI Identifier 4482407
NSA number: NSA-22-047038
Research organization: Atomic Energy of Canada Ltd., Chalk River (Ontario) Canada. Chalk River Nuclear Labs., Fuel Materials Branch.
View MARC record | catkey: 37110363