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Testing of Zircaloy-2-clad uranium seven-rod fuel elements. Final report [electronic resource].

Published
Washington, D.C. : United States. Dept. of Energy, 1960.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
27 pages : digital, PDF file
Additional Creators
General Electric Company, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
In 1955 the Fuels Development Operation began irradiation testing of fuel elements in high temperature water. It was assumed that if a new reactor were built at Hanford, it would be cooled by high-temperature, pressurized water. Corrosion tests showed that aluminum-clad production fuel elements could not be used in high-temperature water. Therefore, while work to improve the resistance of aluminum to high-temperature water proceeded, the Fuel Design Operation began irradiation of stainless steel- and Zircaloy-2-clad fuel elements. During 1956 and 1957, stainless steel-clad elements were tested in the Materials Testing Reactor (MTR), Hanford H Reactor Loop, and the KE Reactor Recirculating (KER) Loops. During 1957, a coextrusion method for cladding uranium rods with Zircaloy-2 was developed. The first irradiation of Zircaloy-2-clad fuel from an off-site supplier began in late 1958. The objective of the irradiation was to study the dimensional stability of the fuel rods and a seven-rod fuel assembly. Two coextruded, seven-rod elements were irradiated in KER Loop l.
Report Numbers
E 1.99:hw--66267
hw--66267
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
07/05/1960.
"hw--66267"
"DE94011991"
Geering, G.T.
Type of Report and Period Covered Note
Topical; 07/01/1960 - 07/01/1960
Funding Information
AC06-76RL01830
View MARC record | catkey: 14372962