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Testing of Zircaloy-2-Clad Uranium Seven-Rod Fuel Elements. Final Report

Description: 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 stee… more
Date: July 5, 1960
Creator: Geering, G. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Irradiation testing of tubular fuel elements: PT-IP 292A. Final report

Description: This report discusses Zircaloy-2 clad uranium and uranium-2 weight percent zirconium fuel tubes which were irradiated to 3200 MWD/T in a high temperature water cooled loop. The outer clad of one tube split due to swelling of the uranium. Postirradiation examination of the fuel cores included metallography, electron microscopy, density determinations, dimensional measurements, and radiochemical burn-up analysis.
Date: April 1, 1961
Creator: Geering, G. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Proposal for charging GEH-10-43 NINI interim measurement test in the ETR

Description: The objective of this test is to irradiate an NPR fuel element inner tube in the ETR 3 {times} 3 Loop. the NPR fuel element is a tube in tube type. Both tubes are Zircaloy-2 clad uranium metal. The inner tube is identified by the Hanford designation NINI. In GEH-10-43 we plan to measure an NINI tube after each cycle for four cycles. An NPR inner tube with slightly larger diameter has been run in the ETR Hanford 3 {times} 3 Loop. Two NINI elements are now running in the 3 {times} 3 Loop.
Date: April 7, 1961
Creator: Geering, G. T. & Heck, E. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Interim report: Some temperature and swelling data on Zircaloy-2 clad coextruded fuel elements

Description: This report provides some temperature and swelling data on Zircaloy-2 clad, coextruded fuel elements irradiated in the KER loops and in the GEH-3 {times} 3P7 loop at the ETR. Data on both rod cluster fuel elements and tubular fuel elements are included. Density changes, where density measurements were made, have also been included. These data are preliminary and are subject to change.
Date: January 25, 1961
Creator: Call, R. L. & Geering, G. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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