Resource Type

Serial/Series Title

A Capsule Design for Experimental High-Flux Irradiations Of Fuel Materials (open access)

A Capsule Design for Experimental High-Flux Irradiations Of Fuel Materials

New reactors presently in design or construction stages, as well as revised operating procedures for existing reactors, have shown an increasing emphasis on extending the exposure time of the reactor fuel elements. However, operating experience at Hanford, as at other installations, has demonstrated that as the amount of burn-up in uranium metal is increased an increase is also noted in operational difficulties resulting from the dimensional behavior of the fuel. During reactor irradiation uranium slugs or rods have been observed to change in length and diameter, to warp, and to develop surface roughening.
Date: October 6, 1952
Creator: Kittel, J. Howard & Tedeschi, P.
System: The UNT Digital Library
The Isolation and Purification of Neptunium-237 Obtained From Hanford Wastes (open access)

The Isolation and Purification of Neptunium-237 Obtained From Hanford Wastes

Through the efforts of the Hanford Engineer Works a quantity of neptunium-237 was separated from uranium waste solutions by a modification of the standard plutonium precipitation process, This material, as concentrates, was shipped to Argonne for final isolation and purification of the neptunium.
Date: May 6, 1953
Creator: Hindman, J. C.; Wehner, Philip, 1917-; Sullivan, J. C. & Cohen, Donald
System: The UNT Digital Library