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Liquid Metal Loops Irradiated on the ORNL Graphite Reactor and the LITR

Description: From abstract: Liquid alkali metals were circulated in a series of structural alloy loops under reactor radiation at high temperature. The first of these loops was a lithium-stainless steel (type 316) system, and the remainder were sodium-Inconel. No effect of radiation other than radioactivation was found. Mass transfer and metallurgical processes attributable to the operating temperatures were observed."
Date: June 1, 1959
Creator: Parkinson, W. W. & Sisman, O.
Partner: UNT Libraries Government Documents Department
open access

The High-Temperature Irradiation Behavior of Hypostoichiometric Uranium Monocarbide

Description: From abstract: A series of three multi-compartmented experiments was designed to investigate the irradiation behavior uranium carbide fuels, as a function of composition, temperature, and burn-up; and the mechanical properties of Type 304 stainless steel, as a function of temperature and integrated thermal neutron flux.
Date: August 31, 1965
Creator: Hahn, R. D.
Partner: UNT Libraries Government Documents Department
open access

Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5: Experimental Data, Final Report

Description: The objective of this program was to provide a mechanical-property database that could be used to predict the performance of Zircaloy cladding under various off-normal, transient, and accident conditions in a power reactor.
Date: May 1981
Creator: Lowry, L. M.; Markworth, A. J.; Perrin, J. S. & Landow, M. P.
Partner: UNT Libraries Government Documents Department
open access

Some Effects of Irradiation on Metals

Description: Report discussing several experiments investigating the effect of radiation on metals, specifically on intermetallic diffusion, mechanical properties of 347 stainless steel and electric resistance of 347 stainless steel.
Date: 1952-03-17?
Creator: Parkins, W. E.
Partner: UNT Libraries Government Documents Department
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