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open access

VBWR Stability Test Report

Description: Analysis of the stability of boiling water reactors.
Date: June 1963
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department
open access

Fast Ceramic Reactor Development Program: Experimental Studies of Sodium Logging in Fast Ceramic Reactor Fuels

Description: From abstract: "The experimental determination of the effects of sodium ingress on high-performance oxide fuels is described. Capsule design, fabrication, irradiation, examination, and analysis are described in detail."
Date: September 1963
Creator: O'Neill, G. L.; Novak, P. E.; Johnson, M. L. & Baily, W. E.
Partner: UNT Libraries Government Documents Department
open access

Materials for Superheated Fuel Sheaths: Relative Performance of Alloys in Superheated Steam Environments

Description: From abstract: "Study of radiation effects upon the tensile properties of the alloys, corrosion behavior in the absence and presence of stress, effect of prolonged, high temperature exposures upon structure sensitive properties of the alloys, and physical metallurgical changes as a function of exposure in a superheat environment.
Date: July 1963
Creator: Comprelli, F. A.; MacMillan, D. F. & Spalaris, C. N.
Partner: UNT Libraries Government Documents Department
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