VBWR Stability Test Report (open access)

VBWR Stability Test Report

Analysis of the stability of boiling water reactors.
Date: June 1963
Creator: U.S. Atomic Energy Commission
System: The UNT Digital Library
Materials for Superheated Fuel Sheaths: Relative Performance of Alloys in Superheated Steam Environments (open access)

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

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.
System: The UNT Digital Library
Analysis of Failure of Type 304 Stainless Steel Clad Swaged Powder Fuel Assembly (open access)

Analysis of Failure of Type 304 Stainless Steel Clad Swaged Powder Fuel Assembly

From introduction: "The purpose of this report is to describe the observations made during the post-irradiation examination of HPD-2S, and to discuss possible modes of failure.
Date: October 3, 1963
Creator: Lees, E. A.
System: The UNT Digital Library
Survey of Piping Failures for the Reactor Primary Coolant Pipe Rupture Study (open access)

Survey of Piping Failures for the Reactor Primary Coolant Pipe Rupture Study

From summary: "An industrial piping failure survey covering 701 contacts in electric utilities, petroleum refineries, chemical processing, marine applications, architect-engineers, component manufacturers, piping fabricating and erectors, insurance companies, and others was conducted as part of the Reactor Primary Coolant Rupture Study."
Date: May 1964
Creator: U.S. Atomic Energy Commission
System: The UNT Digital Library