Irradiation Effects on Reactor Structural Materials.

Abstract

The research program of the NRL Metallurgy Division, Reactor Materials Branch, involves a broad study of the effects of nuclear radiation upon materials. The report covering research for the period 1 February - 30 April 1973, includes: The effect of hold time on fatigue crack propagation in 20% cold worked stainless steel; the effect of implanted helium on fatigue behavior of TZM alloy; radiation enhanced metastability in a high strength structural alloy, The AEC-CE-NRL Cooperative program on A533-B reactor vessel steel; The transition temperature increase for the SM-1A pressure vessel at reactor shutdown; J-integral characterization of the SM-1A reactor pressure vessel steels; The effect of water vapor on the fatigue strength of irradiated Type 348 stainless steel; The effect of beam scanning on void formation in nickel-ion bombarded nickel. (Modified author abstract)

Document Details

Document Type
Technical Report
Publication Date
May 15, 1973
Accession Number
AD0763658

Entities

People

  • Lendell E. Steele

Organizations

  • United States Naval Research Laboratory

Tags

Communities of Interest

  • Ground and Sea Platforms

DTIC Thesaurus Topics

  • Alloys
  • Chemistry
  • Crack Propagation
  • J Integrals
  • Materials
  • Materials Science
  • Metallurgy
  • Nuclear Radiation
  • Pressure Vessels
  • Radiation
  • Reactor Materials
  • Reactor Shutdown
  • Stainless Steel
  • Steel
  • Transition Temperature
  • Water Vapor

Readers

  • Metallurgy
  • Nuclear and Radiation Engineering.
  • Technical Research and Report Writing.