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 Aug-31 October 1972, includes: J-integral characterization of irradiated 304 stainless steel; Studies of fatigue crack propagation in neutron irradiated stainless steel weldments; Exploratory assessments of A508 forging radiation resistance; A parametric study of the vacancy trapping during irradiation; Surveillance results for the MH-1A reactor pressure vessel.

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Document Details

Document Type
Technical Report
Publication Date
Nov 15, 1972
Accession Number
AD0753457

Entities

People

  • Lendell E. Steele

Organizations

  • United States Naval Research Laboratory

Tags

Communities of Interest

  • Energy and Power Technologies
  • Ground and Sea Platforms

DTIC Thesaurus Topics

  • Base Metal
  • Crack Propagation
  • Engineering
  • Fast Reactors
  • Heat Treatment
  • J Integrals
  • Materials
  • Mechanical Working
  • Mechanics
  • Neutron Flux
  • Nuclear Energy
  • Nuclear Radiation
  • Nuclear Reactors
  • Pressure Vessels
  • Reactor Materials
  • Stainless Steel
  • Tensile Strength

Fields of Study

  • Physics

Readers

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