IRRADIATION EFFECTS ON REACTOR STRUCTURAL MATERIALS 1 AUGUST - 31 OCTOBER 1965,

Abstract

The report includes the following: (1) status of reactor radiation damage surveillance programs in several power reactors, (2) the effect of neutron spectra on properties of steels exposed in light water, heavy water, and graphite-moderated reactors, (3) the alleviation of neutron embrittlement of A350-LF1 steel by thermal annealing treatment, and (4) through-thickness Charpy V-notch ductility characteristics of a 4-in. A302-B plate.

Document Details

Document Type
Technical Report
Publication Date
Nov 15, 1965
Accession Number
AD0626466

Entities

People

  • C. Z. Serpan Jr.
  • J. Russell Hawthorne
  • Lendell E. Steele

Organizations

  • United States Naval Research Laboratory

Tags

DTIC Thesaurus Topics

  • Annealing
  • Ductility
  • Embrittlement
  • Graphite Moderated Reactors
  • Graphitic Materials
  • Heavy Water
  • Material Degradation Processes
  • Materials
  • Neutron Spectrum
  • Radiation
  • Spectra
  • Surveillance
  • Thickness
  • Water

Fields of Study

  • Physics

Readers

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