Irradiation Effects on Reactor Structural Materials 1 August 1974 - 31 January 1975.

Abstract

This report, covering research for the period, 1 August 1974 - 31 January 1975 includes: (1) the effect of hold time on fatigue crack propagation in neutron irradiated 20% cold worked Type 316 stainless steel; (2) high fluence assessments of 0.03% copper plate from 30-ton A533-B demonstration melt; (3) examination of microstructures of Inconel 718, Incoloy 800, PH13-8Mo, Mo and Nb after irradiation in EBR-II; (4) fluence dependence of ion damage in nickel; (5) ionsimulated irradiation-induced creep of reactor structural alloys; and (6) notch ductility and strength of Type 316 stainles steel submerged arc weld deposits.

Document Details

Document Type
Technical Report
Publication Date
Feb 01, 1975
Accession Number
ADA010510

Entities

People

  • Lendell E. Steele

Organizations

  • United States Naval Research Laboratory

Tags

DTIC Thesaurus Topics

  • Alloys
  • Arc Welds
  • Coverings
  • Crack Propagation
  • Cracks
  • Demonstrations
  • Ductility
  • Materials
  • Microstructure
  • Physical Properties
  • Stainless Steel
  • Steel
  • Welds

Fields of Study

  • Materials science

Readers

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