IRRADIATION EFFECTS ON REACTOR STRUCTURAL MATERIALS.

Abstract

The research program of the NRL Metallurgy Division, Reactor Materials Branch, is devoted to the determination of the effects of nuclear radiation upon the properties of structural materials. The overall program is sponsored by the Office of Naval Research, the Naval Ship Systems Command, the U. S. Atomic Energy Commission, and the Army Nuclear Power Program. Since research findings which apply to the objectives of one sponsoring agency are also of interest to the others, the overall program progress is reported herein. This report, covering research for the period 1 August - 31 October 1966, includes the following: (1) a comparative response of A302-B and several higher strength steels after irradiation at 200F and at 550F, (2) a comparative evaluation of the notch ductility of 3-1/2%Ni-Cr-Mo weld and base plate after irradiation at 200F and at 550F, (3) the notch ductility characteristics of irradiated AISI 304L and 347 stainless steels after exposure to 1 and 10 x 10 to the 19th power, (4) the response of A350-LF1 (Modified) steel to cyclic irradiation and annealing treatment, and (5) the through-thickness embrittlement and neutron flux variations in a simulated wall of a reactor pressure vessel. (Author)

Document Details

Document Type
Technical Report
Publication Date
Nov 15, 1966
Accession Number
AD0646662

Entities

People

  • C. Z. Serpan
  • J. Russell Hawthorne
  • Lendell E. Steele
  • R. A. Gray

Organizations

  • United States Naval Research Laboratory

Tags

Communities of Interest

  • Energy and Power Technologies

DTIC Thesaurus Topics

  • Chemistry
  • Ductility
  • Materials
  • Materials Science
  • Metallurgy
  • Military Research
  • Neutron Flux
  • Nuclear Energy
  • Nuclear Radiation
  • Pressure Vessels
  • Radiation
  • Reactor Materials
  • Stainless Steel
  • Steel

Readers

  • Materials Science and Engineering.
  • Metallurgy
  • Technical Research and Report Writing.