Irradiation Effects on Reactor Structural Materials.

Abstract

The report, covering research for the period 1 August - 31 October 1970, includes: (1) initial radiation damage surveillance results for the MH-1A reactor vessel, (2) development of a reference fluence decrease through a reactor vessel wall, (3) analysis of the fluence gradient in terms in terms of fracture behavior, including fracture extension resistance for the through-wall vessel properties, (4) correlation of Charpy-V and dynamic tear test results for reactor steels after irradiation, (5) true stress-natural strain determinations for several high temperature alloys irradiated in the EBR-II reactor, and (6) the nature of dislocation loop growth during annealing of irradiated vanadium. (Author)

Document Details

Document Type
Technical Report
Publication Date
Nov 15, 1970
Accession Number
AD0716405

Entities

People

  • C. Z. Serpan Jr.
  • Frank J. Loss
  • J. Russell Hawthorne
  • Lendell E. Steele
  • P. P. Puzak

Organizations

  • United States Naval Research Laboratory

Tags

Communities of Interest

  • Ground and Sea Platforms

DTIC Thesaurus Topics

  • Alloys
  • Annealing
  • Coverings
  • Dislocations
  • Heat Resistant Alloys
  • High Temperature
  • Isotherms
  • Materials
  • Radiation
  • Resistance
  • Surveillance
  • Temperature Gradients
  • Vanadium

Fields of Study

  • Physics

Readers

  • Materials Science (Mechanical Engineering).
  • Nuclear and Radiation Engineering.