IRRADIATION EFFECTS ON REACTOR STRUCTURAL MATERIALS.

Abstract

The report covers research for the period 1 November 1969-31 January 1970, includes: (1) demonstration of improved radiation embrittlement resistance in commercial scale melt of Type A533-B pressure vessel steel, (2) an outline of the effects of fast reactor environment on selected structural and cladding alloys, (3) correlation of dynamic tear, Charpy-V, and drop-weight results from irradiation in a power reactor, (4) neutron exposure of Army SM-1 reactor vessel and related embrittlement projections, (5) initial results of examining radiation sensitive steels by transmission electron microscopy, and (6) description of a newly developed automated system for fatigue crack propagation studies on irradiated metals. (Author)

Document Details

Document Type
Technical Report
Publication Date
Sep 15, 1970
Accession Number
AD0703617

Entities

People

  • C. Z. Serpan Jr.
  • F. A. Smidt Jr.
  • Henry E. Watson
  • J. Russell Hawthorne
  • Lendell E. Steele

Organizations

  • United States Naval Research Laboratory

Tags

Communities of Interest

  • Ground and Sea Platforms

DTIC Thesaurus Topics

  • Control Systems
  • Crack Propagation
  • Electron Microscopy
  • Embrittlement
  • Fast Reactors
  • Materials
  • Microscopy
  • Nuclear Energy
  • Pressure Vessels
  • Radiation
  • Transmission Electron Microscopy

Readers

  • Materials Science (Mechanical Engineering).
  • Nuclear and Radiation Engineering.
  • Technical Research and Report Writing.

Technology Areas

  • Microelectronics