Structural Integrity of Water Reactor Pressure Boundary Components.

Abstract

This report describes research progress in a continuing program to characterize materials properties performance with respect to structural integrity of light water reactor pressure boundary components. Progress for this reporting period is summarized in the following areas: (a) evaluation of critical factors in fatigue crack growth rate studies in a pressurized water reactor environment; (b) fractographic observations of fatigue crack propagation; (c) the IARAR program and its objectives; (d) the effect of submerged arc welding on the notch toughness of low upper shelf A302-B plate exhibiting a low upper shelf and its weld HAZ, and (f) surveys of foreign research related to the safety of light water reactors in Japan, United Kingdom, France, and Germany. (Author)

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Document Details

Document Type
Technical Report
Publication Date
Sep 01, 1977
Accession Number
ADA047398

Entities

People

  • Frank J. Loss

Organizations

  • United States Naval Research Laboratory

Tags

Communities of Interest

  • Energy and Power Technologies
  • Ground and Sea Platforms

DTIC Thesaurus Topics

  • Arc Welding
  • Chemistry
  • Crack Propagation
  • Electron Microscopes
  • Electron Microscopy
  • Frequency
  • Heat Treatment
  • Light Water Reactors
  • Materials
  • Measurement
  • Microscopy
  • Notch Toughness
  • Pressure Vessels
  • Radiation
  • Scanning Electron Microscopy
  • Submerged Arc Welding
  • Transition Temperature

Readers

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