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: evaluation of critical factors in crack growth rate studies in a pressurized water reactor environment; irradiation and postirradiation (annealing) heat treatment study of the toughness of pressure vessel steels having a low upper shelf level; exploratory investigation of notch ductility changes in A508-2 forgings; compositional variables affecting upper shelf toughness; and investigation of warm prestress phenomenon as a means to limit crack extension in a vessel during a loss-of-coolant accident. (Author)

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Document Details

Document Type
Technical Report
Publication Date
Jan 01, 1978
Accession Number
ADA052553

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

  • Crack Propagation
  • Crack Tips
  • Elements
  • Energy Levels
  • Heat Treatment
  • Materials
  • Measurement
  • Mechanics
  • Military Research
  • Pressure Vessels
  • Pressurized Water Reactors
  • Statistical Analysis
  • Stresses
  • Structural Integrity
  • Thermal Shock
  • Transition Temperature
  • Yield Strength

Readers

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