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 crack growth rate studies in a pressurized water reactor environment, (b) irradiation and postirradiation (annealing) heat treatment study of the toughness of pressure vessel steels having a low upper shelf level; and (c) J integral characterization of an A302B steel having a low upper shelf energy. (Author)

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Document Details

Document Type
Technical Report
Publication Date
May 01, 1978
Accession Number
ADA058588

Entities

People

  • Frank J. Loss

Organizations

  • United States Naval Research Laboratory

Tags

Communities of Interest

  • Air Platforms
  • Energy and Power Technologies
  • Ground and Sea Platforms

DTIC Thesaurus Topics

  • Annealing
  • Chemistry
  • Crack Propagation
  • Ductility
  • Fracture (Mechanics)
  • Geometry
  • Heat Treatment
  • J Integrals
  • Materials
  • Measurement
  • Mechanical Properties
  • Mechanics
  • Pressure Vessels
  • Structural Integrity
  • Transition Temperature
  • Transitions
  • Waveforms

Readers

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