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) postirradiation fracture toughness of IAEA coordinated program steels, (b) Charpy V-notch ductility trends of submerged arc weld deposit with cyclic postirradiation annealing and reirradiation treatments, (c) J-R curve characterization of irradiated submerged arc weld deposits, and (d) evaluation of critical factors in cyclic crack growth rate studies in a pressurized water reactor environment. (Author)

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Document Details

Document Type
Technical Report
Publication Date
Sep 28, 1979
Accession Number
ADA075349

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 Welds
  • Crack Propagation
  • Crack Tips
  • Electron Microscopes
  • Electron Microscopy
  • Failure Mode And Effect Analysis
  • Fracture (Mechanics)
  • Heat Treatment
  • High Temperature
  • Low Temperature
  • Materials
  • Measurement
  • Mechanics
  • Pressure Vessels
  • Radiation
  • Test And Evaluation
  • X Rays

Readers

  • Combustion and Flow Dynamics.
  • Materials Science (Mechanical Engineering).
  • Nuclear and Radiation Engineering.