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) Radiation embrittlement resistance of A533-B Class 1 steel plate as a function of extra low copper impurity content (b) Influence of phosphorus and copper content on post-irradiation upper shelf toughness and postirradiation toughness recovery for A533-B steel plate and weld metal (c) Investigations of warm prestress and plastic net ligament phenomena as a means to mitigate crack extension in a vessel during a loss of coolant accident (d) Evaluation of critical factors in crack growth rate studies in a pressurized water reactor environment. (Author)

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Document Details

Document Type
Technical Report
Publication Date
May 01, 1977
Accession Number
ADA042219

Entities

People

  • Frank J. Loss

Organizations

  • United States Naval Research Laboratory

Tags

Communities of Interest

  • Ground and Sea Platforms

DTIC Thesaurus Topics

  • Accidents
  • Annealing
  • Crack Propagation
  • Crack Tips
  • Heat Treatment
  • Materials
  • Measurement
  • Pressure Vessels
  • Radiation Resistance
  • Resistance
  • Simulations
  • Symbols
  • Test And Evaluation
  • Thermal Shock
  • Transition Temperature
  • Transitions
  • Waveforms

Readers

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