Structural Integrity of Water Reactor Pressure Boundary Components.
Abstract
This report describes progress in a program to characterize the properties and performance of materials with respect to the structural integrity of light-water reactor pressure boundary components. The work is sponsored primarily by the U.S. Nuclear Regulatory Commission. Studies on dynamic fracture toughness are also being conducted on a cooperative basis by the Electric Power Research Institute (EPRI) and NRL. In addition, the work on dynamic fracture toughness is supported by the Office of Naval Research. This report describes progress in the following areas: (a) fatigue crack propagation in reactor pressure vessel steels in an air environment, (b) dynamic fracture toughness of 1-in. (25-mm) and precracked Charpy-V bend specimens under impact loading, (c) postirradiation notch ductility and properties recovery in reactor vessel steels, (d) factors contributing to variable resistance of structural steels to radiation embrittlement, and (e) the initial program plan to investigate the phenomena of warm prestress and plastic net ligament in support of thermal shock studies. (Author)
Document Details
- Document Type
- Technical Report
- Publication Date
- Aug 26, 1976
- Accession Number
- ADA030114
Entities
People
- Frank J. Loss
Organizations
- United States Naval Research Laboratory