Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels: An International StudyASTM International, 1983 - 220 pages |
Contents
Introduction | 2 |
NRC Safety Research Priorities for Reactor Vessel Embrittlement Annealing and Surveillance Dosimetry | 5 |
West German Research Programs on Irradiation Effects on Reactor Pressure Vessels | 16 |
A Review of Activities in France | 29 |
Determination of Neutron Damage Parameters for Irradiation Embrittlement | 55 |
Effect of Irradiation on ElasticPlastic Toughness of Pressure Vessel Steels | 64 |
Specific Problems of Reactor Pressure Vessels Related to Irradiation Effects | 86 |
Status of Knowledge of Radiation Embrittlement in U S Reactor Pressure Vessel Steels | 100 |
Survey of Utility Experience with Reactor Vessel Surveillance | 133 |
Thermal Aging Capsule Results from Oconee Nuclear StationUnit 1 | 146 |
Assessing SteadyState Neutron Exposure Effects Through Analyses of Reactor Vessel Surveillance Data | 155 |
Selection of Specimen Types for Irradiation Surveillance Programs | 166 |
A Fracture Energy Criterion for Irradiation Research and Surveillance | 174 |
Problems in the Evaluation of Reactor Vessel Surveillance Capsules | 186 |
A Service Laboratorys View of the Status and Direction of Reactor Vessel Surveillance | 194 |
Summary | 206 |
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Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels ... Lendell E. Steele No preview available - 1983 |
Common terms and phrases
ADJUSTMENT OF REFERENCE annealing ASPEF ASTM International ASTM International www.astm.org behavior Charpy V-notch Charpy-V copper content correlation crack growth dosimetry ductility Embrittlement and Surveillance evaluation exposure fatigue crack fluence flux fracture mechanics fracture toughness heat treatment high-copper IAEA irradiated 290 irradiated materials irradiation embrittlement kJ/m² Laboratory linear elastic load measured method n/cm² neutron irradiation nickel notch Nuclear Reactor Nuclear Reactor Pressure Nuclear Regulatory Commission plant plate positron precracked predicted pressure vessel steels Pressure Vessel Surveillance pressurized thermal shock pressurized water reactors properties radiation damage radiation embrittlement Reactor Pressure Vessels Reactor Vessel Materials REACTOR VESSEL SURVEILLANCE REFERENCE TEMPERATURE Regulatory Guide 1.99 saturation Society for Testing studies submerged arc welds surveillance capsule tearing modulus tension specimens TEST TEMPERATURE Testing and Materials thermal aging thermal shock trend curves unirradiated upper shelf energy values vessel surveillance programs vessel wall water reactors weld metal Westinghouse Yanichko