Search
CSV
RISA Description of a Study for the Thermal Anneal of Neutron-Embrittled Reactor Vessel Materials
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: A number of early light water reactor plants were constructed from materials having low initial Charpy upper shelf values and high copper and phosphorus content. As these elements have been ...
Use of Fracture Mechanics in Reactor Vessel Surveillance
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: This paper presents the basis for utilizing fracture mechanics technology based upon data obtained from small Charpy V-notch specimens incorporated in reactor vessel surveillance programs. Included ...
Fatigue Crack Growth Characteristics of A533 Grade B Class I Plate in an Environment of High-Temperature Primary Grade Nuclear Reactor Water
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Fatigue crack growth rate tests conducted in primary grade reactor coolant at 550°F (288°C) on A533 Grade B Class 1 steel (HSST Plate 02) showed an increase in growth rates at a ...