STP 1366, the nineteenth volume in this series, examines 90 peer-reviewed papers from the international nuclear community, with the emphasis on advanced materials such as silicon carbide and vanadium alloys. A majority of the papers are devoted to pressure vessel embrittlement and its mitigation. Smaller segments address the issues of light water reactors, fusion reactors, and to a lesser extent, breeder reactors.
Several emerging issues are also explored, including reduced activation, welding of irradiated materials and damage resulting form high-energy proton beams in accelerator-driven nuclear systems.
Divided into the following sections:
Pressure Vessel Steels--Mechanical Properties
Pressure Vessel Welds--Mechanical Properties
Pressure Vessel Steels--Segregation and Microstructure
Ferritic and Ferritic/Martensitic Steels--Annealing and Reirradiation Behavior
Irradiation-Induced Behavior Of Iron, Model Alloys, and Ferritic/Martensitic Alloys
Low Activation Ferritic/Martensitic Alloys
Irradiation Creep and The Creep-Swelling Relationship
Austenitic Alloys--Irradiation-Induced Swelling, Segregation and Microstructure
Irradiated Structural Alloys--Welding
Experimental Techniques and Facilities
Beryllium and Ceramics
This publication will be of interest to research scientists, metallurgists, nuclear engineers, nuclear utilities, nuclear reactor vendors. Also university nuclear engineering and materials sciences departments.