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

• Other Materials

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.