STP 1366, the nineteenth volume in this series, examines 90peer-reviewed papers from the international nuclear community, withthe emphasis on advanced materials such as silicon carbide andvanadium alloys. A majority of the papers are devoted to pressurevessel embrittlement and its mitigation. Smaller segments addressthe issues of light water reactors, fusion reactors, and to alesser extent, breeder reactors.

Several emerging issues are also explored, including reducedactivation, welding of irradiated materials and damage resultingform high-energy proton beams in accelerator-driven nuclearsystems.

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 andReirradiation Behavior

• Irradiation-Induced Behavior Of Iron, Model Alloys, andFerritic/Martensitic Alloys

• Low Activation Ferritic/Martensitic Alloys

• Irradiation Creep and The Creep-Swelling Relationship

• Austenitic Alloys--Irradiation-Induced Swelling, Segregationand 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, nuclearreactor vendors. Also university nuclear engineering and materialssciences departments.