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STP1366 |
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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. |
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