Dislocation-Radiation Obstacle Interactions: Developing Improved Mechanical Property Constitutive Models

[摘要] Radiation damage to structural and cladding materials, including austenitic stainless steels, ferritic steels, and zirconium alloys, in nuclear reactor environments results in significant mechanical property degradation, including yield strength increases, severe ductility losses and flow localization, which impacts reliability and performance. Generation IV and advanced fuel cycle concepts under consideration will require the development of advanced structural materials, which will operate in increasingly hostile environments. The development of predictive models is required to assess the performance and response of materials in extreme Gen IV reactor operating conditions (temperature, stress, and pressure), to decrease the time to rapidly assess the properties of new materials and insert them into technological applications (Gen IV and Advanced Fuel Cycle Operations).

[发布日期] 2007-11-29 [发布机构] University of California, Berkeley

[关键词] Building Materials;Reactors;36 Materials Science;Fuel Cycle;Stainless Steels