research

Ion Irradiation Effects and Evaluation of Al/B4C Neutron Absorbing Materials and Zirconium Alloys

Abstract

中子吸收材料和核燃料包壳材料与核燃料安全密切相关。中子吸收材料用于乏燃料的运输和储存中,保持燃料的次临界状态,防止临界事故发生;核燃料包壳材料是防止核燃料和高放射性物质泄漏的重要屏障。本论文主要研究了Al/B4C中子吸收材料和锆合金包壳材料的离子辐照效应,并进行了服役评估。 Al/B4C金属基复合材料具有良好的机械性能,热传导性能和中子吸收性能,主要应用于乏燃料的干式储存罐和乏燃料池格架中。在服役过程中,Al/B4C中子吸收材料不可避免地经受着中子辐照和氦的累积。为了研究辐照效应以及氦在材料中的行为,本论文设计了两个离子辐照:400keV氦离子辐照,离子通量为1.5×1017ions/cm2...Neutron absorbing material and cladding material are significant to nuclear fuel safety. Neutron absorbing materials are used in these spent fuel applications, transportation and storage, to maintain the fuel in subcritical condition and thereby prevent a criticality incident. The fuel cladding is a vital barrier to prevent the leakage of nuclear fuel and high radioactive materials. In this thesis...学位:理学博士院系专业:能源研究院_核工程与材料学号:3242011015385

    Similar works