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The effect of irradiation on the mechanical properties of nuclear fuel cladding and insulating materials for the Gen. IV pressure tube super critical water reactor

辐照对第四代压力管超临界水堆核燃料包壳及绝缘材料力学性能的影响

基本信息

批准号：
424202-2011
负责人：
Klassen, Robert
金额：
$ 5.83万
依托单位：
University of Western Ontario
依托单位国家：
加拿大
项目类别：
NSERC/NRCan/AECL Generation IV Energy Technologies Program
财政年份：
2014
资助国家：
加拿大
起止时间：
2014-01-01 至 2015-12-31
项目状态：
已结题

来源：
https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=551840
关键词：
effect irradiation mechanical properties nuclear

项目摘要

One of the primary challenges associated with the proposed Generation IV pressure tube type SuperCritical Water Reactor (SCWR) is the selection of suitable nucear fuel cladding and thermal insulating material capable of enduring exposure to high levels of neutron irradiation in a supercritical water environment at temperature in excess of 750C. The leading candidate fuel cladding materials are microstructurally-modified austenitic stainless steel alloys while the leading candidate insulating material is an yttrium-stabilized zirconia. To date nothing is known of the effect of prolonged high-temperature neutron irradiation on the mechanical properties of these materials. The proposed research project will obtain such data by performing ion-irradiation on the materials at temperature up to 700C as a means of simulating high-temperature neutron irradiation. Micro-mechanical tests and microstructural analyses, using electron microscopy, of the ion-irradiated material will allow determination, for the first time, of the dependence of the strength, ductility, and microstructural stability of these materials upon irradiation dosage and irradiation temperature. These data are absolutly essential for proceeding with detailed materials selection for the proposed Gen. IV SCWR.

与所提出的第四代压力管式超临界水反应堆（SCWR）相关联的主要挑战之一是选择合适的核燃料包壳和绝热材料，所述材料能够在超过750 ° C的温度下在超临界水环境中耐受暴露于高水平的中子辐照。领先的候选燃料包壳材料是微结构改性的奥氏体不锈钢合金，而领先的候选绝缘材料是钇稳定的氧化锆。到目前为止，还不知道长时间高温中子辐照对这些材料的机械性能的影响。拟议的研究项目将通过在高达700 ℃的温度下对材料进行离子辐照来获得这些数据，作为模拟高温中子辐照的一种手段。微机械测试和微观结构分析，使用电子显微镜，离子辐照的材料将允许确定，第一次，这些材料的强度，延展性和微观结构的稳定性的依赖辐照剂量和辐照温度。这些数据是绝对必要的，为拟议的第四代超临界水反应堆进行详细的材料选择。