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“国产新锆合金小组件辐照考验”是大型先进压水堆重大专项“核电站国产新锆合金及关键材料辐照性能研究项目”课题的子课题之一,其研究目的是在研究堆上开展国产新锆合金小组件的辐照考验,并在热室内完成辐照后检验,获取辐照性能数据,以评估国产新锆合金的辐照性能。课题取得的重要成果之一是论证了利用中国先进研究堆(CARR)及其配套高温高压水回路实施燃料小组件辐照的技术方案,并提交了辐照装置初步设计图纸、中子物理初步分析报告、热工
“Domestic New Zirconium Alloy Components Radiation Test ” is one of the sub-topics of the major project of large-scale advanced PWR "research project of irradiation properties of domestic new zirconium alloy and key materials of nuclear power station Research reactor on the domestic new zirconium alloy components of the irradiation test, and in the hot chamber to complete the test after irradiation to obtain the irradiation performance data to evaluate the domestic new zirconium alloy irradiation performance. One of the important achievements made by the project is to demonstrate the technical proposal of using CARR and its supporting high-temperature and high-pressure water circuit to implement the irradiation of fuel assemblies, and submit preliminary design drawings of irradiation device, preliminary analysis of neutron physics Report, thermal