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Effect of Irradiation Environment of Fast Reactor's Fuel Elements on Void Swelling in P, Ti-Modified 316 Stainless Steel

机译:快速反应堆燃料元件辐射环境对P,Ti改性316不锈钢空隙肿胀的影响

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The difference in swelling behavior of P, Ti-modified 316 stainless steel (PNC316) between sample irradiation using material irradiation vehicle (e.g. FFTF/MOTA) and fuel assembly irradiation in FBR was investigated. From the evaluation of the dose dependence in the swelling of PNC316, it is clearly shown that swelling of claddings irradiated by fuel assemblies occurred earlier than the swelling of samples irradiated by material irradiation vehicle in the range of irradiation temperatures from 723K to 823K. The microstructural evolution of the claddings irradiated by fuel assemblies, which is represented by void formation, should be mainly affected by the irradiation environments: irradiation temperature history, temperature gradient within the thickness of the claddings, and by the primary and secondary stresses within the cladding during irradiation.
机译:研究了使用材料照射型载体(例如FFTF / MOTA)和FBR中的燃料组件辐照样品照射在样品辐射之间的P,Ti改性316不锈钢(PNC316)之间的溶胀行为差异。从评估PNC316的肿胀中的剂量依赖性,清楚地表明,燃料组件照射的包层的肿胀比在照射温度范围为723K至823K的照射温度范围内的样品溶胀。由空隙形成表示的燃料组件照射的包层的微观结构演变应主要受辐射环境的影响:照射温度历史,熔接厚度内的温度梯度,以及覆层内的初级和次级应力。在照射期间。

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