1.1本规程涵盖包壳的辐照后检查程序、破损核燃料元件的确定、材料的选择和辐射研究试验、辐射条件的确定、包壳机械性能试验的进行以及数据报告。 1.2本规程的目的是为燃料元件包壳的辐照后检查提供详细指南，并实现辐射效应领域数据的更好相关性和解释。 1.3本规程可适用于所有类型燃料元件的金属包壳。本实施规程中描述的用于确定燃料元件包壳机械性能的试验应包括在包壳的预辐照表征中，并用于规划辐照效应试验，以评估核反应堆包壳材料和其他部件。 注1:标准E 380中所述的以国际单位制表示的值应视为标准。 ====意义和用途====== 包层材料的物理和机械性能可以通过暴露于高能中子通量而改变。这些变化的大小和关系是材料及其冶金条件的函数；辐射的量、速率和能谱；暴露温度；试验温度；冷却剂的纯度、速度、体积和净化系统；以及所含燃料的影响。

1.1 This practice covers the procedures for postirradiation examination of cladding, determination of breached nuclear fuel elements, selection of material and tests for radiation studies, determination of radiation conditions, conduction of tests for mechanical properties of cladding, and the reporting of data. 1.2 The purpose of this practice is to provide detailed guidelines for the postirradiation examination of fuel element cladding and to achieve better correlation and interpretation of the data in the field of radiation effects. 1.3 This practice may be applied to metallic cladding from all types of fuel elements. The tests described in this practice for determining mechanical properties of the fuel element cladding practice should be included in the preirradiation characterization of the cladding and for planning irradiation effects tests for evaluation of materials for cladding and other components in nuclear reactors. Note 1—The values stated in SI units as described in Standard E 380 are to be regarded as the standard. ====== Significance And Use ====== The physical and mechanical properties of cladding materials can be altered by exposure to a high-energy neutron flux. The magnitude and relationship of these changes are functions of the material and its metallurgical condition; the amount, rate, and energy spectrum of the radiation; the exposure temperature; the test temperature; the purity, velocity, volume, and purification system of the coolant; and effects of contained fuel.