1.1本指南涵盖了可与规程E185要求的核反应堆容器监督方法和程序结合使用的试验方法和程序，但不能作为其替代方法。概述的补充试验方法允许获取有关反应堆容器钢断裂韧性、缺口延展性和抗拉强度特性的辐射引起变化的额外信息。 1.2本指南提供了辐照试样制备的建议，并确定了反应堆监督操作和辐照后测试规划的特殊预防措施和要求。还为个别测试方法提供了数据简化和计算程序指南。 参考其他ASTM试验方法进行试样试验的物理行为和原始数据采集。

1.1 This guide covers test methods and procedures that can be used in conjunction with, but not as alternatives to, those required by Practice E185 for the surveillance of nuclear reactor vessels. The supplemental test methods outlined permit the acquisition of additional information on radiation-induced changes in fracture toughness, notch ductility, and tensile strength properties of the reactor vessel steels. 1.2 This guide provides recommendations for the preparation of test specimens for irradiation, and identifies special precautions and requirements for reactor surveillance operations and postirradiation test planning. Guidance on data reduction and computational procedures also is given for individual test methods. Reference is made to other ASTM test methods for the physical conduct of specimen tests and for raw data acquisition.