ISO 19226:2017提供了一个程序，用于评估反应堆堆芯和安全壳内表面之间、通过压力容器和反应堆腔、活性燃料组件两端之间区域内的辐照数据，前提是堆芯中有中子源。 注:这些辐照数据可能是中子注量或每原子位移（dpa）和氦产量。 该评估采用了中子通量计算和来自容器内和空腔剂量测定（视情况而定）的测量数据。本文件适用于压水反应堆（PWR）、沸水反应堆（BWR）和压重水反应堆（PHWR）。 ISO 19226:2017还提供了评估反应堆压力容器和压水堆、沸水堆和PHWR内部组件中子损伤特性的程序。损伤特性主要是由中子碰撞引起的原子直接位移引起的原子位移损伤，以及由气体产生引起的间接损伤，两者都强烈依赖于中子能谱。 因此，对于给定的中子注量和中子能谱，计算原子位移的总累积数是用于反应堆寿命管理的重要数据。

ISO 19226:2017 provides a procedure for the evaluation of irradiation data in the region between the reactor core and the inside surface of the containment vessel, through the pressure vessel and the reactor cavity, between the ends of active fuel assemblies, given the neutron source in the core. NOTE These irradiation data could be neutron fluence or displacements per atom (dpa), and Helium production. The evaluation employs both neutron flux computations and measurement data from in-vessel and cavity dosimetry, as appropriate. This document applies to pressurized water reactors (PWRs), boiling water reactors (BWRs), and pressurized heavy water reactors (PHWRs). ISO 19226:2017 also provides a procedure for evaluating neutron damage properties at the reactor pressure vessel and internal components of PWRs, BWRs, and PHWRs. Damage properties are focused on atomic displacement damage caused by direct displacements of atoms due to collisions with neutrons and indirect damage caused by gas production, both of which are strongly dependent on the neutron energy spectrum. Therefore, for a given neutron fluence and neutron energy spectrum, calculations of the total accumulated number of atomic displacements are important data to be used for reactor life management.