核能. 反应堆容器和内部构件中子注量和每原子位移（DPA）的测定

[中文适用范围]： 本文件提供了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、活性燃料组件端部之间区域的辐照数据的程序，假定中子源位于反应堆堆芯和安全壳内表面之间。 核。 注：这些辐照数据可以是中子注量或每原子位移 (dpa) 以及氦气产量。 该评估酌情采用中子通量计算以及来自容器内和腔内剂量测定的测量数据。 本文件适用于压水反应堆（PWR）、沸水反应堆（BWR）和加压重水反应堆（PHWR）。 本文件还提供了评估反应堆压力容器以及压水堆、沸水堆和重水堆内部组件的中子损伤特性的程序。 损伤特性集中于由于与中子碰撞导致原子直接位移引起的原子位移损伤和气体产生引起的间接损伤，这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。 [外文原描述]： 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.