中子辐射保护屏蔽 设计原则和选择适用材料的考虑

[中文适用范围]： 本国际标准提出了中子辐射防护屏蔽设计和中子辐射防护屏蔽材料选择的一般方法。 本国际标准适用于中子源所在和使用的设施和操作，以及工人职业暴露的设施和操作。 这些业务和设施的设计和目的差异很大。 这些设施和运营包括但不限于： ——核电厂； ——研究堆； ——粒子加速器和中子发生器； ——聚变研究设施； ——放射性物质作业的运输包装； ——医疗和研究设施及应用； ——工业应用，例如使用测量和检测湿度和密度水平的设备； ——空间应用； ——校准设施； ——射线照相装置； ——核燃料循环装置（后处理厂、钚溶液处理设施、屏蔽室、废物储存等）。 本国际标准中包含的中子屏蔽设计准则和屏蔽材料的选择应适用于此类设施中中子辐射防护屏蔽系统的设计。 [外文原描述]： This International Standard presents the general methodology governing the design of neutron radiation protection shielding and the choice of neutron radiation protection shielding materials. This International Standard is applicable to facilities and operations where neutron sources are located and used, and where workers are occupationally exposed. These operations and facilities vary considerably in design and purpose. These facilities and operations include, but are not limited to:  nuclear power plants;  research reactors;  particle accelerators and neutron generators;  fusion research facilities;  transportation packaging for radioactive materials operations;  medical treatment and research facilities and applications;  industrial applications such as use of devices for measuring and detecting moisture and density level;  space applications;  calibration facilities;  radiographic installations;  nuclear fuel cycle installations (reprocessing plants, plutonium solution handling facilities, shielded cells, waste storage, etc.). The criteria for the design of neutron shielding and the choice of shielding materials contained in this International Standard should be applied to the design of neutron radiation protection shielding systems in such facilities.