ANS 6.6.1-2015（R2020）定义了计算要求，并讨论了轻水反应堆（LWR）核电厂附近由于来自现场封闭源的直接和散射伽马射线而产生的剂量率估计的测量技术。考虑厂房外的现场位置和场外非限制区域的位置。确定了对剂量率有显著影响的所有源，并讨论了计算每个源强度的方法。特别强调16N源，因为它们是沸水反应堆（BWR）的重要直接和散射辐射源。该标准明确排除了气体和液体流出物的辐射。本标准描述了计算剂量率所需考虑的事项，包括组件自屏蔽、墙壁和结构提供的屏蔽以及散射辐射。 给出了测量要求和测量数据解释。本标准包括正常运行和停机条件，但不涉及事故或正常运行瞬态条件。本标准还适用于干燃料储存设施产生的伽马剂量。关键词:屏蔽、辐射防护、轻水反应堆

ANS 6.6.1-2015 (R2020) defines calculational requirements and discusses measurement techniques for estimates of dose rates near light water reactor (LWR) nuclear power plants due to direct and scattered gamma-rays from contained sources on-site. On-site locations outside plant buildings and locations in the offsite unrestricted area are considered. All sources that contribute significantly to dose rates are identified and methods for calculating the source strength of each are discussed. Particular emphasis is placed on16N sources as they are significant sources of direct and scattered radiation for boiling water reactors (BWRs). The standard specifically excludes radiation from gaseous and liquid effluents. The standard describes the considerations necessary to compute dose rates, including component self-shielding, shielding afforded by walls and structures, and scattered radiation. The requirements for measurements and data interpretation of measurements are given. The standard includes normal operation and shutdown conditions but does not address accident or normal operational transient conditions. The standard also applies to the gamma dose resulting from Dry Fuel Storage Facilities.Keywords:shielding, radiation protection, light water reactor