1.1 本指南涵盖中子测量和计算基准的设施和程序。本指南的特定章节讨论:使用特征良好的基准中子场校准积分中子传感器；使用经认证的中子注量标准来校准辐射计数设备或确定实验室间测量的一致性；开发专门的基准场来测试中子输运计算；使用众所周知的裂变谱来基准谱平均截面；以及使用基准数据和计算来确定衍生中子剂量测定结果中的不确定性。 1.2 以国际单位制表示的数值应视为标准值。本标准不包括其他计量单位。 1.3 本标准并非旨在解决与其使用相关的所有安全问题（如有）。本标准的用户有责任在使用前制定适当的安全、健康和环境实践，并确定监管限制的适用性。 1.4 本国际标准是根据世界贸易组织技术性贸易壁垒（TBT）委员会发布的《关于制定国际标准、指南和建议的原则的决定》中确立的国际公认标准化原则制定的。 ====意义和用途====== 3.1 本指南描述了使用具有众所周知特性的中子场进行中子传感器校准、相互比较不同剂量测定方法以及证实用于从中子传感器响应测量中获得中子场信息的程序的方法。 3.2 本指南仅讨论适用于轻水反应堆剂量测定基准测试的选定标准和参考中子场。此处考虑的标准场包括中子源环境，其近似于: a） 未散射中子谱 252 Cf自发裂变；和 b） 这个 235 热中子诱发裂变。选择这些标准场是因为其光谱与反应堆光谱的高能区（E>2 MeV）相似。术语中定义了各类基准字段 E170 . 3.3 还有其他众所周知的中子场设计用于模拟特殊环境，例如压力容器模型，在其中可以在“容器”的钢体积内进行剂量测量当此类模型具有适当的特征时，它们也被称为基准字段。 为了提高中子剂量测量技术的准确性，已经开发或投入使用了各种工程基准领域。指南中讨论了这些特殊的基准实验 2006年 ，并在参考文献中 ( 1. ) 4. 和 ( 2. ) .

1.1 This guide covers facilities and procedures for benchmarking neutron measurements and calculations. Particular sections of the guide discuss: the use of well-characterized benchmark neutron fields to calibrate integral neutron sensors; the use of certified-neutron-fluence standards to calibrate radiometric counting equipment or to determine interlaboratory measurement consistency; development of special benchmark fields to test neutron transport calculations; use of well-known fission spectra to benchmark spectrum-averaged cross sections; and the use of benchmarked data and calculations to determine the uncertainties in derived neutron dosimetry results. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. ====== Significance And Use ====== 3.1 This guide describes approaches for using neutron fields with well known characteristics to perform calibrations of neutron sensors, to intercompare different methods of dosimetry, and to corroborate procedures used to derive neutron field information from measurements of neutron sensor response. 3.2 This guide discusses only selected standard and reference neutron fields which are appropriate for benchmark testing of light-water reactor dosimetry. The Standard Fields considered here include neutron source environments that closely approximate: a) the unscattered neutron spectra from 252 Cf spontaneous fission; and b) the 235 U thermal neutron induced fission. These standard fields were chosen for their spectral similarity to the high energy region (E > 2 MeV) of reactor spectra. The various categories of benchmark fields are defined in Terminology E170 . 3.3 There are other well known neutron fields that have been designed to mockup special environments, such as pressure vessel mockups in which it is possible to make dosimetry measurements inside of the steel volume of the “vessel.” When such mockups are suitably characterized, they are also referred to as benchmark fields. A variety of these engineering benchmark fields have been developed, or pressed into service, to improve the accuracy of neutron dosimetry measurement techniques. These special benchmark experiments are discussed in Guide E2006 , and in Refs ( 1 ) 4 and ( 2 ) .