1.1 本规程适用于气态六氟化铀（UF）的取样 6. )在一次性破坏性分析（SUDA）取样器中使用沸石的吸附剂特性，从处理设施、同位素富集级联或储存筒中提取。 1.2 本实践基于太平洋西北国家实验室开发的SUDA方法 ( 1. ) 2. 用于收集超滤样品 6. 用于核材料保障和其他应用中铀同位素含量的测定。 1.3 UF 6. 收集的转化为氟化铀（UO 2. F 2. )，允许在不太严格的条件下对样品进行处理和分类，以便运输 6. . 1.4 本规程可用于收集用于安全措施测量的样品。 用这种方法采集的保障样品已被证明可以提供合适的同位素测量 ( 1. ) . 1.5 尚未证明该实践是否适合符合规范 C787 和 C996 . 实践 C1052 或 C1703 可用于收集符合这些规范的样品。 1.6 本规程的范围不包括防止危险性的规定。 1.7 单位- 以国际单位制表示的数值应视为标准值。国际单位制后括号中给出的值仅供参考，不被视为标准值。 1.8 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。 1.9 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====== 5.1 设施运营商和安全检查员定期收集UF 6. 从处理线、同位素浓缩级联或储存筒中提取样本，以确定铀同位素组成。同位素比值 n ( 235 U）/ n ( 238 U） 尤其重要，因为它用于计算裂变物质的量 235 样品中的U。 5.2 常规采样实践（例如实践 C1052 和 C1703 )收集超滤样品 6. ，通常数量大于1克。由于超滤的化学危害 6. （在某些情况下，收集量很大），越来越多的航空运输运营商不愿意运输此类样品。相比之下，预计SUDA样品将作为例外数量运输（例如，根据UN 2910） ( 3. ) )，因为转化为危险性较小、更稳定的化学物质可以避免超滤的化学危害 6. 与实践类似 C1880 . 此外，运输要求降低，SUDA取样器的收集质量较小（低于实际情况） C1880 )允许在同一批货物中运输多个SUDA样品。 5.3 对于保障应用，同位素测量值应在2010年国际目标值（ITV）范围内 ( 5. ) 已经证明 ( 1. ) . 5.4 该实践提供了以下品质: 5.4.1 核查核材料申报的适用性。 5.4.2 样品收集器的安全、简单和快速程序，最大限度地减少样品处理和交叉污染的可能性。 5.4.3 在各种设施中使用的灵活性。 5.4.4 适应设施运行参数微小变化的鲁棒性。 5.4.5 采集样本的操作设施的保密性。 5.4.6 样品处理和运输的安全性，因为样品是一种危险性较小、更稳定的形式（特别是UO） 2. F 2. 比超滤更稳定，挥发性更小 6. 气体）。 5.4.7 易于在实验室制备样品，在铀含量回收过程中减少加工危害 ( 1. ) . 5.5 使用本规程采集的样品适用于测定铀同位素组成，如中所述 4.5 ，用于安全防护应用。必须注意确保用于SUDA样品的取样龙头的清洁度，如任何UF 6. 先前样本采集中取样口的滞留可能会影响样本采集和同位素测量（见第节） 9 有关此问题的更多详细信息）。本规程的其他应用也是可能的，但需要在使用前进行验证。

1.1 This practice is applicable to sampling gaseous uranium hexafluoride (UF 6 ) from processing facilities, isotope enrichment cascades or storage cylinders, using the sorbent properties of zeolite in a single-use destructive assay (SUDA) sampler. 1.2 This practice is based on the SUDA method developed at Pacific Northwest National Laboratory ( 1 ) 2 for collection of samples of UF 6 for determination of uranium isotopic content for nuclear material safeguards and other applications. 1.3 The UF 6 collected is converted to uranyl fluoride (UO 2 F 2 ), allowing samples to be handled and categorized for transport under less stringent conditions than are required for UF 6 . 1.4 This practice can be used to collect samples for safeguards measurements. Safeguards samples collected with this practice have been shown to provide suitable isotopic measurements ( 1 ) . 1.5 This practice has not been demonstrated for suitability for compliance with Specifications C787 and C996 . Practices C1052 or C1703 can be used to collect samples for compliance with these specifications. 1.6 The scope of this practice does not include provisions for preventing criticality. 1.7 Units— The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard. 1.8 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. 1.9 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 ====== 5.1 Facility operators and safeguards inspectors routinely collect UF 6 samples from processing lines, isotopic enrichment cascades or storage cylinders to determine uranium isotopic composition. The isotope ratio n ( 235 U)/ n ( 238 U) is particularly important since it is used to calculate the amount of fissile 235 U in the sample. 5.2 Conventional sampling practices (such as Practices C1052 and C1703 ) collect samples of UF 6 , usually in quantities greater than one gram. Due to the chemical hazards of UF 6 (and in some cases the high collection mass), an increasing number of air transport operators are unwilling to transport such samples. In contrast, SUDA samples are expected to be transported as excepted quantities (for example, under UN 2910 ( 3 ) ), as the conversion to a less hazardous, more stable chemical species avoids the chemical hazards of UF 6 similar to Practice C1880 . Additionally, the decreased shipping requirement and small collection mass of SUDA samplers (less than Practice C1880 ) allow for multiple SUDA samples to be transported in the same shipment. 5.3 For safeguards applications, isotopic measurements that fall within the 2010 International Target Value (ITV) ranges ( 5 ) have been demonstrated ( 1 ) . 5.4 This practice provides the following qualities: 5.4.1 Fitness for purpose in verifying nuclear material declarations. 5.4.2 A safe, simple and fast procedure for the sample collector that minimizes sample handling and potential for cross-contamination. 5.4.3 Flexibility for use in a wide variety of facilities. 5.4.4 Robustness to adapt to minor changes in facility operating parameters. 5.4.5 Confidentiality for the operating facility from which the sample is collected. 5.4.6 Safety in sample handling and transport since the sample is a less hazardous, more stable form (specifically, UO 2 F 2 is more stable and less volatile than UF 6 gas). 5.4.7 Ease of sample preparation in the laboratory with reduced processing hazards during recovery of the uranium content ( 1 ) . 5.5 Samples collected using this practice are suitable for determination of uranium isotopic composition, as described in 4.5 , for safeguards applications. Care must be taken to ensure cleanliness of the sampling tap to be used for SUDA samples, as any UF 6 holdup in the sampling tap from previous sample collection could affect sample collection and isotopic measurements (see Section 9 for further details regarding this issue). Other applications of this practice are possible but require validation prior to use.