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现行 ASTM C1703-18(2023)
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Standard Practice for Sampling of Gaseous Uranium Hexafluoride for Enrichment 浓缩用气态六氟化铀取样的标准实施规程
发布日期: 2023-01-01
1.1 本规程涵盖了六氟化铀(UF)代表性样品的提取方法 6. )在气相中发生的转移期间。气相中的这种转移可以在连续生产过程(例如转化设施中的蒸馏塔)中的钢瓶填充过程中发生。此类样品可用于确定是否符合适用的商业规范,例如规范 C787型 . 1.2 自UF以来 6. 取样是在灌装过程中进行的,当取样的散装材料被添加到容器中已经存在的残留物中时(“鞋跟回收”),该做法不涉及买方和卖方之间可能商定的任何特殊附加安排。 此类安排将以质量保证程序为基础,如气瓶来源的可追溯性(以防止受辐照材料污染)。 1.3 如果在填充和取样后清洗接收筒,用户必须进行特殊验证,以验证样品的代表性。因此,预计气相取样对挥发性杂质的结果可能是保守的。 1.4 该实践仅适用于在气相中发生转移时。 当在液相中进行转移时,练习 第1052页 应适用。本规程不适用于气瓶充装后的气体取样,因为取样的样品不能代表气瓶。 1.5 本标准并不旨在解决与其使用相关的所有安全问题(如有)。本标准的使用者有责任在使用前建立适当的安全、健康和环境实践,并确定监管限制的适用性。 1.6 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《国际标准、指南和建议制定原则决定》中确立的国际公认标准化原则制定的。 =====意义和用途====== 5.1 六氟化铀通常大量生产和处理(通常为1至14吨),因此必须参考代表性样品进行表征(见ISO 7195)。 样品用于确定是否符合适用的商业规范 C787型 UF涉及的数量、物理性质、化学反应性和危险性质 6. 对于代表性取样,必须按照最严格控制的程序使用和操作专门设计的设备。UF可采用此做法 6. 以审查现有程序的有效性,或作为未来使用的设备和程序的设计指南。 5.2 本规程旨在避免液体UF 6. 一旦钢瓶装满,取样。出于安全原因,操作大量液体UF 6. 应尽可能避免。 5.3 需要强调的是,这一做法并非旨在解决常规或核临界安全问题。
1.1 This practice covers methods for withdrawing representative sample(s) of uranium hexafluoride (UF 6 ) during a transfer occurring in the gas phase. Such transfer in the gas phase can take place during the filling of a cylinder during a continuous production process, for example the distillation column in a conversion facility. Such sample(s) may be used for determining compliance with the applicable commercial specification, for example Specification C787 . 1.2 Since UF 6 sampling is taken during the filling process, this practice does not address any special additional arrangements that may be agreed upon between the buyer and the seller when the sampled bulk material is being added to residues already present in a container (“heels recycle”). Such arrangements will be based on QA procedures such as traceability of cylinder origin (to prevent for example contamination with irradiated material). 1.3 If the receiving cylinder is purged after filling and sampling, special verifications must be performed by the user to verify the representativity of the sample(s). It is then expected that the results found on volatile impurities with gas phase sampling may be conservative. 1.4 This practice is only applicable when the transfer occurs in the gas phase. When the transfer is performed in the liquid phase, Practice C1052 should apply. This practice does not apply to gas sampling after the cylinder has been filled since the sample taken will not be representative of the cylinder. 1.5 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. 1.6 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 Uranium hexafluoride is normally produced and handled in large (typically 1 to 14-ton) quantities and must, therefore, be characterized by reference to representative samples (see ISO 7195). The samples are used to determine compliance with the applicable commercial specification C787 . The quantities involved, physical properties, chemical reactivity, and hazardous nature of UF 6 are such that for representative sampling, specially designed equipment must be used and operated in accordance with the most carefully controlled and stringent procedures. This practice can be used by UF 6 converters to review the effectiveness of existing procedures or as a guide to the design of equipment and procedures for future use. 5.2 The intention of this practice is to avoid liquid UF 6 sampling once the cylinder has been filled. For safety reasons, manipulation of large quantities of liquid UF 6 should be avoided when possible. 5.3 It is emphasized that this practice is not meant to address conventional or nuclear criticality safety issues.
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