1.1 本规程是钚材料溶解技术的汇编，适用于表征这些材料的试验方法。列出了对钚进行分析或对其他成分进行分析的主要钚材料的溶解处理。当其中一种分析必须具有高精度时，如钚分析时，溶解材料的等分试样是以质量为基础分配的；否则它们以体积为基础进行分配。 1.2 本规程中的程序适用于钚金属、钚氧化物和铀钚混合氧化物的溶解。使用试验方法分析溶解材料的等分试样，如试验方法小组委员会C26.05制定的试验方法，以证明其符合适用要求。其中可能包括产品规格，如规格 C757 和 C833 。 1.3 本规程中的一个或多个程序可能适用于独特的钚材料，如合金、化合物和废料。用户必须确定本规程对此类材料的适用性。 1.4 处理方法按呈现顺序如下: 程序编号 程序标题 部分 1. 室温下用盐酸溶解金属钚 9 2. 金属钚的盐酸溶解和加热 10 3. 金属钚在硫酸中的溶解 11 4. 氧化钚和铀钚混合物的溶解 密封回流技术产生的氧化物 12 5. 硫酸氢钠熔融法溶解氧化钚和铀钚混合氧化物 13 6. 铀钚混合氧化物和低火氧化钚在烧杯中的溶解 14 7. 开放容器（带回流冷凝器）溶解氧化钚粉末 15 8. 开放容器（带回流冷凝器）溶解混合氧化物粉末 16 9 氧化钚粉末的密闭热块溶解 17 10 开放容器（带回流冷凝器）溶解混合氧化物颗粒 18 1.5 以国际单位制表示的数值应视为标准。摩尔浓度（M）的非国际单位制单位也被视为标准单位。括号中的值（非国际单位制），如有提供，仅供参考，不视为标准值。 1.6 本标准并非旨在解决与其使用相关的所有安全问题（如有）。本标准的使用者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。 1.7 本国际标准是根据世界贸易组织技术性贸易壁垒委员会发布的《关于制定国际标准、指南和建议的原则的决定》中确立的国际公认的标准化原则制定的。 ===意义和用途====== 5.1 钚和铀的混合物被用作核反应堆燃料。用作核反应堆燃料的材料必须符合规范中所述的铀和钚的组合含量、有效裂变物质含量和杂质含量的某些标准 C757 和 C833 使用本规程中所述程序之一溶解后，对材料进行钚和铀含量测定，以确定含量是否符合买方规定。 5.2 独特的钚材料，如合金、化合物和废金属，通常用各种酸混合物溶解，或用各种助熔剂熔化。许多钚盐可溶于盐酸。本规程中包含的一个或多个程序可能对其中一些材料有效；但是，用户应验证其对特定钚材料的适用性。

1.1 This practice is a compilation of dissolution techniques for plutonium materials that are applicable to the test methods used for characterizing these materials. Dissolution treatments for the major plutonium materials assayed for plutonium or analyzed for other components are listed. Aliquots of the dissolved materials are dispensed on a mass basis when one of the analyses must be of high precision, such as plutonium assay; otherwise they are dispensed on a volume basis. 1.2 Procedures in this practice are intended for the dissolution of plutonium metal, plutonium oxide, and uranium-plutonium mixed oxides. Aliquots of dissolved materials are analyzed using test methods, such as those developed by Subcommittee C26.05 on Methods of Test, to demonstrate compliance with applicable requirements. These may include product specifications such as Specifications C757 and C833 . 1.3 One or more of the procedures in this practice may be applicable to unique plutonium materials, such as alloys, compounds, and scrap materials. The user must determine the applicability of this practice to such materials. 1.4 The treatments, in order of presentation, are as follows: Procedure Number Procedure Title Section 1 Dissolution of Plutonium Metal with Hydrochloric Acid at Room Temperature 9 2 Dissolution of Plutonium Metal with Hydrochloric Acid and Heating 10 3 Dissolution of Plutonium Metal with Sulfuric Acid 11 4 Dissolution of Plutonium Oxide and Uranium-Plutonium Mixed Oxide by the Sealed-Reflux Technique 12 5 Dissolution of Plutonium Oxide and Uranium-Plutonium Mixed Oxides by Sodium Bisulfate Fusion 13 6 Dissolution of Uranium-Plutonium Mixed Oxides and Low-Fired Plutonium Oxide in Beakers 14 7 Open-Vessel (with Reflux Condenser) Dissolution of Plutonium Oxide Powder 15 8 Open-Vessel (with Reflux Condenser) Dissolution of Mixed Oxide Powder 16 9 Closed-Vessel Hot Block Dissolution of Plutonium Oxide Powder 17 10 Open-Vessel (with Reflux Condenser) Dissolution of Mixed Oxide Pellets 18 1.5 The values stated in SI units are to be regarded as standard. The non-SI unit of molarity (M) is also to be regarded as standard. Values in parentheses (non-SI units), where provided, are for information only and are not considered standard. 1.6 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. 1.7 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 Plutonium and uranium mixtures are used as nuclear reactor fuels. For use as a nuclear reactor fuel, the material must meet certain criteria for combined uranium and plutonium content, effective fissile content, and impurity content as described in Specifications C757 and C833 . After dissolution using one of the procedures described in this practice, the material is assayed for plutonium and uranium to determine if the content is correct as specified by the purchaser. 5.2 Unique plutonium materials, such as alloys, compounds, and scrap metals, are typically dissolved with various acid mixtures or by fusion with various fluxes. Many plutonium salts are soluble in hydrochloric acid. One or more of the procedures included in this practice may be effective for some of these materials; however their applicability to a particular plutonium material shall be verified by the user.