27.120.30 裂变物质 标准查询与下载

ISO 1709:2018/Amd 1:2022 核能.裂变材料.储存、搬运和加工中的临界安全原则.修改件1:控制和安全设备的方法

Nuclear energy — Fissile materials — Principles of criticality safety in storing, handling and processing — Amendment 1: Methods of control and safety equipment

KS A ISO 9894-2022 对液相六氟化铀进行二次取样

Subsampling of uranium hexafluoride in the liquid phase

KS A ISO 7195-2022 核能 六氟化铀（UF6）运输包装

Nuclear energy－Packaging of uranium hexafluoride(UF6) for transport

KS A ISO 9891-2022 二氧化铀粉末和烧结球团中碳含量的测定 高频感应炉燃烧 滴定法/库仑法/红外吸收法

Determination of carbon content in uranium dioxide powder and sintered pellets－High-frequency induction furnace combustion－Titrimetric/coulometric/infrared absorption methods

KS A ISO 9889-2022 二氧化铀粉末和烧结球团中碳含量的测定 电阻炉燃烧 滴定法/库仑法/红外吸收法

Determination of carbon content in uranium dioxide powder and sintered pellets－Resistance furnace combustion－Titrimetric/coulometric/infrared absorbtion method

KS A ISO 1709-2022 核能 裂变材料 储存、处理和加工的临界安全原则

Nuclear energy－Fissile materials－Principles of criticality safety in storing, handling and processing

KS A ISO 9892-2022 金属铀、二氧化铀粉末和球团、硝酸铀酰溶液 氟含量的测定 氟离子选择电极法

Uranium metal, uranium dioxide powder and pellets, and uranyl nitrate solutions－Determination of fluorine content－Fluoride ion selective electrode method

KS A ISO 18213-1-2022 核燃料技术 核材料衡算中的储罐校准和体积测定 第1部分：程序概述

Nuclear fuel technology－Tank calibration and volume determination for nuclear materials accountancy－Part 1：Procedural overview

KS A ISO 21238-2022 核能 核燃料技术 缩放因子法测定核电厂产生的低、中水平放射性废物包的放射性

Nuclear energy－Nuclear fuel technology－Scaling factor method to determine the radioactivity of low- and intermediate-level radioactive waste packages generated at nuclear power plants

KS A ISO 27468-2022 核临界安全 含有压水堆 UOx 燃料的系统的评估 边界燃耗信用方法

Nuclear criticality safety — Evaluation of systems containing PWR UOx fuels — Bounding burnup credit approach

KS A ISO 10276-2022 核能 燃料技术 用于运输放射性物质的包装件耳轴

Nuclear energy－Fuel technology－Trunnions for packages used to transport radioactive material

KS A ISO 18213-2-2022 核燃料技术 核材料衡算储罐标定和体积测定 第2部分：储罐标定数据标准化

Nuclear fuel technology－Tank calibration and volume determination for nuclear materials accountancy－Part 2：Data standardization for tank calibration

KS A ISO 7476-2022 核燃料技术 核级硝酸铀酰溶液中铀的测定 重量法

Nuclear fuel technology－Determination of uranium in uranyl nitrate solutions of nuclear grade quality－Gravimetric method

KS A ISO 9279-2022 二氧化铀球团密度和总孔隙率的测定汞置换法

Uranium dioxide pellets－Determination of density and total porosity－Mercury displacement method

KS A ISO 10980-2022 验证用于测量浓度的参考溶液的强度

Validation of the strength of reference solutions used for measuring concentrations

KS A ISO 27467-2022 核临界安全 假设临界事故分析

Nuclear criticality safety－Analysis of a postulated criticality accident

ASTM C1075-17(2022) 铀精矿取样的标准实施规程

1.1 These practices are intended to provide the nuclear industry with procedures for obtaining representative bulk samples from uranium-ore concentrates (UOC) (see Specification C967). 1.2 These practices also provide for obtaining a series of representative secondary samples from the original bulk sample for the determination of moisture and other test purposes, and for the preparation of pulverized analytical samples (see Test Methods C1022 and C1843). 1.3 These practices consist of a number of alternative procedures for sampling and sample preparation which have been shown to be satisfactory through long experience in the nuclear industry. These procedures are described in the following order. Stage Procedure Section Primary Sampling One-stage falling stream 5 Two-stage falling stream 6 Auger 7 Secondary Sampling Straight-path (reciprocating) 8 Rotating (Vezin) 9, 10 1.3.1 The primary and secondary sampling stages can be organized in the following way: 1.3.2 It is possible to combine the various elements of these stages in different ways to give satisfactory results depending on the agreed requirements of the contracting parties. For a given stage, however, each procedure must be regarded as a whole. It is highly inadvisable to mix elements belonging to different procedures. 1.4 These procedures do not include requirements for health, safety, and accountability. The observance of these practices does not relieve the user of the obligation to be aware of and to conform to all applicable international, federal, state, and local regulations pertaining to processing, shipping, or using uranium-ore concentrates. (Guidance is provided in CFR 10, Chapter 1.) 1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. 1.6 This standard does not purport to address all of the safety problems, 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.

Standard Practices for Sampling Uranium-Ore Concentrate

ASTM C1165-22 在铂工作电极上用受控电位库仑法测定H2SO

Standard Test Method for Determining Plutonium by Controlled-Potential Coulometry in H2SO4 at a Platinum Working Electrode

ASTM C785-08(2022) 核级氧化铝颗粒的标准规范

1.1 This specification applies to pellets of aluminum oxide that may be ultimately used in a reactor core, for example, as filler or spacers within fuel, burnable poison, or control rods. In order to distinguish between the subject pellets and “burnable poison” pellets, it is established that the subject pellets are not intended to be used as neutron-absorbing material. 1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard. 1.3 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.

Standard Specification for Nuclear-Grade Aluminum Oxide Pellets

ASTM C1066-09(2022) 核级氧化锆颗粒的标准规范

1.1 This specification applies to pellets of stabilized zirconium oxide used in nuclear reactors. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. 1.3 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.

Standard Specification for Nuclear Grade Zirconium Oxide Pellets