F40 核材料、核燃料综合 标准查询与下载

EJ/T 1054-2007 核材料和核设施实物保护

本标准规定了核材料和核设施实物保护的基本要求。 本标准适用于核材料和核设施实物保护系统的设计、运行、维护和升级改造。

Physical protection of nuclear material and nuclear facilities

ISO 21847-1:2007 核燃料技术.α光谱测定法.第1部分:铀及其化合物中镎的测定

This part of ISO 21847 describes a method for determining trace amounts of 237Np in uranium hexafluoride, uranium oxides or uranyl nitrate.

Nuclear fuel technology - Alpha spectrometry - Part 1: Determination of neptunium in uranium and its compounds

ISO 21847-3:2007 核燃料技术.α光谱测定法.第3部分:铀及其化合物中铀232的测定

This part of ISO 21847 describes a method for determining trace amounts of 232U in uranium hexafluoride, uranium oxides or uranyl nitrate.

Nuclear fuel technology - Alpha spectrometry - Part 3: Determination of uranium 232 in uranium and its compounds

ISO 21847-2:2007 核燃料技术.α光谱测定法.第2部分:铀及其化合物中钚的测定

This part of ISO 21847 describes a method for determining trace amounts of 238Pu and 239Pu + 240Pu in uranium hexafluoride, uranium oxides or uranyl nitrate.

Nuclear fuel technology - Alpha spectrometry - Part 2: Determination of plutonium in uranium and its compounds

NF M60-455*NF ISO 21238:2007 核能.核燃料技术.测定核电站产生的低级和中级放射废弃物包装件放射性的换算因子法

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.

DIN 25403-1:2007 裂变材料加工和处理的临界安全.第1部分:原则

Criticality safety in processing and handling of fissile materials - Part 1: Principles

ISO 21238:2007 核能.核燃料技术.测定核电厂产生的低和中级放射性废物包放射性的换算因子法

This International Standard gives guidelines for the common basic methodology of empirically determining scaling factors to evaluate the radioactivity of difficult-to-measure nuclides in low- and intermediate-level radioactive waste packages. This International Standard gives common guidelines for the scaling factors used in the characterization of contaminated wastes produced in nuclear power plants with water-cooled reactor. This International Standard is also relevant to other reactor types, such as gas-cooled reactors. Methodologies for determining scaling factors based on theoretical considerations (i.e. not based on experimental measurement) are not covered by this International Standard.

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

ASTM C1205-07 用α光谱测定法对土壤中镅-241进行放射化学测定的标准试验方法

This test method provides the speed and high decontamination factors attainable with liquid-liquid extraction of the actinides and eliminates filtration techniques that are more time consuming. This test method provides a precise determination of americium in concentrations normally found in environmental samples.1.1 This method covers the determination of americium-241 in soil by means of chemical separations and alpha spectrometry. It is designed to analyze up to ten grams of soil or other sample matrices that contain up to 30 mg of combined rare earths. This method allows the determination of americium-241 concentrations from ambient levels to applicable standards. The values stated in SI units are to be regarded as standard.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 and health practices and determine the applicability of regulatory limitations prior to use. For specific precaution statements, see Section 10.

Standard Test Method for The Radiochemical Determination of Americium-241 in Soil by Alpha Spectrometry

ASTM C1507-07 土壤中锶90的放射化学测定用标准试验方法

Because soil is an integrator and a reservoir of long-lived radionuclides, and serves as an intermediary in several pathways of potential exposure to humans, knowledge of the concentration of strontium-90 in soil is essential. A soil sampling and analysis program provides a direct means of determining the concentration and distribution of radionuclides in soil. A soil analysis program has the most significance for the preoperational monitoring program to establish baseline concentrations prior to the operation of a nuclear facility. Soil analysis, although useful in special cases involving unexpected releases, may not be able to assess small incremental releases.1.1 This test method is applicable to the determination of strontium-90 in soil at levels of detection dependent on count time, sample size, detector efficiency, background, and recovery.1.2 This test method is designed for the analysis of ten grams of soil, previously collected and treated as described in Practices C 998 and C 999. This test method may not be able to completely dissolve all soil matrices. The values stated in SI units are to be regarded as the standard. 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Radiochemical Determination of Strontium-90 in Soil

ASTM C1454-07 支持金属铀废核燃料自燃性分析的自燃性/易燃性测试用标准指南

1.1 This guide covers testing protocols for testing the pyrophoricity/combustibility characteristics of metallic uranium-based spent nuclear fuel (SNF). The testing will provide basic data for input into more detailed computer codes or analyses of thermal, chemical, and mechanical SNF responses. These analyses would support the engineered barrier system (EBS) design bases and safety assessment of extended interim storage facilities and final disposal in a geologic repository. The testing also could provide data related to licensing requirements for the design and operation of a monitored retrievable storage facility (MRS) or independent spent fuel storage installation (ISFSI).1.2 This guide describes testing of metallic uranium and metallic uranium-based SNF in support of transportation (in accordance with the requirements of 10CFR71), interim storage (in accordance with the requirements of 10CFR72), and geologic repository disposal (in accordance with the requirements of 10CFR60/63). The testing described herein is designed to provide basic data related to the evaluation of the pyrophoricity/combustibility characteristics of containers or waste packages containing metallic uranium SNF in support of safety analyses (SAR), or performance assessments (PA) of transport, storage, or disposal systems, or a combination thereof.1.3 Spent nuclear fuel that is not reprocessed must be emplaced in secure temporary interim storage as a step towards its final disposal in a geologic repository. In the United States, SNF, from both civilian commercial power reactors and defense nuclear materials production reactors, will be sent to interim storage, and subsequently, to deep geologic disposal. U.S. commercial SNF comes predominantly from light water reactors (LWRs) and is uranium dioxide-based, whereas U.S. Department of Energy (DOE) owned defense reactor SNF is in several different chemical forms, but predominantly (approximately 80 % by weight of uranium) consists of metallic uranium.1.4 Knowledge of the pyrophoricity/combustibility characteristics of the SNF is required to support licensing activities for extended interim storage and ultimate disposition in a geologic repository. These activities could include interim storage configuration safety analyses, conditioning treatment development, preclosure design basis event (DBE) analyses of the repository controlled area, and postclosure performance assessment of the EBS.1.5 Metallic uranium fuels are clad, generally with zirconium, aluminum, stainless steel, or magnesium alloy, to prevent corrosion of the fuel and to contain fission products. If the cladding is damaged and the metallic SNF is stored in water the consequent corrosion and swelling of the exposed uranium enhances the chemical reactivity of the SNF by further rupturing the cladding and creating uranium hydride particulates and/or inclusions in the uranium metal matrix. The condition of the metallic SNF will affect its behavior in transport, interim storage or repository emplacement, or both, and therefore, influence the engineering decisions in designing the pathway to disposal.1.6 Zircaloy spent fuel cladding has occasionally demonstrated pyrophoric behavior. This behavior often occurred on cladding pieces or particulate residues left after the chemical dissolution of metallic uranium or uranium dioxide during fuel reprocessing of commercial spent fuel and/or extraction of plutonium from defense reactor spent fuel. Although it is generally believed that zirconium is not as intrinsically prone to pyrophoric behavior as uranium or plutonium, it has in the past ignited after being sensitized during the chemical extraction process. Although this guide primarily addresses the pyrophoricity of the metallic uranium component of the spent fuel, some of the general principles involved could also apply to zirconium alloy spent fuel cladding.1.7 The interpretation of the test data de......

Standard Guide for Pyrophoricity/Combustibility Testing in Support of Pyrophoricity Analyses of Metallic Uranium Spent Nuclear Fuel

EJ/T 1214-2006 地浸砂岩型铀矿资源/储量估算指南

本标准规定了地浸砂岩型铀矿资源/储量估算原则、指标和参数的确定、估算方法的选择以及矿体圈定的原则，并对年度资源量估算和资源/储量估算的质量等提出了具体要求。 本标准适用于地浸砂岩型铀矿资源/储量的估算，也适用于地浸砂岩型铀矿资源/储量勘查报告的评审。

Guidebook on resources/reserves estimation for in-situ leaching sandstone type uranium deposits

EJ/T 1213-2006 铀矿地质勘查成果分类分级

本标准规定了铀矿地质勘查成果的分类、分级及其审定要求。 本标准适用于铀矿地质勘查各工作阶段的成果管理，也适用于铀矿勘查成果的验收和考核。

Classification and gradation of uranium resource prospecting and exploration outcomes

GJB 5838-2006 军用核材料实物保护准则

本标准规定了生产、使用、贮存和运输军用核材料的实物保护要求。 本标准适用于中华人民共和国境内受管制的军用核材料的实物保护，民用核材料的实物保护也可参照使用。

Criteria for physical protection of military nuclear material

GJB 5839-2006 军用核材料实物保护系统评价导则

本标准规定了评价生产、使用、贮存军用核材料固定场所实物保护系统的内容和方法。 本标准适用于军用核材料固定场所实物保护系统有效性评价和风险评价。对民用核材料、核设施的实物保护系统评价，可参照使用。

Guide for evaluation of physical protection system of military nuclear material

GJB 5840-2006 军用核材料衡算MUF评价准则

本标准规定了军用核材料衡算中MUF的评价方法。 本标准适用于军用核材料衡算中对MUF的评价，民用核材料衡算中对MUF的评价也可参照执行。

Guidance for MUF evaluation of military nuclear material accounting

GJB 3687A-2006 军用核材料术语

本标准规定了军用核材料及其相关领域的术语。 本标准适用于军用核材料生产、分析测试、衡算与控制、实物保护、视察、环境取样、保密及编写标准和技术文件、翻译文献及国内外技术交流等活动。

Terms for military nuclear material

NF M60-461:2006 核能.感应耦合等离子体源原子辐射光谱测定法(ICP-AES)测定钆燃料混合物和钆燃料丸中Gd2O3的含量

Nuclear energy - Determination of Gd2O3 content in gadolinium fuel blends and gadolinium fuel pellets by atomic emission spectrometry using an inductively coupled plasma source (ICP-AES).

NF M60-408*NF ISO 10981:2006 核燃料技术.预处理厂溶解器溶液中铀的测定.液相色谱法

Nuclear fuel technology - Determination of uranium in reprocessing-plant dissolver solution - Liquid chromatography method.

ASTM C1647-06 铀或钚材料中杂质检定用铀或钚或者两者的清除标准实施规程

This practice can be used to separate uranium or plutonium, or both, prior to the impurity analysis by various techniques. The removal of uranium and plutonium prior to quantification can improve the detection limits by minimizing the signal suppression caused by uranium or plutonium when using ICP techniques. Detection limits of ~1–10 part-per-billion (PPB) may be obtainable by matrix removal. Also, removal of the uranium and plutonium may allow the impurities analysis to be performed on a non-glove box enclosed instrument. Other test methods exist to determine impurities in uranium or plutonium. Test Method C 1517 is able to determine many impurities in uranium at detection levels of ~1–10 part-per-million (ppm) by DC-Arc Spectrometry. Test Method C 1287 is able to determine impurities in uranium at detection levels of ~100 ppb by ICP-MS. Test Method C 1432 provides an alternative technique to remove plutonium by ion exchange prior to analysis of the impurities by ICP-AES. This practice can be used to demonstrate compliance with nuclear fuel specifications, for example, Specifications C 753, C 757, C 776, C 787, C 788, and C 996.1.1 This practice covers instructions for using an extraction chromatography column method for the removal of plutonium or uranium, or both, from liquid or digested oxides or metals prior to impurity measurements. Quantification of impurities can be made by techniques such as inductively coupled plasma mass spectrometry (ICP-MS), inductively coupled plasma atomic emission spectrometry (ICP-AES) or atomic absorption spectrometry (AAS.)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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Practice for Removal of Uranium or Plutonium, or both, for Impurity Assay in Uranium or Plutonium Materials

ASTM C1476-06 感应耦合等离子体质谱法分析锝-99用尿的标准试验方法

Code of Federal Regulations, Title 10, 835.402 states that radiological workers who are likely to receive 100 mrem from intakes are required to be monitored for exposure. For the indirect bioassay for radiological workers exposed to nuclear material containing fission products, 99Tc must be measured in urine samples.1.1 This test method covers the determination of the concentration of technetium-99 in urine using inductively coupled plasma-mass spectrometry (ICP-MS). This test method can be used to support uranium enrichment and reclamation facility bioassay programs.1.2 The minimum detectable concentration for this test method, using a quadrupole ICP-MS, is approximately 1.0 ng/L (0.62 Bq/L).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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Analysis of Urine for Technetium-99 by Inductively Coupled Plasma-Mass Spectrometry