27.120.30 裂变物质 标准查询与下载
共找到 993 条与 裂变物质 相关的标准，共 67 页
Nuclear fuel technology -- Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination (ISO 16793:2018)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-07-14
- 实施
- 2021-07-14
Nuclear fuel technology -- Dissolution of plutonium dioxide-containing materials -- Part 1: Dissolution of plutonium dioxide powders (ISO 18256-1:2019)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-07-14
- 实施
- 2021-07-14
Nuclear fuel technology -- Dissolution of plutonium dioxide-containing materials -- Part 2: Dissolution of MOX pellets and powders (ISO 18256-2:2019)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-07-14
- 实施
- 2021-07-14
Safe transport of radioactive materials -- Leakage testing on packages (ISO 12807:2018)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-07-13
- 实施
- 2021-07-13
ISO 16424:2012 is applicable to the evaluation of the homogeneity of Gd distribution within gadolinium fuel blends, and the determination of the Gd2O3 content in sintered fuel pellets of Gd2O3+UO2 from 1 % to 10 %, by measurements of gadolinium (Gd) and uranium (U) elements using ICP-AES. After performing measurements of Gd and U elements using ICP-AES, if statistical methodology is additionally applied, homogeneity of Gd distribution within a Gd fuel pellet lot can also be evaluated. However, ISO 16424:2012 covers the statistical methodology only on a limited basis.
Nuclear energy — Evaluation of homogeneity of Gd distribution within gadolinium fuel blends and determination of Gd2O3 content in gadolinium fuel pellets by measurements of uranium and gadolinium elements
- ICS
- 27.120.30
- CCS
- 发布
- 2021-07-01
- 实施
ISO 22765:2016 describes the ceramographic procedure used to prepare sintered (U,Pu)O2 pellets for qualitative and quantitative examination of the pellet microstructure. The examinations are performed before and after thermal treatment or chemical etching. They allow - observation of any cracks, intra- and intergranular pores or inclusions, and - measurement of the grain size, porosity and plutonium homogeneity distribution. The mean grain diameter is measured by one of the classic methods: counting (intercept method), comparison with standard grids or typical images, etc.[2] The measurement of individual grain sizes requires uniform development of the microstructure over the entire specimen. The plutonium cluster and pore distribution and localization are generally analysed by automatic image analysis systems. The plutonium distribution is usually revealed by chemical etching but alpha-autoradiography can also be used. The first technique avoids the tendency for autoradiography to exaggerate the size of plutonium-rich clusters due to the distance the alpha particles travel away from the source.
Nuclear fuel technology — Sintered (U,Pu)O2 pellets — Guidance for ceramographic preparation for microstructure examination
- ICS
- 27.120.30
- CCS
- 发布
- 2021-07-01
- 实施
Le présent document fournit les éléments suivants :- les spécifications des cylindres pour le transport de l'hexafluorure d'uranium (UF6) afin d'assurer la compatibilité entre les différents utilisateurs ;- la description de la conception des cylindres, sans avoir pour objet le d
Nuclear energy - Packagings for the transport of uranium hexafluoride (UF6)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-06-12
- 实施
- 2021-06-12
1.1 This practice is applicable to sampling gaseous uranium hexafluoride (UF6) 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 UF6 for determination of uranium isotopic content for nuclear material safeguards and other applications. 1.3 The UF6 collected is converted to uranyl fluoride (UO2F2), allowing samples to be handled and categorized for transport under less stringent conditions than are required for UF6. 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.
Standard Practice for Sampling Gaseous Uranium Hexafluoride Using Zeolite in Single-Use Destructive Assay Sampler
- ICS
- 27.120.30
- CCS
- 发布
- 2021-06-01
- 实施
1.1 This guide is a compendium of Quality Measurement Practices for performing measurements of radioactive material using nondestructive assay (NDA) instruments. The primary purpose of the guide is to assist users in arriving at quality NDA results, that is, results that satisfy the end user’s needs. This is accomplished by providing an acceptable and uniform basis for the collection, analysis, comparison, and application of data. The recommendations are guidelines to achieving quality NDA measurements in most areas. 1.2 This guide applies to the use of NDA instrumentation for the measurement of nuclear materials by the observation of spontaneous or stimulated nuclear or atomic radiations, including photons, neutrons, or heat. Recommended calibration, operating, and assurance methods represent guiding principles based on current NDA technology. The diversity of industrywide nuclear materials measurement applications and instrumentation precludes discussion of specific measurement situations. As a result, compliance with practices recommended in this guide must be based on a thorough understanding of contributing variables and performance requirements of the specific measurement application. 1.3 Selection of the best instrument for a given measurement application and advice on the use of this instrument must be provided by a qualified NDA professional following guidance provided in Guide C1490. This guide is to be used as a reference, and to supplement the critical thinking, professional skill, expert judgment, and experimental test and verification needed to ensure that the instrumentation and methods have been properly implemented. 1.4 The intended audience for this guide includes but is not limited to Management, Auditor Support, NDA Qualified Instrument Operators, NDA Technical Specialists, and NDA Professionals. 1.5 The values stated in either SI units or inch-pound units are to be regarded separately as standard. The values stated in each system are not necessarily exact equivalents; therefore, to ensure conformance with the standard, each system shall be used independently of the other, and values from the two systems shall not be combined. 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.
Standard Guide for Making Quality Nondestructive Assay Measurements
- ICS
- 27.120.30
- CCS
- 发布
- 2021-06-01
- 实施
Uranium dioxide powder - Determination of apparent density and tap density (ISO 9161:2019)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-06-00
- 实施
- 2021-06-01
Nuclear fuel technology - Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry (ISO 8299:2019)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-06-00
- 实施
- 2021-06-01
Nuclear energy - Nuclear fuel technology - Determination of plutonium in nitric acid solutions by spectrophotometry (ISO 9463:2019)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-06-00
- 实施
- 2021-06-01
Nuclear fuel technology - Dissolution of plutonium dioxide-containing materials - Part 1: Dissolution of plutonium dioxide powders (ISO 18256-1:2019)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-06-00
- 实施
- 2021-06-01
Nuclear fuel technology - Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination (ISO 16793:2018)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-06-00
- 实施
- 2021-06-01
Nuclear fuel technology - Dissolution of plutonium dioxide-containing materials - Part 2: Dissolution of MOX pellets and powders (ISO 18256-2:2019)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-06-00
- 实施
- 2021-06-01
This document consists of safety related requirements for the planning and installing of storage facilities against radiation, fire and theft. The requirements correspond with radiation protection act and order so far radioactive material is concerned.
Storage and keeping of other radioactive materials - Requirements on protection against radiation, fire and theft to be met by storage facilities
- ICS
- 27.120.30
- CCS
- 发布
- 2021-05-00
- 实施
- 2021-05-01
Uranium dioxide powder - Determination of apparent density and tap density (ISO 9161:2019)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-04-30
- 实施
- 2021-04-30
Nuclear fuel technology - Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry (ISO 8299:2019)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-04-30
- 实施
- 2021-04-30
Nuclear fuel technology - Dissolution of plutonium dioxide-containing materials - Part 1: Dissolution of plutonium dioxide powders (ISO 18256-1:2019)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-04-30
- 实施
- 2021-04-30
Nuclear fuel technology - Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination (ISO 16793:2018)
- ICS
- 27.120.30
- CCS
- 发布
- 2021-04-30
- 实施
- 2021-04-30
