F08 标志、包装、运输、贮存 标准查询与下载



共找到 19 条与 标志、包装、运输、贮存 相关的标准,共 2

Safety technical code for storage facilities of uranium ore and uranium compounds

ICS
CCS
F08
发布
2013-09-01
实施
2013-09-01

本标准规定了一种用于放射性物质运输货包泄漏检验的气体泄漏检验法。 采用该方法可在设计、制造、装运前和定期检验等阶段对运输货包进行验证,以证明货包符合规定的包容要求。 本标准并未规定具体的气体泄漏检验程序,仅给出了进行各种气体泄漏检验方法的最低要求。

Safe transport of radioactive material. Leakage testing on packages

ICS
13.030.30
CCS
F08
发布
1998-02-23
实施
1998-11-01

本标准规定了放射性物质运输用包装的设计、采购、制造、试验、文件编制、使用和维修的质量保证基本要求。 本标准适用于与放射性物质运输包装的质量有关的所有活动和单位。

Quality assurance for packaging used in the transport of radioactive materials

ICS
27.120.30
CCS
F08
发布
1994-09-24
实施
1995-08-01

本标准规定了有关低、中水平放射性固体废物包装安全的设计、制造要求;放射性限值和表面污染限值:标志和标签及堆贮搬运操作要求等。本标准适用于各类核设施、核研究所及同位素生产和应用单位所产生的低、中水平放射性固体废物包装。 本标准不适用于放射性尾矿渣和废辐射源包装。

Standard of safety for low and intermediate-level solid radioactive wastes packages

ICS
13.300
CCS
F08
发布
1991-01-28
实施
1991-12-01

本标准规定了与放射性物质运输有关的所有操作和条件,既包括包装的设计、制造和维护,又包括货包的准备、托运、装卸、载运和中途贮存,货包最终抵达地的验收,以及载运和贮存情况下遇到的正常和事故条件。 本标准适用于放射性物质的陆地、水上和空中任何运输方式。

Regulations for the safe transport of radioactive material

ICS
13.300
CCS
F08
发布
1989-10-20
实施
1990-07-01

Fuel assembly identification for nuclear power reactors

ICS
27.120.30
CCS
F08
发布
2016-10
实施

Practice for Thermal Qualification of Type B Packages for Radioactive Material

ICS
13.300;55.040
CCS
F08
发布
2013
实施

Guidance for Packaging Type A Quantities of Radioactive Materials

ICS
27.120.30
CCS
F08
发布
2013
实施

The major objective of this practice is to provide a common reference document for both applicants and certification authorities on the accepted practices for accomplishing package thermal qualification. Details and methods for accomplishing qualification are described in this document in more specific detail than available in the regulations. Methods that have been shown by experience to lead to successful qualification are emphasized. Possible problems and pitfalls that lead to unsatisfactory results are also described. The work described in this standard practice shall be done under a quality assurance program that is accepted by the regulatory authority that certifies the package for use. For packages certified in the United States, 10 CFR 71 Subpart H shall be used as the basis for the quality assurance (QA) program, while for international certification, ISO 9000 usually defines the appropriate program. The quality assurance program shall be in place and functioning prior to the initiation of any physical or analytical testing activities and prior to submittal of any information to the certifying authority. The unit system (SI metric or English) used for thermal qualification shall be agreed upon prior to submission of information to the certification authority. If SI units are to be standard, then use IEEE/ASTM SI-10. Additional units given in parentheses are for information purposes only.1.1 This practice defines detailed methods for thermal qualification of “Type B” radioactive materials packages under Title 10, Code of Federal Regulations, Part 71 (10CFR71) in the United States or, under International Atomic Energy Agency Regulation TS-R-1. Under these regulations, packages transporting what are designated to be Type B quantities of radioactive material shall be demonstrated to be capable of withstanding a sequence of hypothetical accidents without significant release of contents. 1.2 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. 1.3 This standard is used to measure and describe the response of materials, products, or assemblies to heat and flame under controlled conditions, but does not by itself incorporate all factors required for fire hazard or fire risk assessment of the materials, products, or assemblies under actual fire conditions.

Standard Practice for Thermal Qualification of Type B Packages for Radioactive Material

ICS
55.040 (Packaging materials and accessories)
CCS
F08
发布
2008
实施

This standard provides nuclear criticality safety criteria for the handling, storage, and transportation of LWR fuel rods and units outside reactor cores.

Criticality Safety Criteria for the Handling, Storage and Transportation of LWR Fuel Outside Reactors

ICS
27.120.30
CCS
F08
发布
2004
实施

1.1 Part of the total inventory of commercial spent nuclear fuel (SNF) is stored in dry cask storage systems (DCSS) under licenses granted by the U.S. Nuclear Regulatory Commission (NRC). The purpose of this guide is to provide information to assist in supporting the renewal of these licenses, safely and without removal of the SNF from its licensed confinement, for periods beyond those governed by the term of the original license. This guide provides information on materials behavior under conditions that may be important to safety evaluations for the extended service of the renewal period. This guide is written for DCSS containing light water reactor (LWR) fuel that is clad in zirconium alloy material and stored in accordance with the Code of Federal Regulations (CFR), at an independent spent-fuel storage installation (ISFSI). The components of an ISFSI, addressed in this document, include the commercial SNF, canister, cask, and all parts of the storage installation including the ISFSI pad. The language of this guide is based, in part, on the requirements for a dry SNF storage license that is granted, by the U.S. Nuclear Regulatory Commission (NRC), for up to 20 years. Although government regulations may differ for various nations, the guidance on materials properties and behavior given here is expected to have broad applicability.1.2 This guide addresses many of the factors affecting the time-dependent behavior of materials under ISFSI service [10 CFR Part 72.42]. These factors are those regarded to be important to performance, in license extension, beyond the currently licensed 20-year period. Examples of these factors are given in this guide and they include materials alterations or environmental conditions for components of an ISFSI system that, over time, could have significance related to safety. For purposes of this guide, a license period of an additional 20 to 80 years is assumed.1.3 This guide addresses the determination of the conditions of the spent fuel and storage cask materials at the end of the initial 20-year license period as the result of normal events and conditions. However, the guide also addresses the analysis of potential spent fuel and cask materials degradation as the result of off-normal, and accident-level events and conditions that may occur during any period.1.4 This guide provides information on materials behavior to support continuing compliance with the safety criteria, which are part of the regulatory basis, for licensed storage of SNF at an ISFSI. The safety functions addressed and discussed in this standard guide include thermal performance, radiological protection, confinement, sub-criticality, and retrievability. The regulatory basis includes 10 CFR Part 72 and supporting regulatory guides of the U.S. Nuclear Regulatory Commission. The requirements set forth in these documents indicate that the following items were considered in the original licensing decisions: properties of materials, design considerations for normal and off-normal service, operational and natural events, and the bases for the original calculations. These items may require reconsideration of the safety-related arguments that demonstrate how the systems continue to satisfy the regulatory requirements. Further, to ensure continued safe operation, the performance of materials must be justified in relation to the effects of time, temperature, radiation field, and environmental conditions of normal and off-normal service. Arguments for long-term performance must account for materials alterations (especially degradations) that are expected during the service periods, which include the periods of the initial license and of the license renewal. This guide pertains only to structures, systems, and components important to safety during extended storage period and during retrieval functions, including transport and transfer operations. Materials information that pertains to safety functions, inclu......

Standard Guide for Evaluation of Materials Used in Extended Service of Interim Spent Nuclear Fuel Dry Storage Systems

ICS
27.120.01 (Nuclear energy in general)
CCS
F08
发布
2003
实施

1.1 Part of the total inventory of commercial spent nuclear fuel (SNF) is stored in dry cask storage systems (DCSS) under licenses granted by the U.S. Nuclear Regulatory Commission (NRC). The purpose of this guide is to provide information to assist in supporting the renewal of these licenses, safely and without removal of the SNF from its licensed confinement, for periods beyond those governed by the term of the original license. This guide provides information on materials behavior under conditions that may be important to safety evaluations for the extended service of the renewal period. This guide is written for DCSS containing light water reactor (LWR) fuel that is clad in zirconium alloy material and stored in accordance with the Code of Federal Regulations (CFR), at an independent spent-fuel storage installation (ISFSI). The components of an ISFSI, addressed in this document, include the commercial SNF, canister, cask, and all parts of the storage installation including the ISFSI pad. The language of this guide is based, in part, on the requirements for a dry SNF storage license that is granted, by the U.S. Nuclear Regulatory Commission (NRC), for up to 20 years. Although government regulations may differ for various nations, the guidance on materials properties and behavior given here is expected to have broad applicability.1.2 This guide addresses many of the factors affecting the time-dependent behavior of materials under ISFSI service [10 CFR Part 72.42]. These factors are those regarded to be important to performance, in license extension, beyond the currently licensed 20-year period. Examples of these factors are given in this guide and they include materials alterations or environmental conditions for components of an ISFSI system that, over time, could have significance related to safety. For purposes of this guide, a license period of an additional 20 to 80 years is assumed.1.3 This guide addresses the determination of the conditions of the spent fuel and storage cask materials at the end of the initial 20-year license period as the result of normal events and conditions. However, the guide also addresses the analysis of potential spent fuel and cask materials degradation as the result of off-normal, and accident-level events and conditions that may occur during any period.1.4 This guide provides information on materials behavior to support continuing compliance with the safety criteria, which are part of the regulatory basis, for licensed storage of SNF at an ISFSI. The safety functions addressed and discussed in this standard guide include thermal performance, radiological protection, confinement, sub-criticality, and retrievability. The regulatory basis includes 10 CFR Part 72 and supporting regulatory guides of the U.S. Nuclear Regulatory Commission. The requirements set forth in these documents indicate that the following items were considered in the original licensing decisions: properties of materials, design considerations for normal and off-normal service, operational and natural events, and the bases for the original calculations. These items may require reconsideration of the safety-related arguments that demonstrate how the systems continue to satisfy the regulatory requirements. Further, to ensure continued safe operation, the performance of materials must be justified in relation to the effects of time, temperature, radiation field, and environmental conditions of normal and off-normal service. Arguments for long-term performance must account for materials alterations (especially degradations) that are expected during the service periods, which include the periods of the initial license and of the license renewal. This guide pertains only to structures, systems, and components important to safety during extended storage period and during retrieval functions, including transport and transfer operations. Materials information that pertains to safety functions, inclu......

Standard Guide for Evaluation of Materials Used in Extended Service of Interim Spent Nuclear Fuel Dry Storage Systems

ICS
27.120.01 (Nuclear energy in general)
CCS
F08
发布
2003
实施

本标准规定了用能产品能耗标识的项目、形式和要求。本标准适用于用能产品的能耗标识。

General Rules for Energy Consumption Labeling of Energy-Using Products

ICS
27.01
CCS
F08
发布
1999-12-1
实施
2000-3-1

本标准规定了发货单位或个人向审管部门提交的放射性物质运输安全分析报告编写的标准格式和主要内容。 本标准适用于乏燃料运输以及在运输过程中潜在风险较大,审管部门认为必须进行安全分析的放射性物质货包的陆地、水上和空中任何方式的运输。

Standard format and content of radioactive material transport safety analysis report

ICS
27.010
CCS
F08
发布
1994-07-18
实施
1994-12-01

本标准规定了放射性物质运输环境影响报告书的标准格式和主要内容。 本标准适用于放射性物质B型货包的陆地、水上和空中运输方式。

Standard format and content of environmental impact report for radioactive material transportation

ICS
27.010
CCS
F08
发布
1994-03-07
实施
1994-08-01

本标准规定了核电厂物项包装、运输、装卸、接收、贮存和维护的技术要求和方法。 本标准适用于核电厂物项从生产制造厂对物项检验合格后到物项出库期间的包装、运输、装卸、接收、贮存和维护。

Requirements for packaging, transportation, handling, receiving, storage and maintenance of nuclear power plant items

ICS
CCS
F08
发布
1991-10-11
实施
1992-03-01

Fuel assembly identification for nuclear power reactors

ICS
27.120.30
CCS
F08
发布
1988-03
实施

Nuclear energy.radioactive materials.packagings-test for contents leakage.

ICS
13.280;13.300;27.120.01
CCS
F08
发布
1977-12-01
实施
1977-11-25

Guidance on design, design approval, competent authority certification, manufacture and use. Supplements and amplifies IAEA Safety Series No. 6 (1973).

Guide to the design, testing and use of packaging for the safe transport of radioactive materials

ICS
13.280;27.120.30
CCS
F08
发布
1976-01-30
实施
1976-01-30



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