GB 50807-2013 鈾礦石和鈾化合物貯存設(shè)施安全技術(shù)規(guī)范

本規(guī)范適用于鈾礦石和鈾化合物固定貯存設(shè)施的設(shè)計(jì)、施工、驗(yàn)收及運(yùn)行維護(hù)。

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

GB/T 17230-1998 放射性物質(zhì)安全運(yùn)輸 貨包的泄漏檢驗(yàn)

本標(biāo)準(zhǔn)規(guī)定了一種用于放射性物質(zhì)運(yùn)輸貨包泄漏檢驗(yàn)的氣體泄漏檢驗(yàn)法。 采用該方法可在設(shè)計(jì)、制造、裝運(yùn)前和定期檢驗(yàn)等階段對(duì)運(yùn)輸貨包進(jìn)行驗(yàn)證，以證明貨包符合規(guī)定的包容要求。 本標(biāo)準(zhǔn)并未規(guī)定具體的氣體泄漏檢驗(yàn)程序，僅給出了進(jìn)行各種氣體泄漏檢驗(yàn)方法的最低要求。

Safe transport of radioactive material. Leakage testing on packages

GB 15219-1994 放射性物質(zhì)運(yùn)輸包裝質(zhì)量保證

本標(biāo)準(zhǔn)規(guī)定了放射性物質(zhì)運(yùn)輸用包裝的設(shè)計(jì)、采購、制造、試驗(yàn)、文件編制、使用和維修的質(zhì)量保證基本要求。 本標(biāo)準(zhǔn)適用于與放射性物質(zhì)運(yùn)輸包裝的質(zhì)量有關(guān)的所有活動(dòng)和單位。

Quality assurance for packaging used in the transport of radioactive materials

GB 12711-1991 低、中水平放射性固體廢物包裝安全標(biāo)準(zhǔn)

本標(biāo)準(zhǔn)規(guī)定了有關(guān)低、中水平放射性固體廢物包裝安全的設(shè)計(jì)、制造要求；放射性限值和表面污染限值：標(biāo)志和標(biāo)簽及堆貯搬運(yùn)操作要求等。本標(biāo)準(zhǔn)適用于各類核設(shè)施、核研究所及同位素生產(chǎn)和應(yīng)用單位所產(chǎn)生的低、中水平放射性固體廢物包裝。 本標(biāo)準(zhǔn)不適用于放射性尾礦渣和廢輻射源包裝。

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

GB 11806-1989 放射性物質(zhì)安全運(yùn)輸規(guī)定

本標(biāo)準(zhǔn)規(guī)定了與放射性物質(zhì)運(yùn)輸有關(guān)的所有操作和條件，既包括包裝的設(shè)計(jì)、制造和維護(hù)，又包括貨包的準(zhǔn)備、托運(yùn)、裝卸、載運(yùn)和中途貯存，貨包最終抵達(dá)地的驗(yàn)收，以及載運(yùn)和貯存情況下遇到的正常和事故條件。 本標(biāo)準(zhǔn)適用于放射性物質(zhì)的陸地、水上和空中任何運(yùn)輸方式。

Regulations for the safe transport of radioactive material

DIN 25433:2016 核動(dòng)力反應(yīng)堆的燃料組件標(biāo)識(shí)

Fuel assembly identification for nuclear power reactors

ANSI/ASTM E2230:2013 放射性材料用B型包裝件的熱合格鑒定用規(guī)程

Practice for Thermal Qualification of Type B Packages for Radioactive Material

ANSI N14.7-2013 放射性材料定量類型A包裝導(dǎo)則

Guidance for Packaging Type A Quantities of Radioactive Materials

ASTM E2230-08 放射性材料的“B ” 型包裝熱限制的標(biāo)準(zhǔn)實(shí)施規(guī)程

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

ANSI/ANS 8.17-2004 反應(yīng)堆外部的輕水反應(yīng)堆燃料的搬運(yùn),貯藏和運(yùn)輸臨界安全性準(zhǔn)則

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

ASTM C1562-03 長期用臨時(shí)核燃料干燥儲(chǔ)藏系統(tǒng)的材料評(píng)估標(biāo)準(zhǔn)指南

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

ASTM C1562-03e1 長期用臨時(shí)核燃料干燥儲(chǔ)藏系統(tǒng)的材料評(píng)估標(biāo)準(zhǔn)指南

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

DB11/ 114-1999 用能產(chǎn)品能耗標(biāo)識(shí)通則

本標(biāo)準(zhǔn)規(guī)定了用能產(chǎn)品能耗標(biāo)識(shí)的項(xiàng)目、形式和要求。本標(biāo)準(zhǔn)適用于用能產(chǎn)品的能耗標(biāo)識(shí)。

General Rules for Energy Consumption Labeling of Energy-Using Products

EJ/T 839-1994 放射性物質(zhì)運(yùn)輸安全分析報(bào)告的標(biāo)準(zhǔn)格式和內(nèi)容

本標(biāo)準(zhǔn)規(guī)定了發(fā)貨單位或個(gè)人向?qū)徆懿块T提交的放射性物質(zhì)運(yùn)輸安全分析報(bào)告編寫的標(biāo)準(zhǔn)格式和主要內(nèi)容。 本標(biāo)準(zhǔn)適用于乏燃料運(yùn)輸以及在運(yùn)輸過程中潛在風(fēng)險(xiǎn)較大，審管部門認(rèn)為必須進(jìn)行安全分析的放射性物質(zhì)貨包的陸地、水上和空中任何方式的運(yùn)輸。

Standard format and content of radioactive material transport safety analysis report

EJ/T 818-1994 放射性物質(zhì)運(yùn)輸環(huán)境影響報(bào)告書的標(biāo)準(zhǔn)格式和內(nèi)容

本標(biāo)準(zhǔn)規(guī)定了放射性物質(zhì)運(yùn)輸環(huán)境影響報(bào)告書的標(biāo)準(zhǔn)格式和主要內(nèi)容。 本標(biāo)準(zhǔn)適用于放射性物質(zhì)B型貨包的陸地、水上和空中運(yùn)輸方式。

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

EJ/T 564-1991 核電廠物項(xiàng)包裝、運(yùn)輸、裝卸、接收、貯存和維護(hù)要求

本標(biāo)準(zhǔn)規(guī)定了核電廠物項(xiàng)包裝、運(yùn)輸、裝卸、接收、貯存和維護(hù)的技術(shù)要求和方法。 本標(biāo)準(zhǔn)適用于核電廠物項(xiàng)從生產(chǎn)制造廠對(duì)物項(xiàng)檢驗(yàn)合格后到物項(xiàng)出庫期間的包裝、運(yùn)輸、裝卸、接收、貯存和維護(hù)。

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

DIN 25433:1988 核動(dòng)力反應(yīng)堆的燃料組件標(biāo)識(shí)

Fuel assembly identification for nuclear power reactors

NF M60-301:1977 核能.放射性材料.內(nèi)裝物泄漏用包裝試驗(yàn)

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

BS 3895:1976 放射性物質(zhì)安全運(yùn)輸包裝的設(shè)計(jì)、試驗(yàn)及使用指南

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