核能工程_国内外标准网文献检索下载

1.[标准] 核电厂运行许可证延续评估通用要求

发布单位：
中国-国家标准(CN-GB)

标准状态：
现行

标准号：
GB/T 43797-2024

发布时间：
2024-03-15

中标分类：
F63 动力堆

国标分类：
27.120.20 核电站、安全

实施时间：
2024-07-01

摘要：本文件规定了核电厂运行许可证有效期限延续评估的流程、安全论证基准确定、电厂整体评估、时限老化分析、环境影响评估、安全改进及承诺、最终安全分析报告增补和修改、运行许可证延续申请文件编制以及延续运行安全基准更新等要求。本文件适用于核电厂运行许可证有效期延续（简称“运行许可证延续”)评估活动，其他核设施参照使用。

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2.[标准] 核电厂可靠性、可用性、可维修性和安全性管理规范

发布单位：
中国-国家标准(CN-GB)

标准状态：
现行

标准号：
GB/T 44080-2024

发布时间：
2024-05-28

中标分类：
F63 动力堆

国标分类：
27.120.20 核电站、安全

实施时间：
2024-05-28

摘要：本文件规定了在核电厂全生命周期中实施可靠性、可用性、可维修性和安全性连贯的全过程管理的方法和要求。
本文件适用于核电厂全生命周期各阶段的RAMS管理。

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3.[标准] 核电厂管道冰塞冷冻隔离

发布单位：
中国-国家标准(CN-GB)

标准状态：
现行

标准号：
GB/T 44389-2024

发布时间：
2024-08-23

中标分类：
F65 核电厂核岛

国标分类：
27.120.10 反应堆工程

实施时间：
2024-08-23

摘要：本文件规定了核电厂冰塞冷冻隔离的施工前准备、冰塞施工、冰塞质量保证和冰塞记录与报告等要求。
本文件适用于核电厂金属管道上以液氮或干冰等作为制冷剂（低温介质)冰塞冷冻隔离技术。
注：冷冻介质通常是水或水的混合物（例如硼酸混合物)。

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4.[标准] 重水同位素纯度的测定　傅里叶变换红外光谱法

发布单位：
中国-国家标准(CN-GB)

标准状态：
现行

标准号：
GB/T 44647-2024

发布时间：
2024-09-29

中标分类：
F60 核反应堆综合

国标分类：
27.120.10 反应堆工程

实施时间：
2024-09-29

摘要：本文件描述了使用傅里叶变换红外光谱法测定全范围重水同位素纯度的方法。
本文件适用于重水堆核电厂、研究堆、重水生产厂家和重水相关领域的重水同位素纯度的测定。

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5.[标准] 压水堆核燃料组件制造工艺和产品合格性鉴定要求

发布单位：
中国-国家标准(CN-GB)

标准状态：
现行

标准号：
GB/T 44771-2024

发布时间：
2024-10-26

中标分类：
F49 核材料、核燃料生产、处理设备和设施

国标分类：
27.120.99 有关核能的其他标准

实施时间：
2025-02-01

摘要：本文件规定了压水堆核燃料组件制造工艺和产品合格性鉴定的要求。
本文件适用于压水堆核燃料组件制造工艺和产品合格性鉴定。其他类型的核燃料组件制造工艺和产品合格性鉴定参照执行。

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6.[标准] 压水堆核燃料元件制造及包装、贮存、运输过程接触材料控制要求

发布单位：
中国-国家标准(CN-GB)

标准状态：
现行

标准号：
GB/T 44772-2024

发布时间：
2024-10-26

中标分类：
F49 核材料、核燃料生产、处理设备和设施

国标分类：
27.120.99 有关核能的其他标准

实施时间：
2025-02-01

摘要：本文件规定了压水堆核燃料元件制造及包装、贮存和运输过程中接触材料的分类、要求及控制要求。
本文件适用于压水堆核燃料组件、相关组件制造及包装、贮存和运输过程中的接触材料的控制，原材料制造及其包装、贮存和运输过程中的接触材料的控制可参照执行。

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7.[标准] 固体闪烁体性能测量方法

发布单位：
中国-国家标准(CN-GB)

标准状态：
现行

标准号：
GB/T 13181-2024

发布时间：
2024-05-28

中标分类：
F80 核仪器与核探测器综合

国标分类：
27.120.01 核能综合

实施时间：
2024-12-01

摘要：本文件描述了闪烁体的相对光输出、相对能量转换效率、α-β比、固有脉冲幅度分辨率、闪烁光衰减长度、发射光谱、时间特性、辐照硬度、自身放射性水平、β-γ比和n-γ比、温度效应、闪烁体阵列的不均匀性、光串扰等的测量方法。本文件适用于常用固体闪烁体的性能测量。

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8.[标准] 核电蒸汽发生器用干燥器

发布单位：
中国-团体标准(CN-TUANTI)

标准状态：
现行

标准号：
T/ZS 0593-2024

发布时间：
2024-02-06

中标分类：
F 能源、核技术

国标分类：
27.120.99 核能工程 - 有关核能的其他标准

实施时间：
2024-02-06

摘要：主要技术内容:前言1 范围2 规范性引用文件3 术语和定义4 基本要求5 技术要求6 检验方法7 检验规则8 标志、包装、运输与储存9 质量承诺
9.[标准] Standard Terminology Relating to Nuclear Materials

核材料相关标准术语

发布单位：
美国-美国材料与试验协会(US-ASTM)

标准状态：
现行

标准号：
ASTM C859-24

发布时间：
2024-01-01

中标分类：
-

国标分类：
01.040.27 词汇 - 能源和热传导工程 (词汇)

27.120.30 核能工程 - 裂变物质

实施时间：

摘要： 1.1This terminology standard covers terms, definitions, descriptions of terms, nomenclature, and explanations of acronyms and symbols specifically associated with standards under the jurisdiction of Committee C26 on Nuclear Fuel Cycle. The content of this terminology standard may also be applicable to documents not under the jurisdiction of Committee C26, in which case this terminology standard may be referenced in those documents.1.2While subcommittees within Committee C26 are free to only provide terms and definitions within individual standards, each subcommittee may request the addition of utilized terms and definitions to this terminology standard if it believes that such serves the broader interest of Committee C26 and the nuclear fuel cycle profession. Therefore, terms and definitions proposed for inclusion in TerminologyC859need not be used in more than one committee standard before being considered.1.3In general, technical terms that are defined in common dictionaries would not also be defined in this terminology standard unless there is a need to emphasize a specific definition in making appropriate use of a Committee C26 standard.1.4Subcommittee C26.10 (Nondestructive Assay) also has a terminology standard applicable to its standards: TerminologyC1673.1.5This 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.
10.[标准] Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution

六氟化铀和硝酸铀溶液中裂变和衰变产物的伽马能发射的标准试验方法

发布单位：
美国-美国材料与试验协会(US-ASTM)

标准状态：
现行

标准号：
ASTM C1295-24

发布时间：
2024-01-15

中标分类：
-

国标分类：
27.120.30 核能工程 - 裂变物质

实施时间：

摘要： 1.1This test method covers the measurement of gamma energy emitted from fission products in uranium hexafluoride (UF6) and uranyl nitrate solution. This test method may also be used to measure the concentration of some uranium decay products. It is intended to provide a method for demonstrating compliance with UF6SpecificationsC787andC996, uranyl nitrate SpecificationC788, and uranium ore concentrate SpecificationC967.1.2The lower limit of detection is estimated at 5000 MeV Bq/kg (MeV kg-1/s-1) of uranium and is the square root of the sum of the squares of the individual reporting limits of the nuclides to be measured. The limit of detection was determined on a pure, aged natural uranium (ANU) solution. The value is dependent upon the detector efficiency and background that can be achieved.1.3The fission product nuclides to be measured are106Ru/106Rh,103Ru,137Cs,144Ce,144Pr,141Ce,95Zr,95Nb, and125Sb. Among the uranium decay product nuclides that may be measured is231Pa. Other gamma energy-emitting fission and uranium decay nuclides present in the spectrum at detectable levels should be identified and quantified as required by the data quality objectives.1.4The values stated in SI units are to be regarded as standard. Additionally, the non-SI units of kiloelectron volts and megaelectron volts are to be regarded as standard. No other units of measurement are included in this standard.1.5This 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.1.6This 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. ====== Significance And Use ======5.1Specific gamma-ray emitting radionuclides in UF6are identified and quantified using a high-resolution gamma-ray energy analysis system, which includes a high-resolution germanium detector. This test method shall be used to meet the health and safety specifications ofC787,C788, andC996regarding applicable fission products in reprocessed uranium solutions. This test method may also be used to provide information to parties such as conversion facilities on the level of uranium decay products in such materials. Pa-231 is a specific uranium decay product that may be present in uranium ore concentrate and is amenable to analysis by gamma spectrometry.
11.[标准] Design of nuclear power plants against seismic events — Part 6: Post-seismic measures

核电站抗震设计第6部分:地震后措施

发布单位：
国际组织-国际标准化组织(IX-ISO)

标准状态：
现行

标准号：
ISO 4917-6:2024

发布时间：
2024-02-27

中标分类：
-

国标分类：
91.120.25 建筑物的防护 - 地震和防振

27.120.20 核能工程 - 核电站、安全

实施时间：

摘要： This document applies to nuclear power plants with water cooled reactors.This document does not apply to earthquakes stronger than the design basis earthquake.This document specifies guidance on the actions to be taken in preparation for and following an earthquake at a nuclear power plant. This document is intended to be used as a guideline for decision making regarding continued operation, shutdown and restart of the nuclear power plant after an earthquake. It can also be used to assist operating organizations in the preparation and implementation of an overall pre- and post-earthquake action programme for dealing with situations in accordance with the level of seismic ground motion experienced at the site, and the seismic design level of the plant.
12.[标准] Design of nuclear power plants against seismic events — Part 1: Principles

核电站抗震设计第1部分:原理

发布单位：
国际组织-国际标准化组织(IX-ISO)

标准状态：
现行

标准号：
ISO 4917-1:2024

发布时间：
2024-02-22

中标分类：
-

国标分类：
91.120.25 建筑物的防护 - 地震和防振

27.120.20 核能工程 - 核电站、安全

实施时间：

摘要： This document applies to nuclear power plants with water cooled reactors and, in particular, to the design of components and civil structures against seismic events in order to meet the safety objectives. For other nuclear facilities the applicability of the document is checked in advance, before it might be applied correspondingly. Seismic isolation is not adressed in the series of ISO 4917.The following safety objectives are defined in order to ensure the protection of people and the environment against radiation risks:a)？controlling reactivity;b)？cooling fuel assemblies;c)？confining radioactive substances;d)？limiting radiation exposure.
13.[标准] Design of nuclear power plants against seismic events — Part 3: Civil structures

核电站抗震设计第3部分:民用结构

发布单位：
国际组织-国际标准化组织(IX-ISO)

标准状态：
现行

标准号：
ISO 4917-3:2024

发布时间：
2024-02-22

中标分类：
-

国标分类：
91.120.25 建筑物的防护 - 地震和防振

27.120.20 核能工程 - 核电站、安全

实施时间：

摘要： This document applies to civil structures of nuclear power plants with water cooled reactors in order to achieve the safety objectives given in ISO？4917-1. For other nuclear facilities the applicability of the document needs to be checked in advance, before it might be applied correspondingly.This document specifies the requirements for civil structures for the verification of their load-bearing capacity in case of a seismic event. Additionally, requirements are specified pertaining to the verification of the serviceability of civil structures as far as necessary for maintaining their safety-related function in case of a seismic event (e.g. deformation and crack-width limitations).This document will be applied under the presumption that the geology and tectonics of the plant site have been investigated with special emphasis on the existence of active geological faults and lasting geological ground displacements, and that the site has been deemed suitable for a nuclear installation.To achieve these goals, this document deals with the requirements specific to the seismic design of civil structures above and beyond their conventional design. The basic requirements of these precautionary measures are dealt with in ISO？4917-1.This document does not apply to cranes, to detachment devices for lifting equipment nor to the supporting and mounting constructions of components.This document is independent of national standards. Recommendations, given in Annex？A, are mainly based on the KTA Design-Philosophy and European standards. Alternatively other equivalent standards or regulations can be used in case the general requirements given in this document can be met.NOTE？The term civil structures as used in this document comprise buildings and structural members made of reinforced concrete, pre-stressed concrete, steel, as well as steel composite structures and masonry. Among others, these include the containment, crane runways, platforms, fastening constructions and canals.
14.[标准] Design of nuclear power plants against seismic events — Part 4: Components

核电站抗震设计第4部分:部件

发布单位：
国际组织-国际标准化组织(IX-ISO)

标准状态：
现行

标准号：
ISO 4917-4:2024

发布时间：
2024-03-07

中标分类：
-

国标分类：
91.120.25 建筑物的防护 - 地震和防振

27.120.20 核能工程 - 核电站、安全

实施时间：

摘要： This document applies to nuclear power plants with water cooled reactors. For other nuclear facilities check the applicability of the document in advance, before it might be applied correspondingly.This document specifies the requirements for the earthquake safety of components. The operation-specific safety-related requirements for each component, e.g. load-bearing capacity (stability), integrity and functionality (see 4.1) are not the subject of this document. With regard to analysing the mechanical behaviour of the individual components and verifying the fulfillment of their safety related functions, additionally, the respective component-specific standards need to be consulted.In this document, the term "mechanical components" refers to components such as vessels, heat exchangers, pumps, valves, lifting gear, distribution systems and pipe lines including their support structures in as far as these components are not considered to be civil structures in accordance with ISO？4917-3. Liners, crane runways, platforms and scaffoldings are not considered as being part of these mechanical components.In this document, the term electrical components refers to the combination of electrical devices including all electrical connections and their support structures (e.g. cabinets, frames, consoles, brackets, suspensions or supports).Supplementary to this document the seismic qualification of electrical components is reported in IEC/IEEE？60980-344.NOTE？This document is independent of national standards. Recommendations, given in Annex？A, are mainly based on the Eurocodes-Design-Philosophy and European Standards. Alternatively other equivalent standards or regulations can be used in case the general requirements given in this document together with Annex？A can be met.
15.[标准] 直流蒸发器核电机组水汽回路清洁控制技术要求

发布单位：
中国-行业标准-能源(CN-NB)

标准状态：
未生效

标准号：
NB/T 11297-2023

发布时间：
2023-10-11

中标分类：
F60/69 能源、核技术 - 核反应堆

国标分类：
27.120.01 核能工程 - 核能综合

实施时间：
2024-04-11

摘要：本文件规定了直流蒸发器核电机组水汽回路清洁控制的总体要求、各阶段清洁控制措施、蒸发器吹扫、水汽回路化学清洗及整体冲洗的技术要求。本文件适用于建设阶段的直流蒸发器核电机组
16.[标准] 核电厂常规岛与辅助配套设施可靠性数据管理导则

发布单位：
中国-行业标准-能源(CN-NB)

标准状态：
未生效

标准号：
NB/T 25018-2023

发布时间：
2023-10-11

中标分类：
F83 能源、核技术 - 核仪器与核探测器 - 反应堆、核电厂安全配电设备

国标分类：
27.120.20 核能工程 - 核电站、安全

实施时间：
2024-04-11

摘要：本标准规定了核电厂常规岛与辅助配套设施可靠性数据管理的相关内容。本标准适用于核电厂常规岛与辅助配套设施可靠性数据管理的实施
17.[标准] 核电厂汽轮机数字电液控制系统维修导则

发布单位：
中国-行业标准-能源(CN-NB)

标准状态：
未生效

标准号：
NB/T 11296-2023

发布时间：
2023-10-11

中标分类：
K54 电工 - 发电用动力设备 - 汽轮机及其辅助设备

国标分类：
27.120.20 核能工程 - 核电站、安全

实施时间：
2024-04-11

摘要：本文件规定了核电厂汽轮机数字电液控制系统的维修策略要求，包括巡检、定期试验与检查、定期更换、维修技术要求。本文件适用于核电厂商业运行阶段的汽轮机数字电液控制系统，不包含液压油子系统及其他就地设备。其它动力源发电厂可参照执行
18.[标准] 压水堆核电厂常规岛压力管道监督管理导则

发布单位：
中国-行业标准-能源(CN-NB)

标准状态：
现行

标准号：
NB／T 11234-2023

发布时间：
2023-05-26

中标分类：
F01 能源、核技术 - 能源、核技术综合 - 技术管理

国标分类：
27.120 能源和热传导工程 - 核能工程

实施时间：
2023-11-26

摘要：本文件规定了压水堆核电厂常规岛（以下简称常规岛）压力管道监督管理范围、监督管理体系、监督管理方式、日常巡检、压力管道定期检查、支承定期检查、安全阀和仪表定期校验检定以及管理优化。本文件适用于压水堆核电厂常规岛，电厂辅助设施区域管道的监督管理可参照执行
19.[标准] 核电厂用玻璃纤维增强塑料外包覆钢筋混凝土管道技术规程

发布单位：
中国-行业标准-能源(CN-NB)

标准状态：
未生效

标准号：
NB/T 11295-2023

发布时间：
2023-10-11

中标分类：
F00 能源、核技术 - 能源、核技术综合 - 标准化、质量管理

国标分类：
27.120.99 核能工程 - 有关核能的其他标准

实施时间：
2024-04-11

摘要：本文件规定了核电厂用埋地玻璃纤维增强塑料外包覆钢筋混凝土管道技术规程的术语和定义、材料、设计、制造、技术要求及试验方法、工程验收文件等基本技术要求。本文件适用输送介质温度为-5℃～60℃海水或淡水的玻璃纤维增强塑料外包覆钢筋混凝土埋地管道、管件。其它行业用埋地玻璃纤维增强塑料外包覆钢筋混凝土管道可参照本文件执行
20.[标准] 核科学技术术语　第7部分：核材料管制与核保障

发布单位：
中国-国家标准(CN-GB)

标准状态：
现行

标准号：
GB/T 4960.7-2023

发布时间：
2023-12-28

中标分类：
F04 基础标准与通用方法

国标分类：
27.120.01 核能综合

实施时间：
2024-07-01

摘要：本文件界定了核材料管制相关的通用、核材料与核设施、实物保护、核材料衡算、核材料控制、视察以及核保障领域的术语和定义。本文件适用于编写核材料管制与核保障领域内的各级标准和有关技术文件等。

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