27.120.20 核电站、安全 标准查询与下载
共找到 1795 条与 核电站、安全 相关的标准，共 120 页
Nuclear power plants - Instrumentation important to safety - Containment monitoring for early detection of developing deviations from normal operation in light water reactors
- ICS
- 27.120.20
- CCS
- 发布
- 2022-11-15
- 实施
Nuclear facilities - Instrumentation systems important to safety - Radiation monitoring for accident and post-accident conditions - Part 3: Equipment for continuous high range area gamma monitoring
- ICS
- 27.120.20
- CCS
- 发布
- 2022-11-10
- 实施
Nuclear facilities - Instrumentation systems important to safety - Radiation monitoring for accident and post-accident conditions - Part 3: Equipment for continuous high range area gamma monitoring
- ICS
- 27.120.20
- CCS
- 发布
- 2022-11-10
- 实施
The purpose of this document is to give an overview of the minimum requirements for performing the dicentric assay with quality control measures using mitogen stimulated peripheral blood lymphocytes for initial assessment of individuals involved in a mass casualty scenario. The dicentric assay is the use of chromosome damage to quickly estimate approximate radiation doses received by individuals in order to supplement the early clinical categorization of casualties . This document focuses on the organizational and operational aspects of applying the dicentric assay in an initial assessment mode. The technical aspects of the dicentric assay can be found in ISO 19238 . This document is applicable either to an experienced biological dosimetry laboratory working alone or to a network of collaborating laboratories (as defined in C lause 7 ) .
Radiation protection — Performance criteria for laboratories performing initial cytogenetic dose assessment of mass casualties in radiological or nuclear emergencies — General principles and applicati
- ICS
- 27.120.20
- CCS
- 发布
- 2022-11-07
- 实施
Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 4: Oxidation induction techniques
- ICS
- 27.120.20
- CCS
- 发布
- 2022-11-04
- 实施
Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 4: Oxidation induction techniques
- ICS
- 27.120.20
- CCS
- 发布
- 2022-11-04
- 实施
- 2022-11-04
Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 2: Indenter measurements
- ICS
- 27.120.20
- CCS
- 发布
- 2022-11-04
- 实施
Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 4: Oxidation induction techniques
- ICS
- 27.120.20
- CCS
- 发布
- 2022-11-04
- 实施
Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 2: Indenter measurements
- ICS
- 27.120.20
- CCS
- 发布
- 2022-11-04
- 实施
Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 4: Oxidation induction techniques
- ICS
- 27.120.20
- CCS
- 发布
- 2022-11-04
- 实施
Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 2: Indenter measurements
- ICS
- 27.120.20
- CCS
- 发布
- 2022-11-04
- 实施
本标准规定了燃料棒性能分析软件评价原则、评价方法、评价过程中关注的重点问题、评价准则和评价结论，可以为燃料棒性能分析软件的评价提供指导，以确保软件评价的质量和合规性。 本标准适用于压水堆核动力厂所使用的燃料棒性能分析软件，其它堆型核电厂和研究堆所使用的燃料棒性能分析软件可参照执行。 本标准适用于预测燃料棒在I、II类工况下堆内性能的燃料棒性能分析软件，用于预测燃料棒在III、IV类事故工况下堆内性能的燃料棒事故分析软件可参照执行。 本标准可为燃料棒性能分析软件评价的申请单位、核能行业从业者、以及核安全监管单位的人员提供参考。
Review for Fuel Rod Analysis Software
- ICS
- 27.120.20
- CCS
- D441
- 发布
- 2022-10-25
- 实施
- 2022-10-25
国家核安全局负责提出校核计算工作要求，并委托技术支持单位开展校核计算。核动力厂校核计算主要针对初步安全分析报告和最终安全分析报告中的关键内容开展符合性和评价性计算。 本文件适用于核动力厂设计、运行和退役阶段中安全审评碳-14源项校核计算，研究堆和小型模块化堆的校核计算可参照执行。 本文件规定了碳-14源项校核计算过程中涉及的原则、计算内容选择、数据需求确定、计算软件和模型描述、模型构件、结果分析以及结论等方面的内容。
Technical requirements for verification and calculation of carbon-14 source term in operation state of nuclear power plant safety review
- ICS
- 27.120.20
- CCS
- D441
- 发布
- 2022-10-25
- 实施
- 2022-10-25
本文范围包括核实核动力厂的设计是否满足核与辐射安全法规给出的安全管理要求、主要技术要求以及核动力厂设计和运行要求。 本文件适用于核动力厂设计和运行过程中安全审评设计扩展工况的校核计算，研究堆和其它核设施的校核计算可参照执行。 本文件规定了设计扩展工况校核计算过程中涉及的原则、计算内容选择、数据需求确定、计算软件和模型描述、模型构建、结果分析以及结论等方面的内容。
Check Calculation Method of Design Extension Conditions in Nuclear Power Plant Safety Review
- ICS
- 27.120.20
- CCS
- D441
- 发布
- 2022-10-25
- 实施
- 2022-10-25
堆芯子通道分析软件评价技术规范规定了评价的目的、评价方法、评价过程中关注的重点问题，并明确了评价准则。 本文件可为堆芯子通道分析软件安全评价的审评人员提供指导，也可为核动力厂安全分析用计算机软件开发单位的软件确认工作提供参考。 本文件适用于压水堆核动力厂所使用的堆芯子通道分析软件，其它堆型核电厂和研究堆所使用的堆芯子通道分析软件可参照执行。 本文件将结合堆芯子通道分析软件安全评价实践以及国内软件验证和确认计算的发展不断修订和完善。
Technical specification for evaluation of core subchannel analysis software
- ICS
- 27.120.20
- CCS
- D441
- 发布
- 2022-10-25
- 实施
- 2022-10-25
本文件为核动力厂设计基准事故非破口类工况的安全审评校核计算工作提供指导，以规范设计基准事故非破口类工况校核计算程序、确保工作质量、提高工作效率。本文件也可为核动力厂的设计、运营等单位、核能行业从业者的核与辐射安全分析计算工作提供参考。
Nuclear Power Plant Safety Review Design Basic Accident Non-LOCA Checking Calculation
- ICS
- 27.120.20
- CCS
- D441
- 发布
- 2022-10-25
- 实施
- 2022-10-25
本文件规定了离散纵标屏蔽分析软件评价原则、评价方法、评价过程中关注的重点问题、评价准则和评价结论。本文件主要适用于压水堆核动力厂所使用的离散纵标屏蔽分析软件，其它堆型核电厂和研究堆所使用的离散纵标屏蔽分析软件可参照执行。本文件为离散纵标屏蔽分析软件的评价提供指导，以确保软件评价的质量和合规性。本文件也可为离散纵标屏蔽分析软件评价的申请单位、核能行业从业者、以及核安全监管单位的人员提供参考。
Evaluation Method of Discrete Ordinate Shielding Analysis Software
- ICS
- 27.120.20
- CCS
- D441
- 发布
- 2022-10-25
- 实施
- 2022-10-25
This document establishes requirements relevant to the selection and use of wireless devices in instrumentation and control (I&C) systems important to safety used in nuclear power plants (NPPs). Those I&C systems may fully consist of wireless devices. other activity that may be necessary to use the device in an important to safety application. This document applies to the I&C of new NPPs and to backfit of I&C in existing NPPs. Every wireless device or wireless system that is important to safety is in the scope of this document. Both fixed and mobile devices and all data types (voice, process data, etc.) are included within the scope if they provide a safety classified function. This document restricts the use of wireless devices to systems supporting category C functions according to IEC 61226, excluding explicitly their use for categories A and B. Non-safety devices and systems may use this document as guidelines, for example to ensure that important to safety devices are not disturbed. – Clause 5 describes the fundamental requirements regarding safety and cybersecurity. – Clause 6 gives wireless-specific requirements that have to be included in the system design. – Clause 7 describes the requirements for the selection and integration of wireless devices. – Clause 8 deals with electromagnetic compatibility and spectrum management. – Clause 9 gives wireless-specific requirements regarding cybersecurity. – Clause 10 describes the requirements for the qualification of wireless devices and their environment.
Nuclear power plants. Instrumentation and control systems important to safety. Selection and use of wireless devices
- ICS
- 27.120.20
- CCS
- 发布
- 2022-09-30
- 实施
- 2022-09-30
BS ISO 7753. Nuclear criticality safety. Use of criticality accident alarm systems for operations
- ICS
- 27.120.20
- CCS
- 发布
- 2022-09-02
- 实施
- 2022-09-02
See the scope of IEC 62988:2018. Adoption of IEC 62988:2018 is to be done without modification.
Nuclear power plants - Instrumentation and control systems important to safety - Selection and use of wireless devices
- ICS
- 27.120.20
- CCS
- 发布
- 2022-08-19
- 实施
- 2023-02-08 (7)
