This International Standard provides a methodology to estimate a reasonably maximal value of the number of fissions of a postulated criticality accident.The fission number estimate, associated with its postulated criticality accident, impacts the accident emergency planning and response because it is used for the estimation of radiation doses and of radioactive materials release.This International Standard does not provide a methodology and guidance to determine bounding accident scenarios.This International Standard does not cover criticality accident detection which is dealt with by ISO 7753.This International Standard does apply to nuclear facilities, plants, laboratories, storage, and transportation of fissile material (but not to nuclear power reactor cores) where a credible criticality accident may occur.
- ISO 16117-2013 - 中外标准 - ISO- 2013/1 - 现行
关键词：临界安全 定义 估计 最大 核的 核能 核电厂 辐射 辐射事故 放射性照射 辐射危害 辐射测量 辐射防护 放射性物质 放射性 Criticality safety Definitions Estimation Maximum Nuclear Nuclear energy Nuclear power plants Radiation Radiation casualities Radiation exposure Radiation hazards Radiation measurement Radiation protection Radioactive materials Radioactivity
his International Standard specifies the applicable requirements related to the design and the operation of containment and ventilation systems of nuclear power plants and research reactors, taking into account the following.
- ISO 26802-2010 - 中外标准 - ISO- 2010/1 - 现行
关键词：密封装置 污染 定义 装置 安装 核装置 核电厂 核电站 核反应堆 操作 辐射防护 反应堆安全 危险管理 安全工程 安全性要求 防护屏蔽 规范(验收) 通风 通风系统 Containments Contamination Definitions Installations Nuclear installations Nuclear power plants Nuclear power stations Nuclear reactors Operation Radiation protection Reactor safety Reactors Safety Safety engineering Safety requirements Shields Specification (approval) Ventilation Ventilation systems
This International Standard specifies the applicable requirements concerning the design and use of ventilationsystems in nuclear installations such as hot cells, nuclear fuel fabrication and examination laboratories,plutonium-handling facilities, reprocessing plants, enrichment facilities, nuclear-waste treatment stations,storage facilities, etc.The purpose of ventilation and containment systems is to and ensure safety functions and protect workers,public and environment against the spread of radioactive contamination resulting from the operationalprocesses of these installations.This International Standard does not apply to the containment envelope of nuclear power plants and someresearch reactors where high pressure can occur during accident scenarios. It does apply to auxiliary roomsof these facilities.The requirements for the design and use of ventilation systems that ensure safety functions in nuclearreactors will be developed in another International Standard.
- ISO 17873-2004 - 中外标准 - ISO- 2004/1 - 现行
关键词：安全工程 设计 定义 电气工程 安全 操作 电气设备 核装置 核电厂 通风 钚 辐射防护 污染 职业安全 装置 污染控制 Contamination Definition Definitions Design Electrical engineering Electrical equipment Installations Nuclear installations Nuclear power plants Occupational safety Operation Plutonium Pollution control Radiation protection Safety Safety engineering Ventilation
核设施 屏蔽罩的通风 -
This International Standard specifies the requirements for the construction and the installation of radiobiological shielding devices used as ventilation passages through shielded enclosures with concrete or leaded walls to protect against gamma radiation. This International Standard applies to all shielded containment enclosures used for handling radioactive products or material emitting penetrating radiation (gamma or neutrons) in such quantities and of such emission rate that these products must be handled remotely behind a shielding wall. Typically, the enclosures considered cover all types of nuclear fuel cycle installations: reprocessing plants, hot activity laboratories, plutonium solution handling facilities, shielded cells, waste storage installations, etc. It could eventually be applied to particle accelerators, primary containment of research reactors, fusion research reactors, radiographic installations, neutron generators, etc. However, pressurized vessels, sealed sources, transport packaging for radioactive materials, as well as enclosures, primary circuits and vessels of nuclear power plants have been deliberately excluded from the scope of this International Standard. This International Standard specifies general and detailed principles which shall be respected when designing ventilation penetrations for shielded enclosures. These specifications can be divided more generally into two categories of guidance, which apply to the two following systems of ventilation penetrations for shielded enclosures already in use: — the first corresponding to the most important conventional systems used worldwide, and — the second corresponding to an alternative method, called the "cast iron helix technique".
- ISO 15080-2001 - 中外标准 - ISO- 2001/1 - 现行
关键词：数学计算 验证 套管 空气过滤器 空调设备 检验 生产 空调器 作标记 工作性能 外壳 监督(认可) 设计 空调系统 定义 通风 规范(验收) 安全工程 核技术 核装置 Air conditioners Air filters Air-conditioning equipment Air-conditioning systems Bushings Definition Definitions Design Enclosures Inspection Marking Mathematical calculations Nuclear installations Nuclear technology Operatability Production Safety engineering Specification (approval) Surveillance (approval) Ventilation Ventilations Verification
This International Standard describes the principles and methodologies of measuring both gas open porosity and permeability of hydraulic binder-based matrices used for immobilization of radioactive waste. The measurements can be carried out by using different apparatus designed and constructed on the basis of a few recommended characteristics. The measurements can be performed on samples prepared in a laboratory or taken from industrial production. Samples can be obtained by moulding or by coring a block.
- ISO 11599-1997 - 中外标准 - ISO- 1997/1 - 现行
关键词：粘合剂 液压的 透气性 孔隙率检验 污染控制 核能 辐射防护 试验 放射性物质 渗透性测量 放射性废物 Binding agents Gas permeability Hydraulic Nuclear energy Permeability measurement Pollution control Porosity tests Radiation protection Radioactive materials Radioactive wastes Testing
核电厂 可维修性 术语 两种语言版 -
Identifies the typical parameters and terms necessary for collecting and exchanging maintainability data. The definitions are valid for corrective maintenance. For preventive maintenance, a similar classification can be drawn up. The general guidelines on the exchange of reliability data for nuclear power plants are given in ISO 6527.
- ISO 8107-1993 - 中外标准 - ISO- 1993/1 - 现行
关键词：核电厂 词汇 核动力 核能 核反应堆 术语 定义 维修 Definitions Maintenance Nuclear energy Nuclear power Nuclear power plants Nuclear reactors Nuclear-electric power stations Terminology Vocabulary
核能 轻水反应堆 核燃料衰变热功率的计算 -
Provides the basis for calculating the decay heat power of non-recycled nuclear fuel considering: the contribution of the fission products from nuclear fission; the contribution of the actinides; the contribution of isotopes resulting from neutron capture in fission products.
- ISO 10645-1992 - 中外标准 - ISO- 1992/1 - 现行
关键词：核燃料 衰变热功率 核反应堆 核能 轻水反应堆 数学计算 Decay heat power Light water reactors Mathematical calculations Nuclear energy Nuclear fuels Nuclear reactors
核电厂 抗震设计 -
Specifies the requirements for designing and the data required and the way in which they should be used in order to determine the earth motions to be taken as the design basis earthquake (DBE), moreover the way in which the proof of seismic design adequacy should be established and documented. Determination of DBE is covered by both probabilistic and deterministic methods. Is entirely applicable when the DBE is greater than or equal to intensity VII on the MSK scale. When the DBE is less, the structural analysis could also be performed by using simpler rules.
- ISO 6258-1985 - 中外标准 - ISO- 1985/1 - 废止
关键词：数学计算 定义 设计 规范 结构 核技术 结构设计 抗震结构 地震带 地震区 抗震设计 地震防护 核电厂 核电站 Definition Definitions Design Earthquake protection Earthquake zones Earthquake-resistant design Mathematical calculations Nuclear power plants Nuclear technology Nuclear-electric power stations Specifications Structural design Structures