临界安全是指在乏燃料最终处置过程中防止发生未受控的核链式反应（临界）的安全要求，确保在运行阶段和运行后阶段，临界事件的发生概率及其后果受到充分限制。具体而言，是在处理和加工核燃料（如二氧化钍轻水混合物、钚-239硝酸轻水混合物、铀235金属轻水混合物等）时防止发生自持核链式反应的安全措施和数据。
| 标准号 & 类别 | 标准名称 | 发布 |
|---|---|---|
| ANSI/ANS 57.1-1992(2005) 规范 |
Design Requirements for Light Water Reactor Fuel Handling Systems
燃料处理系统 燃料组件 |
2005 美国国家标准学会 |
| ANSI/ANS 8.21-1995(2011) 规范标准 |
use of fixed neutron absorbers in nuclear facilities outside reactors
|
2011-05-19 美国国家标准学会 |
| ANSI/ANS 8.22-1997(2011) 规范标准 |
Nuclear Criticality Safety Based on Limiting and Controlling Moderators
裂变材料 |
2011 美国国家标准学会 |
| ANSI/ANS 8.27-2015(2020) 规范标准 |
Burnup Credit for LWR Fuel
燃料组件 |
2020-08-07 美国国家标准学会 |
| BS ISO 16117:2013 规程标准 |
Nuclear criticality safety. Estimation of the number of fissions of a postulated criticality accident
|
2013-10-31 英国标准学会 |
| DIN 25403 Bb.1:1997 指南标准 |
Criticality safety in processing and handling fissile materials - Comments
裂变材料 |
1997-10 德国标准化学会 |
| DIN 25403 Beiblatt 1:1997 指南标准 |
Criticality safety in processing and handling fissile materials — Comments
裂变材料 |
1997-10-01 德国标准化学会 |
| DIN 25403-1 E:2012-11 规范 |
Criticality safety in processing and handling of fissile materials - Part 1: Principles
核燃料 |
2012-11 德国标准化学会 |
| DIN 25403-1:2013-12 规范 |
Criticality safety in processing and handling of fissile materials - Part 1: Principles
核燃料 |
2013-12 德国标准化学会 |
| DIN 25403-2:1995 规范 |
核燃料的处理和和搬运时的临界安全性.第2部分:铀235金属轻水混合物的临界数据 Criticality safety in processing and handling fissile materials - Part 2: Criticality data for uranium 235 metal light-water mixtures
临界值 |
1995-10 德国标准化学会 |
| DIN 25403-3:2000 试验 |
处理和搬运核燃料时的临界安全性.第3部分:钚239金属-轻水混合物的临界数据 Criticality safety in processing and handling fissile materials - Part 3: Criticality data for plutonium 239 metal light-water-mixtures
临界值 |
2000-09 德国标准化学会 |
| DIN 25403-4:1995 规范 |
核燃料的处理和和搬运时的临界安全性.第4部分:二氧化铀轻水混合物的临界数据 Criticality safety in processing and handling fissile materials - Part 4: Criticality data for uranium dioxide light-water mixtures
临界值 二氧化铀 |
1995-10 德国标准化学会 |
| DIN 25403-6:2000 试验 |
处理和搬运核燃料时的临界安全性.第6部分:钚239硝酸盐-轻水混合物的临界数据 Criticality safety in processing and handling fissile materials - Part 6: Criticality data for plutonium 239 nitrate light-water-mixtures
临界值 |
2000-09 德国标准化学会 |
| DIN 25403-7:1996 试验 |
核燃料处理和装运临界安全性.水中低浓缩二氧化铀栅棒的临界数据 Criticality safety in processing and handling fissile materials - Part 7: Criticality data for low enriched uranium dioxide lattices in water
|
1996-08 德国标准化学会 |
| DIN 25403:2024-12 规范标准 |
Criticality safety in processing and handling of fissile materials - Principles
核燃料 核设施 |
2024-12-01 德国标准化学会 |
| DIN 25471:2009 规范 |
带轻水反应堆的核电站燃料槽中核燃料元件在搬运和储存时燃耗应考虑的临界安全性 Criticality safety taking into account the burnup of fuel elements when handling and storing nuclear fuel elements in fuel pools of nuclear power plants with lightwater reactors
|
2009-05 德国标准化学会 |
| DIN 25471:2021 |
在轻水反应堆核电站燃料池中处理和储存核燃料元件时考虑燃料元件燃耗的临界安全 Criticality safety taking into account the burnup of fuel elements when handling and storing nuclear fuel elements in fuel pools of nuclear power plants with lightwater reactors
燃耗 |
2021-08-00 德国标准化学会 |
| DIN 25471:2021-08 规范 |
在轻水反应堆核电站燃料池中处理和储存核燃料元件时考虑燃料元件燃耗的临界安全 Criticality safety taking into account the burnup of fuel elements when handling and storing nuclear fuel elements in fuel pools of nuclear power plants with lightwater reactors
燃料组件 燃耗 |
2021-08 德国标准化学会 |
| DIN 25472:2012-08 规范 |
Criticality safety for final disposal of nuclear fuels to be discarded
|
2012-08 德国标准化学会 |
| DIN 25474 E:2013-03 规范 |
Measures of administrative character for conservation of criticality safety in nuclear facilities excluding reactors
|
2013-03 德国标准化学会 |
| DIN 25474:2014 规范 |
Measures of administrative character for conservation of criticality safety in nuclear facilities excluding reactors
核燃料 |
2014-06-01 德国标准化学会 |
| DIN 25474:2014-06 规范 |
Measures of administrative character for conservation of criticality safety in nuclear facilities excluding reactors
核燃料 |
2014-06 德国标准化学会 |
| DIN 25478 Bb.1:2012 指南标准 |
Application of computer codes for the assessment of criticality safety - Supplement 1: Explanations
偏差 基准系统 |
2012-09 德国标准化学会 |
| DIN 25478 Beiblatt 1:2012-09 规范 |
Application of computer codes for the assessment of criticality safety - Supplement 1: Explanations
偏差 |
2012-09 德国标准化学会 |
| DIN 25478 E:2013-08 规范 |
Application of computer codes for the assessment of criticality safety
|
2013-08 德国标准化学会 |
| DIN 25478:2014 规范 |
Application of computer codes for the assessment of criticality safety
|
2014-06-01 德国标准化学会 |
| DIN 25712 E:2014-05 试验 |
考虑容器中受辐射轻水反应堆燃料组件运输和储存的燃料燃耗的临界安全 Criticality safety taking into account the burnup of fuel for transport and storage of irradiated light water reactor fuel assemblies in casks
燃料组件 |
2014-05 德国标准化学会 |
| DIN 25712:2007 试验 |
考虑容器中受辐射轻水反应堆燃料组件运输和储存的燃料燃耗的临界安全 Criticality safety taking into account the burnup of fuel for transport and storage of irradiated light water reactor fuel assemblies in casks
燃耗 |
2007-07 德国标准化学会 |
| DIN 25712:2015 规范 |
考虑容器中受辐射轻水反应堆燃料组件运输和储存的燃料燃耗的临界安全 Criticality safety taking into account the burnup of fuel for transport and storage of irradiated light water reactor fuel assemblies in casks
燃耗 |
2015-04 德国标准化学会 |
| DIN 25712:2015-04 试验 |
考虑到运输和储存桶中辐照轻水反应堆燃料组件的燃料燃耗的临界安全 Criticality safety taking into account the burnup of fuel for transport and storage of irradiated light water reactor fuel assemblies in casks
|
2015-04 德国标准化学会 |
| ISO 1709:1995 规范 |
Nuclear energy - Fissile materials - Principles of criticality safety in storing, handling and processing
裂变材料 |
1995-11 国际标准化组织 |
| KTA 3107:2014(R2017) 规程标准 |
Nuclear Criticality Safety Requirements during Refueling
燃料组件 |
2014-11-01 德国核技术委员会 |
| SS-ISO 27467:2009 规范 |
核临界安全 假设临界事故的分析（ISO 27467:2009 等同采用） Nuclear criticality safety - Analysis of a postulated criticality accident (ISO 27467:2009, IDT)
|
2009 瑞典标准研究所 |
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