核安全技术原则
规范用词核安全技术原则
英文对照technical principles for nuclear safety
名词定义为达到核安全目标在技术上必须遵循的指导原则。包括安全相关活动中贯彻纵深防御概念，采用经验证的技术，辐射防护中合理可行尽量低的原则，实施质量保证活动、设计及运行中重视人因工程学和运行经验反馈和安全研究等。
名词审定电力名词审定委员会
见载刊物《电力名词（第二版）》 科学出版社
公布时间2009年
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核安全技术原则 相关科技名词
- 参考核电厂reference nuclear power plant
- 第三代[核电]反应堆third generation of nuclear power reactor
- [美国]电力公司要求文件utility requirement document;URD
- 欧洲电力公司要求文件European Utility Requirement;EUR
- 第四代[核电]反应堆fourth generation of nuclear power reactor
- 核电厂安全性safety of nuclear power plant
- 核电厂可靠性reliability of nuclear power plant
- 核电厂采购控制nuclear power plant procurement control
- 核电厂厂区site of nuclear power plant
- 核电厂建设进度控制scheduling in construction of nuclear power plant
- 核电厂建设网络进度network schedule for construction of nuclear power plant
- 人因事件human event
- 蒸汽排放控制steam discharge control
- 蒸汽发生器水分夹带试验moisture carry over test of steam generator
- 冰塞检修法maintenance method by ice plug
- 核保障现场视察on-site inspection for safeguard
- 原子能法Atomic Energy Law
- 核电项目策划nuclear power project planning
- 核电厂建设单位construction unit of nuclear power plant
- 核电厂营运单位operating unit of nuclear power plant
- 核电厂选址siting of nuclear power plant
- 轻水反应堆light water reactor;LWR
- 压水反应堆pressure water reactor;PWR
- 沸水反应堆boiling water reactor;BWR
- 先进压水反应堆advanced pressurized water reactor;APWR
- 重水反应堆heavy water reactor
- 先进CANDU堆advanced CANDU reactor;ACR
- 石墨水冷反应堆graphite watercooled reactor
- 石墨气冷反应堆graphite gas-cooled reactor
- 高温气冷反应堆high temperature gas cooled reactor;HTGR
- 柱状型高温气冷堆prismatic high temperature gas cooled reactor
- 球床型高温气冷堆high temperature gas cooled reactor of pebble bed;PBMR
- 熔盐反应堆molten salt reactor
- 快中子增殖反应堆fast breeder reactor
- 超临界水冷反应堆supercritical water-cooled reactor
- 动力反应堆power reactor
- 船用反应堆ship reactor
- 移动式核电厂mobile nuclear power plant
- 托卡马克聚变实验装置Tokamak
- 激光聚变实验装置laser fusion experimental device
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