核能发电
规范用词核能发电
英文对照nuclear electricity generation
名词定义利用核反应堆中链式核裂变反应所释放的能量发电。
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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核能发电 相关科技名词
- 反应堆结构断裂力学fracture mechanics in reactor structure
- 主管道材料material for main pipe
- 蒸汽发生器传热管材料material for steam generator tube
- 晶间腐蚀intergranular corrosion
- 反应堆冷却剂材料material for reactor coolant
- 反应堆屏蔽材料reactor shielding material
- 反应堆核设计reactor nuclear design
- 技术规格书technical specification
- 核设计准则nuclear design criterion
- 反应堆热功率reactor thermal power
- [核电厂]额定电功率rated electrical power
- [核电厂]热效率thermal efficiency
- 设计基准地震design basis earthquake;DBE
- 堆芯功率密度power density incore
- [燃料元件]线功率[fuel element] linear power
- 堆芯布置方案core configuration pattern
- 堆芯功率分布core power distribution
- 换料方案refueling scheme
- 平衡堆芯equilibrium core
- 低泄漏堆芯refueling core for low neutron leakage
- [堆芯]首次铀装量first uranium inventory [of core]
- 核电厂抗震设计seismic design of nuclear power plant
- 地震响应分析analysis of structural response to seismic excitation
- 楼层响应谱floor response spectrum
- 运行安全地震operational safety earthquake;SL-1
- 时间历程time history
- 极限安全地震ultimate safety earthquake;SL-2
- 零周期加速度zero period acceleration;ZPA
- 核安全技术原则technical principles for nuclear safety
- 安全系统设计准则design criteria of safety system
- 卡棒准则stuck rod criteria
- 锆水反应zirconium-water reaction
- 钠水反应sodium-water reaction
- 设计基准外部事件design basis external event
- 设计基准事故design basis accident
- 最大可信事故maximum credible accident;MCA
- 极限事故工况limiting accident condition
- 系统和部件的可靠性设计reliability design of system and component
- 反应堆热工分析reactor thermal analysis
- 反应堆释热heat release in reactor
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