缓发临界
规范用词缓发临界
英文对照delayed criticality
名词定义反应堆的正反应性ρρ，依靠缓发中子的参与，使得裂变链式反应可控地达到临界状态的现象。
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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缓发临界 相关科技名词
- 堆芯比焓升core specific enthalpy rise
- 热通道因子hot channel factor
- 热点因子hot point factor
- 工程因子engineering factor
- 轴向[释热率]不均匀因子axial heat generation peaking factor
- 径向[释热率]不均匀因子radial heat generation peaking factor
- 两相流动不稳定性two phase flow instability
- 堆芯流量分配core flow distribution
- 子通道间横流lateral flow between subchannels
- 流量惰走lateral flow;flow coastdown
- [反应堆]自然循环natural circulation in reactor
- 反应堆热工流体力学reactor thermo-hydraulics
- 反应堆水力实验reactor hydraulic experiment
- 反应堆整体水力模拟试验reactor integral mock-up hydraulic test
- 堆芯压降core pressure loss
- 流动压降flow pressure drop
- 两相压降two phase pressure drop
- 两相压降倍率two phase pressure drop multiplier
- 提升压降elevation pressure drop
- 限流器flow restrictor
- 反应堆结构力学structural mechanics in reactor technology
- 反应堆结构热应力thermal stress in reactor structure
- 反应堆结构热冲击thermal shock in reactor structure
- 核动力装置结构减震器damper in nuclear power structure
- 核动力装置结构阻尼器snubber in nuclear power structure
- 流-固耦合fluid-structure interaction;FSI
- 流致振动flow-induced vibration;FIV
- 核能发电nuclear electricity generation
- 核能供热nuclear heat
- 核电机组nuclear power unit
- 核动力nuclear power
- 核电规划nuclear power development program
- 核电基础结构infrastructure to a nuclear power program
- 核电人力资源开发manpower resource development for nuclear power
- 核电厂nuclear power plant
- 第一代[核电]反应堆first generation of nuclear power reactor
- 第二代[核电]反应堆second generation of nuclear power reactor
- 原型[核电]反应堆prototype [nuclear power] reactor
- 示范[核电]反应堆demonstration [nuclear power] reactor
- 商用[核电]反应堆commercial [nuclear power] reactor