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- Graphite moderated sodium cooled reactor 石墨慢化钠冷却反应堆
- sodium cooled reactor 钠冷反应堆
- A physical and thermohydraulic general estimate for the core of 25MW Lead Cooled Fast Breeder Reactor (LCFBR) has been carried out. The estimated result was compared with that of Sodium Cooled Fast Breeder Reactor (SCFBR) at the same power. 对25 MW电功率铅冷快增殖堆堆芯进行了物理和热工水力概算,并将计算结果与相同功率的钠冷快增 殖堆的结果进行了分析比较。
- sodium cooled graphite moderated reactor 钠冷石墨慢化堆
- sodium cooled zirconium hydride moderated reactor 钢冷氢化锆慢化堆
- The coated fuel particle is the key fuel element in the high temperature gas cooled reactor (HTGR). 包覆燃料颗粒是高温气冷堆燃料元件的关键组成部分。
- The high temperature gas cooled reactor physics simulation code VSOP was used for the prediction of the fuel loading for HTR 10 first criticality. 该文利用高温气冷堆物理模拟程序VSOP对HTR-10初次临界装料进行预估,计算了初次临界所需燃料球和石墨球数,为临界实验提供依据。
- ZrC layers are used instead of silicon carbide (SiC) layers for fabricating a new type of coated fuel particle for the high temperature gas cooled reactor (HTGR). 为了进一步发展和开发利用高温气冷堆，用碳化锆镀层替代碳化硅镀层制备新型的包覆燃料颗粒。
- The essential principle and implementation of the bi directional detector for Fuel Handling System (FHS) in 10MW High Temperature gas cooled Reactor (HTR 10) are presented. 介绍了10MW高温气冷堆燃料元件装卸系统双向探测器的基本原理和实现方法。
- MW high temperature gas cooled reactor(HTR 10) is a helium cooled and graphite moderated nuclear reactor. Spherical graphite fuel elements are piled loosely in the core. 10MW高温气冷堆为氦气冷却、石墨慢化的核反应堆，球形石墨燃料元件松散堆积在堆芯中。
- TRANSIENT BEHAVIOR OF THE LOSS OF HEAT SINK WITHOUT SCRAM AND INHERENT SAFETY OF SODIUM COOLED FAST REACTOR 钠冷快堆无停堆保护失热阱固有安全特性
- Organic liquid moderated and cooled reactor 有机液体慢化冷却反应堆
- Windscale advanced gas cooled reactor 温斯凯尔改进型气冷反应堆
- Heavy water moderated and organic cooled reactor 重水慢化有机物冷却反应堆
- water moderated organic cooled reactor 水慢化有机冷却堆
- heavy water gas cooled reactor type reactor 重水气冷堆
- high temperature gas - cooled reactor 高温气冷堆
- high-temperature gas cooled reactor 高温气冷堆
- Sodium and water react (together). 钠和水能起反应。
- supercritical water cooled reactor 超临界水堆
