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- high temperature gas cooled breeder reactor 高温气冷增殖反应堆
- gas cooled breeder reactor 气冷增殖堆
- GCFBR (Gas Cooled Fast Breeder Reactor) 气冷快中子增殖反应堆
- gas cooled fast breeder reactor (GCFBR) 气冷快中子增殖堆
- semi homogeneous gas cooled breeder 半均匀气冷增殖反应堆
- gas cooled fast breeder reactor 气冷快中子增殖堆
- To produce(fissionable material) in a breeder reactor. 产生裂变的物质增殖,指在增殖反应堆里产生(可裂变的物质)
- To produce(fissionable material)in a breeder reactor. 产生裂变的物质增殖,指在增殖反应堆里产生(可裂变的物质)
- 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。
- A number of breeder reactor designs use liquid sodium as coolant. 一些增殖反应堆的设计使用液态钠为冷却剂。
- 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。
- Verifications and design of the remote control on 10MW high temperature gas cooled test reactor helium circulator are described in this paper. 简要描述了清华大学10MW高温气冷实验堆的氦循环风机远距离控制系统的设计与调试概况。
- 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。
- 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。
- Fast breeder reactors are in a calss by themselves. 快速反应堆有自己属性。
- 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。
- A breeder reactor. 增殖反应堆
- 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。
- The AEC predicted that by the year 2000 breeder reactor capacity would equal the total generating capacity of the United States in 1973. 原子能委员会预计,到2000年,增殖反应堆的能力将高于1973年美国全部发电量。
- Of course, the breeder reactor program involved in SIPI was not a routine government program. 当然,“公共情报有限公司科学家学院”一案中的增殖反应堆计划并非一个惯常的政府计划。