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冷却剂流道
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     Coating takes place of coolant
     涂层代替冷却剂
短句来源
     On Hot runner Technology
     热流道技术
短句来源
     A SIMULATING TEST OF COOLANT TEMPERATURE MIXING
     冷却剂温度混合模拟试验
短句来源
     The Application of Hot Runner System
     热流道系统的应用
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     Temperature distributions were given for the Be armor,the Be pebble bed,the Li_4SiO_4 pebble bed,the TBM structural material,and the helium coolant in the cooling pipe.
     研究TBM各区及冷却剂氦气流道的温度场分布,并对二维和三维计算结果进行比较。
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  coolant channel
The first wall is separated from the blanket wall and has a circular cross-section coolant channel since this shape is the most desirable for resisting the mechanical load due to the pressurized cooling water.
      
Quench is initiated in the first layer and propagates in this coolant channel as well as to the second coolant channel, via heat conduction.
      
Applied heat transfer condition in each coolant channel is the same as the ITER normal operation condition.
      
Consequently, as the temperature of the molten salt increases, the liquid viscosity decreases and the flow in the coolant channel increases.
      
Developing manufacturing facilities for coolant channel components made from zirconium alloys was one of the most challenging tasks.
      
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The structural scheme of Dual-cooled Lithium Lead( DLL) blanket module has been proposed for the fusion power reactor (named FDS-Ⅱ), whose basic concept is to use RAFM steel (e.g. CLAM steel) as structural material, liquid metal LiPb as both coolant and breeder, and SiCf/SiC composite material as flow channel inserts which serves as electrical and thermal insulators. In particular, the structure configuration of the blanket module is integrated considering breeding zone, channels of coolant, mechanical connections,...

The structural scheme of Dual-cooled Lithium Lead( DLL) blanket module has been proposed for the fusion power reactor (named FDS-Ⅱ), whose basic concept is to use RAFM steel (e.g. CLAM steel) as structural material, liquid metal LiPb as both coolant and breeder, and SiCf/SiC composite material as flow channel inserts which serves as electrical and thermal insulators. In particular, the structure configuration of the blanket module is integrated considering breeding zone, channels of coolant, mechanical connections, maintenance, etc. Furthermore, the introduction of “” shape steel grids have two advantages: simplifying the coolant channels which is to be easily implemented, simplifying manufacturing processes and enhancing the reliability. The DLL blanket may achieve higher availability in coolant system, manufacturing and assembly compared with other liquid metal lithium-lead blankets.

给出聚变发电反应堆FDS Ⅱ模块式液态锂铅包层(DLL)结构方案,以低活化马氏体(RAFM)钢为结构材料,采用液态金属LiPb作为增殖材料和冷却剂,使用碳化硅流道插件作为电绝缘和热绝缘。包层的设计特点体现在:从增殖区、冷却剂流道、屏蔽包层、母管、机械连接、维修装配等几个方面全局考虑包层设计,结构布置完整;独有的“”形隔板设计使氦气冷却回路容易实现,增殖流道简单,可简化制造工艺,提高可靠性。同其他液态锂铅包层相比,DLL包层在冷却剂系统、制造、装配上可成就较高的可行性。

The mathematics model in which radioactive nuclides are released from(nuclear) fuel to the environment during accident conditions in China Advanced Research(Reactor)(CARR) is eatablished.The source terms in the following accidents are analyzed,including small loss of coolant accident,heat exchanger plate break,heavy water loop break,fuel handling accident,coolant channel blocking accident,and three fuel(assemblies) meltdown.The quantities of radioactive(nuclides) released to the environment through different...

The mathematics model in which radioactive nuclides are released from(nuclear) fuel to the environment during accident conditions in China Advanced Research(Reactor)(CARR) is eatablished.The source terms in the following accidents are analyzed,including small loss of coolant accident,heat exchanger plate break,heavy water loop break,fuel handling accident,coolant channel blocking accident,and three fuel(assemblies) meltdown.The quantities of radioactive(nuclides) released to the environment through different paths during accidents are given to prevent undue radiological hazard to the public during accident conditions.

研究建立了中国先进研究堆(CARR)在事故工况下放射性核素从燃料芯块向环境释放的数学模型。根据CARR初步事故分析结果,对可能导致放射性向外界释放的5种事故工况(小破口失水事故、换热器传热板破裂事故、重水回路管道破裂事故、燃料操作事故、冷却剂流道堵塞事故)以及假想的3盒组件燃料板熔化超设计基准事故进行了源项分析,分别给出了不同事故和释放途径下释放到环境的放射性核素的量,以防止事故情况下公众和环境遭受过量放射性损伤。

 
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