fast reactor的例句大全

numerical analysis of china experimental fast reactor cold and hot plenums under normal condition

中国实验快堆额定工况下冷热钠池数值分析

The affection of fatigue and creep to the crack growth must be considered when LBB is applied on the nuclear pipes in the high temperature reactors ( as fast reactor) beyond the creep temperature.

对于在蠕变温度以上高温堆（如快堆）的核级管道，运用LBB分析时应该考虑疲劳和蠕变对裂纹扩展的影响。

Optimization of Breeding Property in a Fast Reactor

快中子反应堆增殖特性最优化分析

study on the deep burn-up fuel cycle of the pebble-bedgas-cooled fast reactor

深燃耗球床式气冷快堆研究

Along with the development of nuclear power technology in china, it is necessary to develop the fast breeder reactor ( fast reactor) through own efforts.

随着我国核电技术的发展，自主研制钠冷快中子增殖堆十分必要。

The fast reactor safety analysis is the foundation and key of FBR research work.

快堆安全分析是快堆研究工作的基础和重点.

Snell experiments have a good fast reactor benchmark properties.

Snell实验具有良好的快堆基准特性。

Chinese Experimental Fast Reactor ( CEFR) project is the first independent research, design, construction and management of the fast neutron reactor in China.

中国实验快堆（CEFR）工程是我国第一座自主研究、设计、建造和管理的快中子实验反应堆。

And on Monday China National Nuclear Corporation brought out their fast reactor expert to discuss nuclear safety.

周一，中国核工业集团（China National Nuclear Corporation）请他们的快中子反应堆专家出面讨论核安全。

The method can be used in fast reactor safety analysis and simulating calculation of velocity and temperature in heat exchanger of industry.

对该问题的研究结果可应用于快堆安全分析以及工业换热设备内流场和温场的模拟计算。

Some useful results which could be applied to reactor operation and physical start-up of acetain experimental fast reactor have been obtained.

它们对某试验快堆的安全运行和物理启动可能是有用的。

The TWG-FR has mostly focused on experimental and theoretical aspects of fast reactor technology and safety.

在小组-FR的大多集中在快堆技术和安全方面的实验和理论。

Predictive model for local core melting accident caused by subassembly blockage in a fast reactor Analysis and Prevention to the Melt Down of Convection Bank in a Package Boiler

快堆局部堵流所致堆芯局部熔化事故的预测模型快装锅炉对流管束熔化事故原因分析及预防措施

Study on the deep burn-up fuel cycle of the pebble-bed gas-cooled fast reactor

深燃耗球床式气冷快堆研究

Sodium Pool Fire Analysis of Sodium-cooled Fast Reactor by Calculation

钠冷快堆中池式钠火的计算分析

Neutronics of weapons-grade Pu burning in accelerator-driven sub-critical fast reactor

加速器驱动次临界快堆燃烧武器级钚的中子学研究

Reactor vessel cooling system is one of the important auxiliary systems in the primary system of China experimental fast reactor ( CEFR), which can cool the reactor vessel in various conditions.

堆容器冷却系统是中国实验快堆（CEFR）一回路系统中的重要辅助系统之一，用于在各种工况下对反应堆堆容器进行冷却。

Analysis and evaluation of FCCI for fast reactor

快中子反应堆的FCCI分析与预测

The Effects of Neutron Irradiation on the Type 316 Stainless Steel for Homemade Fast Reactor Fuel Element Cladding Material

国产快堆燃料元件包壳材料316不锈钢的中子辐照效应

Lead-bismuth eutectic ( LBE) cooled reactor is fast reactor, and different from PWR on coolant, cover gas, structure and etc. Radioactive source term is also characteristic.

铅铋反应堆是快中子反应堆，与压水堆在冷却剂、保护气体等结构和材料上有明显区别。