中国实验快堆,CEFR
1)CEFR中国实验快堆
1.Thermal stratificaiton studies in the upper plenum of CEFR;中国实验快堆热钠池热分层现象研究
2.Development progress of the CEFR-MOX fuel;中国实验快堆MOX燃料研究进展
3.Sodium fire analysis codes must be developed and applied in order to meet the requirement of accident analysis of China Experimental Fast Reactor ( CEFR ) and to suppo.开发和应用钠火事故分析程序,及时满足目前中国实验快堆安全分析的要求和我国快堆后续发展的需要,是本课题的首要任务。
英文短句/例句

1.The Development of Fault Diagnosis Systems of Sodium Pump for China Experiment Fast Reactor;中国实验快堆钠泵故障诊断系统的开发研究
2.Researching for Chinese Experimental Fast Reactotr Digital Power Regulating System by Simulating;中国实验快堆功率调节系统的数字化仿真研究
3.Research and Design on the Safety Parameter Display System of China Experimental Fast Reactor;中国实验快堆安全参数显示系统的研究与设计
4.Numerical simulation of temperature field of pump support cooling system for China experimental fast reactor中国实验快堆泵支承冷却系统温度场分析
5.Analysis of sodium/argon flow in anti-siphon equipment's curved pipeline of China Experimental Fast Reactor中国实验快堆虹吸破坏装置两相流动分析
6.The thermal hydraulic characteristics of the air heat exchanger in China Experimental Fast Reactor中国实验快堆空气热交换器热工流体力学研究
7.Corrosion of the weldments for outlet(inlet) pipe of China Experimental Fast Reactor super-heater in high temperature sodium中国实验快堆过热器出(入)口管焊接件在高温钠中的腐蚀
8.Transient Simulation and Analysis for Delayed Neutron Detection System of China Experimental Fast Reactor中国实验快堆缓发中子探测系统的瞬态模拟与分析
9.Corrosion of the weldments for China experimental fast reactor main vessel and its neck support in high temperature sodium and sodium vapour中国实验快堆主容器母材及其颈部支撑焊接件在高温钠及钠蒸气中的腐蚀
10.FARET (Fast Reactor Experiment Test)快中子反应堆实验测试
11.The Research of Brazing Application for Measuring Installation of Fast Neutron Experimentation Reactor;快中子实验反应堆测控装置钎焊技术研究
12.international thermonuclear experimental reactor国际热核实验反应堆
13.RESEARCH ON IRRADIATION DAMAGE OF CLADDING MATERIALS BY LIGHT ION BOMBARDMENT UNDER THE EXPERIMENTAL FBR DEVELOPMENT PROJECT实验快堆发展计划中包壳材料轻离子辐照损伤探讨
14.Design and Implementation of Computer Supervisory Control System for Experimental Fast Reactor Fuel Exchange;实验快堆换料过程计算机监控系统设计与开发
15.Simulation principle and analysis for heat transfer of argon space in the main vessel of China Experimental Fast Reactor快堆主容器内氩气空间传热实验原理及分析
16.Controlled nuclear fusion and ITER project可控核聚变与国际热核实验堆(ITER)计划
17.The Strategical Position of FBR in Nuclear Power Development in China快堆在我国未来核电事业发展中的战略地位
18.The Concept and Experiment of "Happy to Learn Chinese" Teaching Mode in Thai Public School泰国公立中学“快乐学汉语”教学模式构想及实验
相关短句/例句

China Experimental Fast Reactor中国实验快堆
1.China Experimental Fast Reactor Probabilistic Safety Assessment Level Ⅰ ——Foundation of the Event Trees;中国实验快堆一级概率安全评价——事件树的建立
2.Computational Validating for Temperature Monitoring-Spot Arrangement in Core Outlet Region of China Experimental Fast Reactor;中国实验快堆堆芯出口区域温度监测点布置计算验证
3.3D Software Simulation Design for Main Process Piping and Equipment of China Experimental Fast Reactor;中国实验快堆工程主工艺管系及设备三维校核设计
3)China Experimental Fast Reactor(CEFR)中国实验快堆
1.Based on the Leak-Before-Break (LBB) Analysis Method, this paper performs a fracture mechanics analysis on the intermediate loop of the decay heat removal system in China Experimental Fast Reactor(CEFR).采用破前漏(LBB)分析方法,对中国实验快堆余热排放系统中间回路进行断裂力学分析。
2.Based on the leak before break (LBB) analysis method, according to the requirements of French regulatory RCC-MR, this paper performs a fracture mechanics analysis on the intermediate loop of the decay heat removal system in China Experimental Fast Reactor(CEFR).本文采用破前漏(LBB)分析方法,按照法国RCC-MR规范要求,对中国实验快堆余热排放系统中间回路进行断裂力学分析。
4)China Experiment Fast Reactor中国实验快堆
1.Seismic appraisal test of control rod drive mechanism of China Experiment Fast Reactor;中国实验快堆控制棒驱动机构抗震鉴定试验
2.In this paper, The Web-based remote monitoring and failure diagnosis system is developed for important equipments of China Experiment Fast Reactor.本课题结合中国实验快堆(CEFR)重要设备,开发基于Web的远程监测诊断系统,并针对钠泵开发了远程故障诊断软件。
5)China Experimental Fast Reactor (CEFR)中国实验快堆
1.China Experimental Fast Reactor (CEFR) is the first sodium-cooled fast reactor of China.中国实验快堆(China Experimental Fast Reactor,CEFR)是我国第一座钠冷池式快中子反应堆,其特有的钠-钠-水三回路的主冷却系统引入了蒸汽发生器发生钠水反应事故的风险。
6)CEFR中国实验快堆(CEFR)
延伸阅读

快堆分子式:分子量:CAS号:性质:由快中子引起裂变的反应堆。即引起裂变的初级中子的平均能量>100千电子伏。就用途而言,一般情况下快堆不仅用于动力发电,也用于增殖,将可裂变核素转化成易裂变核素,如铀-238转化为钚-239,故又称快增殖堆(fast breeder reac-tor)。快堆一般采用液金属钠作载热剂,故又称钠冷快堆(sodium-cooled fast reactor)