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- A nuclear desalination system using 200 MW nuclear heating reactor and multi-effect distillation process is presented in this paper. 本文提出了200兆瓦核供热堆与多效蒸发淡化工艺组合的核能海水淡化方案。
- Abstract The power automatic control system on nuclear heating reactor (NHR) is a multi input &multi output non linear system. 摘要 核供热堆功率自动控制系统是一个多输入多输出的非线性系统。
- The technology for the low temperature nuclear heating reactor (NHR) is developed independently and its property right is completely owned by China. 低温核供热堆技术是我国独立开发的拥有完全自主知识产权的高新技术。
- A HR-200 nuclear desalination system is proposed which consists of one unit of 200 MW(t)nuclear heating reactor and multi-effect distillation (MED)process plant. 提出了利用200MW(t)核供热堆与多效蒸发工艺相组合的一种核能海水淡化系统。
- JIA Haijun,LI Yi,XIAO Zhi,et al.Study of system and evaporation process of a multi-tower VTE-MED coupled with nuclear heating reactor[J].Nuclear Power Engineering,2003,24 (6):101-104(in Chinese). [2]贾海军;李毅;肖志;等.;与核供热堆耦合的海水淡化系统及蒸发工艺研究[J]
- By using the code, the steady-state heat-removed capacity of the passive natural-circulation residual-heat-removed system for 200MW Nuclear Heating Reactor (NHR-200) is calculated. 运用SAC-PREARS程序对200MW核供热堆非能动自然循环余热排出系统的稳态自然循环载热能力进行了计算;
- Abstract: PHOENICS-3.2, a three dimension CFD code, is used to simulate the heat transfer and flow in the bypass and the upper plenum of the core of 200 MW nuclear heating reactor (NHR-200). 摘 要: 应用三维CFD软件PHOENICS-3.;2,计算了200MW低温供热堆(NHR-200)堆芯旁通区及上腔室的流场和温场。
- Investigation on heat-electricity cogeneration with nuclear heating reactor is one of the important aspects of exploitation and research on comprehensive utilization of nuclear heating reactors. 核供热反应堆热电联产研究是低温堆综合利用开发研究的一个重要方面。
- Design of Primary Heat Exchanger for Nuclear Heating Reactor 核供热堆主换热器的设计研究
- Research on the Periphery Loose Assembly in Long-cycle Nuclear Heating Reactor 长寿期供热堆外围组件方案研究
- Fuzzy Inference-Based Fault Diagnosis System for Nuclear Heating Reactor 基于模糊推理的核供热堆故障诊断系统研究
- A soft-measuring method to measure the core coolant temperature at the outlet of a nuclear heating reactor 核供热堆堆芯冷却剂出口温度的软测量方法
- The Measuring Method and Error Estimation of Temperature for Coolant at Ou tlet of Nuclear Heating Reactor 核供热堆堆芯出口冷却剂温度测量方法和误差估计
- Research of Management Information System of Radiation Protection for Low Temperature Nuclear Heating Reactor 低温核供热站辐射防护管理信息系统研究
- Installation method for the steel container and vessel of the Nuclear Heating Reactor 核供热堆压力壳、钢安全壳套装工艺
- Research on Real-Time Simulation of Heat Exchanger in Low Temperature Nuclear Heating Reactor 低温供热堆换热器的实时仿真研究
- Real Time Simulation Research in 200 MW Low Temperature Nuclear Heating Reactor Core 200MW低温供热堆堆芯实时仿真研究(英文)
- Dose Radiological Sampling and Monitoring System of Daqing 200MW Nuclear Heating Reactor 大庆200MW核供热站剂量与放射性监测
- Keywords nuclear heating reactor (NHR);control rod position indicator;detector;coding bar;tri-code; 供热堆;控制棒位置指示系统;探测器;编码棒;多态码;
- Experimental Study on Measurement Method of Exit Temperature of Coolant of Fuel Assembly in Core of 200 MW Nuclear Heating Reactor 200MW核供热堆堆芯燃料元件盒冷却剂出口温度测量方法实验研究