breeder reactor
英 [ˈbriːdə(r) riˈæktə(r)]
美 [ˈbriːdər riˈæktər]
增殖（反应）堆
双语例句
- The fact is new reactor research and development has long been stalled in the United States, since President Jimmy Carter killed the Clinch River breeder reactor program in the wake of the 1979 Three Mile Island accident.
事实是，自从1979年三哩岛核电站事故后，美国前总统吉米•卡特终止了克林奇河增值反应堆计划，此后，美国新型反应堆的研究和开发就一直止步不前。 - Liquid metal cooled fast breeder reactor
液态金属冷却快增殖反应堆 - 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） - A breeder reactor is a nuclear reactor which not only consumes nuclear fuel but also produces such fuel.
增殖反应堆是一种不仅消耗核燃料，还能生产核燃料的核反应堆。 - Liquid metal breeder reactor
液态金属增殖反应堆 - 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。 - Fusion hybrid breeder reactor
聚变混合增殖反应堆 - Enrico fermi fast breeder reactor
讹科费米快中子增殖反应堆 - At the same time, CEFR is the first pool-type LMFBR ( Liquid Metal Fast Breeder Reactor) using dacay heat removel system to.
另外，CEFR又是世界上首次在堆内采用非能动手段来排出堆芯余热的池式快堆。 - It's as incomprehensible to ordinary people as the workings of a breeder reactor.
对普通人来说，这就像核增殖反应堆的运行一样不可理解。 - 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。 - Waterhammer Program Development and Application for Fast Breeder Reactor's Sodium Circus
快堆钠回路水锤程序开发与应用 - Single Assembly Preliminary Analysis for Horizontal Seismic Analysis on Fast Breeder Reactor Core
快堆堆芯水平抗震分析的单组件初步分析 - Discussion of the steady state velocity field and temperature distribution in the sodium pool of a fast breeder reactor
快堆钠池三维稳态流场和温度场的研究 - Inherent Safety Analysis for Lead Cooled Fast Breeder Reactor
铅冷快堆固有安全性的分析 - A three dimensional model for fluid flow and heat transfer in sodium pool of a fast breeder reactor ( FBR) is built on mass, momentum and energy conservation laws.
针对快中子增殖反应堆钠池的流动传热特点，以质量、动量、能量守恒定律为基础，建立有关快堆钠池流动传热的三维数学模型。 - Neutronics analyzation of helium cooled solid breeder blanket in a fusion reactor
聚变堆氦冷固态增殖包层中子学分析 - Dynamic characteristics study for main vessel of pool-type fast breeder reactor
池式快增殖堆主容器的动力特性研究 - Seismic Response Analysis for the Main Vessel of Pool-Type Fast Breeder Reactor
池式快堆主容器地震响应分析 - The neutron fluxes in the preliminary design of the helium cooled solid breeder blanket of a fusion solid breeder reactor were analyzed for various arrangements of the tritium breeder and neutron multiplier layers.
聚变堆固态包层框架下，针对初步设计的聚变堆氦冷固态包层进行了中子学分析。 - For the sake of full utilization of uranium resources and the minimization of nuclear waste, the closed fuel cycle of fast breeder reactor is the fundamental way out for the sustainable development of nuclear fission energy.
为了充分利用铀资源并实现核废物的最少化，快堆燃料闭式循环是核裂变能可持续发展的根本出路。 - Finite element analysis of three dimensional steady and unsteady temperature fields ( computation of temperature distribution of turbine blade with composite cooling) numerical analysis of heat transfer and flow with three dimensional steady and transient states in sodium pool of fast breeder reactor
三维物体稳态及瞬态温度场的有限元分析（复合冷却涡轮叶片三维温度场计算）快堆钠池三维稳态与非稳态流动传热的数值研究 - Effects of Thermodynamics Parameters of Steam Generator on the Response Behavior of Leak Detection System for Liquid Metal-cooled Fast Breeder Reactor
快堆蒸汽发生器热力参数对泄漏探测系统响应特性的影响 - Numerical analysis of heat transfer and flow with three dimensional steady and transient states in sodium pool of fast breeder reactor
快堆钠池三维稳态与非稳态流动传热的数值研究 - Physical and thermohydraulic study on lead cooled fast breeder reactor
铅冷快增殖堆物理和热工水力研究 - 3-D Monte-Carlo method was employed for analyzing Liquid Metal Fast Breeder Reactor ( LMFBR) sodium two-phase flow in fuel bundle under hypothetical loss of coolant accident ( LOCA) conditions.
采用蒙特卡罗方法分析钠冷快堆在假想冷却剂丧失条件下燃料棒束的钠两相流传热。 - Investigation on acoustic leak detection methods in liquid metal fast breeder reactor steam generator I. characteristics of signals
快堆蒸汽发生器声学泄漏探测技术的研究&Ⅰ.系统信号特性 - Numerical Simulation of Sodium Pool Fires in Liquid Metal-Cooled Fast Breeder Reactor
钠冷快堆钠池火事故数值模拟 - Some physical properties of the Th-~ ( 223) U thermal-neutron breeder reactor
Th-~（233）U热中子增殖堆某些物理特性的探讨
英英释义
noun
- a nuclear reactor that produces more fissile material than it burns