fast reactor
美 
英
- un.快中子反应堆；快堆
- 网络快中子堆；中子增殖堆；快反应器
英汉解释
例句
Japan has been developing fast-reactor technology for decades, but it has not gone well.
几十年来，日本一直致力于发展快中子反应堆技术，但收效甚微。
Heavy-metal aerosol transport in a lead-bismuth-cooled fast reactor with in-vessel direct-contact steam generation.
带有容器内直接连结蒸汽发生器的铅-铋冷却快堆的重金属气溶胶输运…[中国核科技信息与经济研究院]。
In the next years, the pace of fast reactor development picked up, and the programs were at their peaks by 1980.
在未来几年，快堆发展的步伐加快，在他们的方案是由1980年的高峰。
Another advantage of fast reactor technology is the higher utilization ratio of uranium.
中子反应堆另一优势是更高的铀利用率。
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（ChinaNationalNuclearCorporation）请他们的快中子反应堆专家出面讨论核安全。
A combined method to evaluate the resonance self shielding effect in power fast reactor fuel assembly calculation.
动力快堆燃料组件计算中共振自屏蔽效应混合估计方法…[中国核科技信息与经济研究院]。
Behavior of fission products zirconium and barium in fast reactor fuel irradiated to high burnup.
高燃耗快堆燃料中裂变产物锆和钡的行为…[中国核科技信息与经济研究院]。
Safety analysis of fast reactor core with uranium-free fuel for actinide transmutation.
用于锕系元素嬗变的不含铀燃料快堆堆芯安全分析…[中国核科技信息与经济研究院]。
Xu said that the decision will not affect the fast reactor because it has already been officially approved and tested.
徐说，此决定将不会影响中子反应堆，因为已经被官方批准及实验过。
Experiments and analyses on sodium void reactivity worth in uranium-free fast reactor at FCA.
快临界装置的钠空穴反应性价值的实验和分析…[中国核科技信息与经济研究院]。
Development and validation of ALFUS: an irradiation behavior analysis code for metallic fast reactor fuels.
ALFUS的开发与证实：金属快堆燃料的辐照行为分析编码…[中国核科技信息与经济研究院]。
A metal fuel fast reactor core for the self-consistent nuclear energy system.
自洽核能系统的金属燃料快堆堆芯…[中国核科技信息与经济研究院]。
Pu vector sensitivity study a Pu burning fast reactor. Pt. 2. Rod worth assessment and design optimization.
燃钚快堆钚矢量灵敏性研究，第2部分，棒价值评价与设计最佳化…[中国核科技信息与经济研究院]。
Fission gas release and swelling model of metallic fast reactor fuel.
快堆金属燃料裂变气体释放和溶胀模型…[中国核科技信息与经济研究院]。
In the early 1990s, China and Russia began cooperation on fast reactor.
上世纪90年代初，中俄两国开始在快堆领域进行多方位合作。
Status of research and development of the lead-alloy-cooled fast reactor.
铅合金冷却快堆研究发展情况…[中国核科技信息与经济研究院]。
The study has significant academic value for research of advanced space fast reactor and engineering application.
本论文的工作对先进空间快堆的研究以及工程应用有理论指导意义。
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。
Study of Transmutation of Minor Actinides in Accelerator-Driven Sub-critical Fast Reactor
次锕系元素在加速器驱动的次临界快堆中嬗变的研究
Modeling of Accident Scenario Caused by Total Blockage of Single Subassembly in a Fast Reactor and its Validation
快堆单个燃料组件完全堵流事故的建模及其验证
Molten material transport model verification for a fast reactor
快堆内熔融物传播模型的验证
Radial Heat Transfer Mechanisms of Faulted Fast Reactor Fuel Subassembly During Local Accidents
快堆局部事故时受损燃料组件的径向传热机理
Numerical Simulation of Natural Convection in Annual Space of Rotating Plug for The CEFR Fast Reactor
对中国实验快堆旋塞环形空间自然对流的数值模拟
Study of Transmutation in Modular Fast Reactor Using MOX Fuel
MOX燃料模块快堆的嬗变研究
Performance and Startup Characteristics of Advanced Space Fast Reactor
先进空间快堆运行特性和启动特性
Comparison analysis on base material between Chinese test fast reactor and Russian fast reactor
中国实验快堆与俄罗斯快堆母材对比分析
Generation of minor group cross section library for micro beryllium-reflex layer fast reactor
微小型铍反射层快中子堆专用群截面数据库的制作
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
Application of Wavelet Transform to Fault Diagnosis of Sodium Pump of China Experiment Fast Reactor
小波变换在中国实验快堆钠泵故障诊断中的应用
Safety Characteristic Analysis of Advanced Space Fast Reactor
先进空间快堆安全特性分析
Predictive model for local core melting accident caused by subassembly blockage in a fast reactor
快堆局部堵流所致堆芯局部熔化事故的预测模型
Establishment and validation of the model of molten pool in fast reactor
钠冷快堆中熔融池模型的建立与验证
Neutronics Study on Minor Actinide Heterogeneous Core of ADS Fast Reactor
加速器驱动的次临界系统快堆次锕系核素非均匀布置堆芯的中子学研究
Calculation and Assessment of the Stress Intensity for the Main Vessel in China Experimental Fast Reactor
中国实验快堆堆容器应力强度计算与评定
Non-compliance Control in Manufacture of Fast Reactor Products
快堆产品制造过程中不符合项的控制
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
Calculation of Pseudo Fission-product Data for Fast Reactor
快堆伪裂变产物数据的计算
Prediction of sodium boiling caused by total blockage of a single subassembly inlet in the Chinese experimental fast reactor
中国实验快堆单组件完全堵流后钠沸腾的预测
Sodium Spray Fire Analysis of Sodium-Cooled Fast Reactor
钠冷快堆中喷雾钠火的计算分析
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
