1.
Preliminary Design of Sub-critical Reactor Core for Accelerator Driven System with Three Proton Beams
三束流驱动ADS次临界反应堆堆芯初步设计
2.
Nuclear criticality safety for fissile materials outside reactors--Safety controls in conducting subcritical neutron multiplication measurements in situ
GB15146.7-1994反应堆外易裂变材料的核临界安全次临界中子增殖就地测量安全规定
3.
maritime gas-cooled reactor critical experiment
气冷式海上反应堆临界试验装置
4.
Nuclear criticality safety for fissile materials outside reactors--Administrative regulation for nuclear criticality safety
GB15146.1-1994反应堆外易裂变材料的核临界安全核临界安全行政管理规定
5.
primary reactor coolant system
反应堆一次冷却系统
6.
once through reactor
燃料一次循环反应堆
7.
Analysis of Candidate Core Materials in SCWR Based on Boiler Materials of SCU
基于超临界火电站锅炉用材的超临界水冷却反应堆堆芯候选材料分析
8.
Delayed Supercritical Process with Temperature Feedback at Arbitary Initial Power
任意初始功率下考虑温度反馈的反应堆缓发超临界过程
9.
Correction Method for Critical Extrapolation of ControlRods-Rising during Physical Start-Up of Reactor with Spatial Effect
反应堆物理启动提棒外推临界时考虑空间效应的修正方法
10.
Analysis of the Effect on Two-dimensional Transport-burnup Calculation of Dual-cooled Waste Transmutation Blanket for the Fusion-Driven Sub-critical System;
聚变驱动的次临界堆燃耗计算二维效应分析研究
11.
Core plasma parameters design and analysis for the fusion driven sub-critical system
聚变驱动次临界堆聚变堆芯参数设计与分析
12.
CONCEPTUAL RESEARCH ON REACTOR CORE PHYSICS FOR ACCELERATOR DRIVEN SUB CRITICAL REACTOR
加速器驱动次临界堆堆芯物理概念研究
13.
Nuclear criticality safety for fissile materials outside reactor--Requirements for nuclear criticality safety in the storage of fissile material
GB15146.3-1994反应堆外易裂变材料的核临界安全易裂变材料贮存的核临界安全要求
14.
The first explosion tore the reactor vault apart.
第一次爆炸将反应堆的屏蔽室炸飞了。
15.
The sampling method by coupling criticality source direction biasing and the exponential transform is established for duct shielding calculation.
建立临界源方向偏倚和指数变换相结合的藕合抽样方法，用于反应堆孔道的屏蔽计算。
16.
reactor core radiation detector
反应堆堆芯辐射检测仪
17.
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
18.
Application of Degree of Similarity in Choice of Correlations for Supercritical Water Reactor
贴近度在超临界水堆实验关联式选择中的应用