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.
reactor core radiation detector
反应堆堆芯辐射检测仪
3.
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
4.
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
5.
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
6.
reactor core isolation cooling system
反应堆堆芯隔离冷却系统
7.
Neutron flux distributions in the reactor core are measured.
测量了反应堆堆芯里的中子通量分布。
8.
Heat Balance Test for Determined Reactor Core Power
计算核反应堆堆芯功率的热平衡试验
9.
maritime gas-cooled reactor critical experiment
气冷式海上反应堆临界试验装置
10.
Coupled Thermal-Hydraulics and Neutron-Physics Analysis of Supercritical Water Cooled Reactor With Mixed Spectrum Core
混合能谱超临界水堆堆芯热工-物理性能分析
11.
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
12.
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
13.
primary reactor coolant system
反应堆一次冷却系统
14.
once through reactor
燃料一次循环反应堆
15.
it had a graphite core and no containment structure.
这些反应堆有一个石墨堆芯，没有外壳结构。
16.
In-core instrumentation for neutron fluence rate measurements in nuclear reactors
GB/T8995-1988核反应堆中子注量率测量堆芯仪表
17.
A Mechanism Investigation of Core Melting in Nuclear Reactor Using Molecular Dynamics Method
用分子动力学方法研究反应堆堆芯熔化机理
18.
A Measurement Method Regarding Reactor Core Thermal Power and Error Analysis
反应堆堆芯热功率测量方法及其误差分析