1)core design堆芯设计
1.This new core design was considered to be the hybrid of the existing thermal SCWR and fast SCWR cores.它在继承了热谱与快谱超临界堆芯设计优点的同时,有效地克服了两者的不足。
英文短句/例句
1.Design and Application of Reactor Core with Tight-Lattice Rod Type Fuel Element稠密栅棒型燃料元件堆芯设计及应用
2.The Nuclear Core Design of 450MWt Pressurized Water Reactor45万千瓦(热)压水堆堆芯核设计
3.Design of Core Vessel and Core Structure in China Advanced Research Reactor中国先进研究堆堆芯容器及堆内构件设计研究
4.Safety Analysis for Xi’an Pulsed Reactor in Pulse Operation Mode with the Core in Steady Arrangement and Design Project for the New Core Arrangement西安脉冲堆稳态堆芯脉冲运行安全性分析及新堆芯布置方案设计
5.Core Physics Design Calculation of Minitype Fast Reactor by MCNP Code;基于MCNP的微型钠冷快堆堆芯物理设计计算
6.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
7.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
8.Analysis of MOX core thermal characteristics and design criteriaMOX燃料堆芯热工特性及设计限值研究
9.GNPS 18-Months Fuel Cycles Core Thermal Hydraulic Design大亚湾核电站18个月换料堆芯热工水力设计
10.Heat Balance Test for Determined Reactor Core Power计算核反应堆堆芯功率的热平衡试验
11.Core Stable Flowrate Distribution of High Flux Engineering Test Reactor(HFETR)高通量工程试验堆堆芯流量分配计算
12.The physics scheme design for In-Hospital Neutron Irradiator-Mark 1 reactor loaded low-enrichment fuel低浓化医院中子照射器(IHNI-1)堆芯的物理方案设计
13.Core Neutron Space-time Kinetics of High Temperature Gas Cooled Reactor高温气冷堆堆芯中子时空动力学模拟计算
14.The comparison of the computational results for reactor core of PWR and BWR are also presented.文中还给出了压水堆和沸水堆堆芯计算实例的比较。
15.In this paper, the genetic algorithm( GA) has been used in reactor fuel management of core arrangement optimal calculation.应用遗传算法编制了核反应堆堆芯燃料管理优化计算程序。
16.reactor core radiation detector反应堆堆芯辐射检测仪
17.Design of Injection Mould with Multiple-cores Puller-Equi-spaced in Circumference,Core Pulling in Circular Arc Trace周向均布多型芯圆弧抽芯注塑模设计
18.Debug System of RAM Chip and Its ASIC Design;RAM芯片测试系统及其专用芯片设计
相关短句/例句
Nuclear design堆芯核设计
3)core steady-state design堆芯稳态设计
4)hydraulic core design堆芯水力学设计
5)core thermal design堆芯热工设计
6)core design constraint堆芯设计约束条件
延伸阅读
堆芯活性区分子式：CAS号：性质：反应堆的堆芯。是反应堆的核心部分。核燃料在这里发生自持链式裂变反应，并且不断地释放出能量。热中子反应堆活性区由核燃料、慢化剂、冷却剂、结构材料及保证反应堆启动、停闭、正常运行的控制棒等。天然铀石墨慢化水冷反应堆的堆芯就像一个石墨堆砌成的大型蜂窝煤，孔洞中装入燃料元件和通过冷却剂。
