gas-cooled reactor

1. Probabilistic Safety Assessment Framework of Pebble-Bed Modular High-Temperature Gas-Cooled Reactor
   球床模块式高温气冷堆核电站的概率安全分析框架
2. Core Neutron Space-time Kinetics of High Temperature Gas Cooled Reactor Characteristic Behavior of Pebble-Bed Modular High-Temperature Gas-Cooled Reactor During Loss of Forced Cooling Accidents
   高温气冷堆堆芯中子时空动力学模拟计算球床模块式高温气冷堆失冷事故特性研究
3. Heavy-water-moderated gas-cooled reactor charging/ make-up flow [ reactor coolant system]
   重水慢化气冷反应堆上充／补给水流量〔反应堆冷却剂系统〕
4. Preliminary Study on Electromagnet Drive Mechanism in Reserve Shutdown System of High-Temperature Gas-Cooled Reactor
   高温气冷堆备用停堆系统电磁铁驱动机构初步研究
5. Analysis and Experiment of New Style Discharge Vessel in Reserve Shutdown System of High-Temperature Gas-Cooled Reactor
   高温气体冷却式反应堆高温气冷堆备用停堆装置新型供料器分析与试验
6. Preparation of ZrC Layer of Coated Fuel Particle for High-Temperature Gas-Cooled Reactor by Chemical Vapor Deposition With ZrCl_4 Vapor
   ZrCl4蒸汽沉积法制备高温气冷堆包覆燃料颗粒ZrC涂层
7. Operation Characteristics Study of Modular High Temperature Gas-Cooled Reactor Nuclear Power Plant Optimization of Leakage Calculation in RCP System of PWR
   模块式高温气冷堆核电站的运行特性研究压水堆核电厂一回路冷却剂泄漏率计算的优化
8. Maritime gas-cooled reactor critical experiment
   气冷式海上反应堆临界试验装置外接冷气式冷藏集装箱
9. The plan for developing a high-temperature gas-cooled reactor by Tsinghua University is a basic research project for the development of the civilian use of nuclear energy, but it is said to "aid in the development of nuclear weapons".
   清华大学发展高温气冷堆计划是一种民用核能开发试验，是核能开发的基础性研究，却被说成是“有助于发展核武器”。
10. Discontinuity Factor Applied in Three-Dimensional Diffusion Calculation for High-Temperature Gas-Cooled Reactor
    不连续因子应用于高温气冷堆三维扩散计算温斯凯尔改进型气冷反应堆
11. Pneumatic Conveying Technology Development and Application on High-Temperature Gas-Cooled Reactor
    气力输送技术发展及其在高温气冷堆上的应用
12. Discussion on Amount of Water Ingress Mass in Steam Generator Heat-Exchange Tube Rupture Accident of High-Temperature Gas-Cooled Reactor
    低压-高压热水换热器高温气冷堆蒸汽发生器换热管断裂事故进水量影响因素分析
13. Lumped-parameter simulation of the temperature feedback in a high temperature gas-cooled reactor
    高温气冷堆温度反馈的集总参数法模拟
14. Source and Effect of Tritium From Indirect Closed Brayton Cycle With High-Temperature Gas-Cooled Reactor
    高温气冷堆闭式布雷顿间接循环中氚的来源及其影响
15. Analysis of Characteristics of Different Working Fluids for Gas Turbine Cycle with High Temperature Gas-Cooled Reactor
    高温气冷堆气轮机循环的不同工质特性分析
16. Performance Analysis of Collimator in Online Burnup Measurement System for Pebble Modular High-Temperature Gas-Cooled Reactor With Monte-Carlo Method
    球床模块式高温气冷堆在线燃耗测量系统准直器性能的Monte-Carlo分析
17. Friction and Wear in High Temperature Gas-cooled Reactor ( HTGR) and Application of Surface Coatings
    高温气冷反应堆中的摩擦磨损及表面涂层技术的应用
18. Study of Magnetic Vortex Damper Used by Control-Rod System of High-Temperature Gas-Cooled Reactor
    高温气冷堆控制棒涡流限速器研究综述
19. Summary on The Prefeasibility Study of High Temperature Gas-Cooled Reactor Application in China
    高温气冷堆在我国应用的预可行性研究摘要
20. Study on characteristic of helium turbine with high temperature gas-cooled reactor
    高温气冷堆氦气轮机性能的初步研究
21. Development and Application Prospect of High Temperature Gas-cooled Reactor ( HTGR) Power Generation Technology
    高温气冷堆发电技术的发展和应用前景
22. The digital physical start-up system for nuclear reactor is introduced. The system was used successfully in physical start-up experiment of 10 MW high-temperature gas-cooled reactor.
    介绍了数字化物理启动系统的构成和基本工作原理，及其在10MW高温气冷实验堆物理启动试验过程中的首次成功运用。
23. In addition, the requirements of hydrogen production to reactors was brought forward and the advantages of high temperature gas-cooled reactor ( HTGR) for nuclear hydrogen production were put forward.
    提出了制氢过程对反应堆的要求，并介绍了高温气冷堆用于核能制氢的优势。
24. Research on Graphite Dust Behavior in 10MW High Temperature Gas-cooled Reactor
    10MW高温气冷堆中石墨粉尘行为研究
25. The helium purification system of the Helium Test Loop was constructed for demonstrating test of the High Temperature Gas-cooled Reactor.
    为了减少结构材料的腐蚀并验证高温气冷实验堆中的氦净化工艺，在氦气试验回路中设置了氦净化系统并进行了试验。
26. Three methods are introduced to calculate thermal radiation in High Temperature Gas-cooled Reactor ( HTGR).
    介绍了高温气冷堆非能动余热排出系统的辐射换热计算方法。
27. World Development of Nuclear Power System and High Temperature Gas-cooled Reactor
    世界核电发展趋势与高温气冷堆
28. In this paper, the features of the emergency power supply system of the 10MW High Temperature Gas-cooled Reactor ( HTR-10) are briefly introduced, and the reliability of the emergency power supply system of the HTR-10 is calculated using fault-tree analysis method.
    简单介绍了10MW高温气冷堆（HTR-10）电力系统的设计特点，并用故障树法对HTR－10交流安全母线供电的可靠性进行了定量的理论分析。
29. Model Analysis of Monte-Carlo Method for First Criticality Physics Calculation in Pebble Bed High Temperature Gas-Cooled Reactor
    球床式高温气冷堆初次临界物理计算的蒙特卡罗方法模型分析

noun

1. a nuclear reactor using gas as a coolant