CANDU nuclear power plant是什么意思

网络释义

用法例句

CSDVS fail open event analysis and handling measure of CANDU nuclear power plant;

重水堆核电站主蒸汽旁排阀故障分析和应对策略

A computer simulation and the statistical analysis of the inspected data on the typical points in the sea area nearby are developed to research the distribution of PWR nuclear power station's liquid ejections around the Daya Bay.

　为了研究压水堆核电站液态流出物在大亚湾海域的分布规律,采用计算机模拟和对周围海域中典型点的监测数据引进统计分析,建立了相应的数学模型。

STUDY ON CEMENT SOLIDIFICATION OF BORATE ACID LIQUID WASTES AND CONCENTRATES FROM PWR;

压水堆核电站产生的硼酸废液和浓缩废液的水泥固化研究

There exists probability of fuel assembly damage in PWR during refueling period.

在压水堆核电站换料的过程中存在燃料棒破损的可能。

Research of the Improvement of Adjuster Control of Heavy Water Reactor Power Plant;

重水堆核电站调节棒控制改进的研究

Study on Stock of Spare Parts of Qinsan Phase Ⅲ Candu Nuclear Power Station;

秦山三期重水堆核电站备品备件库存研究

CSDVS fail open event analysis and handling measure of CANDU nuclear power plant

重水堆核电站主蒸汽旁排阀故障分析和应对策略

ANALYSIS OF EFFLUENCE TRITIUM RELEASE FROM QINSHAN PHASE Ⅲ HEAVY WATER REACTOR

秦山三期重水堆核电站流出物氚排放的比较分析

The Application of Reliability Centered Maintenance in Fuelling Machine Head System of TQNPC Nuclear Power Station;

以可靠性为中心的维修在秦山三期重水堆核电站装卸料机系统上的应用研究

Qinshan Phase Ⅲ (CANDU) Nuclear Power Porject Quality Assurance

秦山三期(重水堆)核电站工程质量保证

A Progress Survey of Qinshan Phase Ⅲ (CANDU) Nuclear Power Plant Project

秦山三期(重水堆)核电站工程进展概况

Technical improvement in Qinshan Phase Ⅲ nuclear power plant after commercial operation

秦山三期(重水堆)核电站的技术改进

Study on Injection Cooling during Severe Accidents for the Pressurized Water Reactor Nuclear Power Plant;

压水堆核电站严重事故下注水冷却措施的研究

Simulation of Dynamic Mathematical Modeling for PWR Nuclear Power Plant Core Based on PSASP

基于PSASP的压水堆核电站堆芯建模及仿真研究

External Reactor Vessel Cooling Measure in Severe Accident for Pressurized Water Reactor Nuclear Power Plant

压水堆核电厂严重事故下堆腔注水措施研究

Aanalysis of Cementation Technology for Liquid Radioactive-Waste in PWR NPPs

压水堆核电站放射性废液水泥固化技术分析

a nuclear missile, power-station, reactor

核导弹、 电站、 反应堆

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

The Development of Fuel Rod Damage Character Analysis Code for Light Water Reactor of Nuclear Power Plant;

轻水堆核电站燃料棒破损性状分析程序的开发

Modeling and Controlling of PWR Nuclrear Power Plant and the Development of Simulation Software;

压水堆核电站的建模控制与仿真软件开发

The Research about Standardization Management of Radiation Protection in Pressurized Water Reactor Power Plant;

压水堆核电站辐射防护规范化管理研究

Nuclear Power Plant Simulation System and Its Improvement Based on PCTRAN;

基于PCTRAN的压水堆核电站模拟仿真系统及其改进