压水堆核电厂,PWR nuclear power plant
1)PWR nuclear power plant压水堆核电厂
1.Aging problems and life evaluation for the key metallic components inPWR nuclear power plant;压水堆核电厂关键金属部件的老化和寿命评估
英文短句/例句
1.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
2.Classification for the items of pressurized water reactor nuclear power plantsGB/T17569-1998压水堆核电厂物项分级
3.Design rules for mechanical components of pwr nuclear islemdsGB/T16702-1996压水堆核电厂核岛机械设备设计规范
4.Vibratory examination testing on anti-looseness performance of PWR internal fasteners压水堆核电厂堆内构件联接件防松性能振动考核试验
5.Radioactive source term of PWR nuclear power plant for operational statesGB/T13976-1992压水堆核电厂运行工况下的放射性源项
6.Study on the Hydrogen Source during Severe Accident for PWR;压水堆核电厂严重事故情况下氢气源项研究
7.Research on the Technique of Distributed Control System for Pressurized Water Reactor Coolant System;压水堆核电厂主冷却剂集散控制系统技术研究
PARISION OF ENVIRONMENTAL RADIOLOGICAL IMPACTS FOR THREE TYPES OF PWR NUCLEAR POWER PLANT三种压水堆核电厂的放射性环境影响比较
9.Optimization of Leakage Calculation in RCP System of PWR压水堆核电厂一回路冷却剂泄漏率计算的优化
10.The Principle and methodology of pressurized water reactor nuclear power plant core power capability verification for reload are introduced.介绍了压水堆核电厂换料堆芯功率能力验证分析的原理和方法。
11.The main factor of localization of nuclear island major equipment of PWR nuclear power plant--Large forgings压水堆核电厂核岛主设备国产化关注点——大型锻件
12.Numerical Simulation for Thermal Stratification of PWR NPP Pressurizer Surge Line压水堆核电厂稳压器波动管热分层现象数值分析
13.Effect of Natural Circulation on RCS Depressurization Strategy in PWR NPP压水堆核电厂自然循环对一回路卸压策略的影响
14.Analysis and Self-Development Research of Nulear Detecting Technology Applying to Candu Nuclear Power Plant;CANDU重水堆核电厂核测技术的分析和自主化研究
15.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
16.Program for testing radiation shields in light water reactors (LWR)GB/T13160-1991轻水堆核电厂辐射屏蔽检测大纲
17.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
18.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
相关短句/例句
900 MW PWR nuclear power plant900MW压水堆核电厂
3)pressurized water plant压水[堆]电厂
4)light water reactor nuclear power plant轻水堆核电厂
5)pressurized water reactor (PWR) nuclear power压水堆核电
6)SWESSAR (standard plant)斯通-韦伯斯特标准(压水堆)核电厂
延伸阅读
压水堆核电厂压水堆核电厂pressurized water reactor nuclear power plant裹2中国压水堆核电厂主要今傲衰┌────────┬────┬───┬─────┬─────┬────┬─────┬──────┐│参数名称│单位│秦山 │秦山第二核│大亚清1、 │岭澳1、 │台清马鞍山│田清(连云港)││││机组 │ 电厂机组│2号机组│2号机组 │1、2号机组│ l、2号机组│├────────┼────┼───┼─────┼─────┼────┼─────┼──────┤│电功率 │MW │3 10 │640│985│966 │951│1000│├────────┼────┼───┼─────┼─────┼────┼─────┼──────┤│热功率 │MW │1035 │1930 │2895 │2895│2785 │3000│├────────┼────┼───┼─────┼─────┼────┼─────┼──────┤│环路数 ││2 │2 │3 │3│3 │4│├────────┼────┼───┼─────┼─────┼────┼─────┼──────┤│每环路冷却剂流t │t/h │12000 │24000 │16754 │1 6754 │16530 │21500│├────────┼────┼───┼─────┼─────┼────┼─────┼──────┤│反应堆运行压力 │MPa │15。2 │1 5.5 │15.2 │15.2│15.7 │15.7│├────────┼────┼───┼─────┼─────┼────┼─────┼──────┤│冷却荆进口温度 │℃ │287.9 │1 93.8│292.4 │293.4│291.7 │289.7│├────────┼────┼───┼─────┼─────┼────┼─────┼──────┤│冷却剂出口温度 │℃ │316.1 │327.2 │3276 │328 │328.7 │321 │├────────┼────┼───┼─────┼─────┼────┼─────┼──────┤│落汽压力│MPa │5。
