water reactor

The utility model relates to the field of nuclear fuel components, in particular to an upper tube seat of a pressure water reactor fuel element.

本实用新型涉及核燃料元件领域，具体涉及一种压水堆燃料组件上管座。

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Quality Assurance on Manufacture Stage of Pressure Vessel for Water Reactor

水堆压力容器制造阶段的质量保证

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This paper describes the model of calculating the flux distribution in two dimensional hexagonal geometry light water reactor fuel assembly by interface current method.

利用界面流法计算两维六角形轻水堆燃料组件内中子通量密度分布。

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Steam generator ( SG) is one of main equipments in the pressurized water reactor ( PWR) nuclear power plant, but also it is a pivotal equipment which brings heat from reactor core to the secondary loop coolant by primary loop water.

蒸汽发生器是压水堆核动力装置中的主要设备之一，也是把一回路冷却剂从反应堆堆芯带出的热量传给二回路水的关键设备。

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The load following of pressurized water reactor ( PWR) is studied. A three-dimensional fuzzy control system of boron concentration is designed.

对压水堆负荷跟踪运行进行了研究，提出将一种三维模糊控制系统应用于硼浓度自动调节的设计方案。

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Application and Discussion of Charging Pump Decontamination for Pressurized Water Reactor Nuclear Power Station

压水堆核电站上充泵的去污实践及其理论探讨

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Fuel assembly grids of pressurized water reactor strengthen the coolant mixing around rod through mixing structure.

压水堆燃料组件格架上交混叶片的大小和形状影响其交混能力和流动阻力.

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Simulation of Gas Distribution Inside a Water Reactor Containment

水堆安全壳内气体分布模拟计算

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Improving gradually fuel burn-up is one of the paths which can lower the expense on fuel cycle cost for light water reactor.

逐渐提高燃料燃耗是降低轻水堆燃料循环费用的途径之一。

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A below of cooling water pipes of acrylonitrile reactor bursted.

某化工厂丙烯腈反应器冷却水管弯管部位发生爆管.

Transformation of Stirring Reactor of Water Cooling Crystallization Cans

水冷结晶罐搅拌器的改造

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Project with China's own brands and using the advanced pressurized water reactor nuclear power technology-CPR 1000.

项目采用具有我国自主品牌的先进压水堆核电技术 —— CPR1000.

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Reload design is directly related to the economy and safety of a Pressurized Water Reactor ( PWR). Because of the large search space and large number of optimization variables, PWR LP search is a very complicated combinatorial problem.

压水堆堆芯换料方案设计关系到核电厂运行的安全性和经济性，但由于优化变量众多搜索空间异常庞大，是一个十分复杂的组合优化问题。

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Preliminary study on the use of coated fuel particles in the fabrication of water reactor fuel element

包覆燃料颗粒在水堆中应用的初步研究

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In this work, a tight pitch lattice and mixed fuel assemblies pressured heavy water reactor concept was investigated.

在这项工作中，一种紧沟天窗与混合燃料集束压力重水反应堆的概念被调研。

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Research on Mathematical Model of Thermo-Economics Analysis for Pressurized Water Reactor Nuclear Cogeneration Plant

核供热反应堆热电联产实验研究热电联产压水堆核电机组热经济性定量分析模型

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Experimental investigation on 1% small break loss of coolant accident of pressurized water reactor cold leg

PWR冷管段1%小破口失水事故实验研究

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We investigated the hydraulic loading, water temperature and filter height of reactor through the experiment.

试验考察了进水水温、水力负荷和滤层高度对反应器处理效能的影响。

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Casting Technique for Primary Coolant Piping for Pressurized Water Reactor Power Plant and Its Localization

压水堆一回路管道的铸造工艺及其国产化

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Study on Primary Coolant System Depressurization Effect Factor in Pressurized Water Reactor

压水堆一回路卸压措施影响因素研究

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Pressurized Water Reactor Nuclear Power Plant Model for Power System Dynamic Simulation

用于电力系统动态模拟的压水堆核电站数学模型

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Annealing Characteristic Comparison of NTD FZ ( H) Si Irradiated in Light water reactor and Heavy water reactor

轻/重水堆中子辐照氢区熔硅退火特性的比较

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Research on Advanced Pressurized Water Reactor Fuel Management Calculation Method and Program Development

先进的压水堆燃料管理计算方法研究及软件研制

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Measurement of neutron energy spectrum at thermal column of heavy water reactor

重水反应堆热柱中子能谱测量

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A new method is provided for the determination of the photoneutron background source in Heavy Water Reactor.

此外，我们还从对正常运行状态下的实时反应性值的统计分析得到了光激中子源本底的大小，为确定重水堆光激中子源大小提供了一个新的方法。

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The momentum integral method is applied in the frame of safety analysis of pressure water reactors under hypothetical loss of coolant accident ( LOCA) conditions to simulate numerically film condensation, rewetting and vaporization on the inner surface of a pressure water reactor containment.

采用动量积分方法分析压水堆发生失水事故时在安全壳的内表面上的液膜凝结、再浸润和蒸发过程。

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The waste water containing radioactive tritium will be generated when the nuclear reactor is in operation.

核反应堆在工作过程中产生大量带有放射性的含氚废水.

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The neutron energy spectrum at the thermal column of the heavy water reactor of China Institute of Atomic Energy has been measured by using a mechanical chopper by time-of-flight method. The result shows that the energy spectrum deviates from Maxwell distribution.

利用飞行时间法，用机械选择器测量了中国原子能科学研究院重水反应堆热柱的中子能谱.结果表明，该热柱能谱和理论Maxwel谱有偏离。

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The reactor cooling system re-circulates water, so its return would simplify recovery operations.

反应堆的冷却系统将水不断进行循环，冷却系统恢复后可以简化复原工作。

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Pressurized water reactor fuel performance problems connected with fuel cladding corrosion processes.

与燃料包壳腐蚀过程有关的压水堆燃料性能问题.

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