1、

Introduction of the Methods of Locating Failed Fuel Rods for Pressurized Water Reactor Plant

压水堆电站燃料元件破损定位探测方法介绍

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2、

The new developments of locating failed fuel rods technology for pressurized water reactor power plant which developed from the seventies till now are briefly introduced.

本文主要介绍70年代以来国外压水堆电站燃料元件破损定位探测技术的新发展。

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3、

Meanwhile, the four corners are respectively and symmetrically provided with positioning pin holes, so that the assembly of the pressure water reactor fuel element can be more flexible and convenient.

同时,在四角位置分别对称布置定位销孔,从而使压水堆燃料组件的安装更加灵活方便。

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4、

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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5、

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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6、

In 1950s, canned pump was applied on pressurized water reactor power plant.

上世纪五十年代,屏蔽泵首次应用于压水堆核电站。

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7、

Taking into account the advantages of fusion-fission hybrid reactor and problems of nuclear fuel supply and nuclear waste disposal, fusion-fission hybrid reactor and pressurized water reactor combined fuel cycle system concept was proposed.

同时考虑聚变-裂变混合堆的优势以及我国核电大发展过程中面临的核燃料供应和核废料处理问题,提出了聚变-裂变混合堆压水堆联合循环系统的概念。

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8、

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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9、

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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10、

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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11、

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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12、

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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13、

The Research about Standardization Management of Radiation Protection in Pressurized Water Reactor Power Plant; plant nuclear protection system

压水堆核电站辐射防护规范化管理研究反应堆辐射防护系统

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14、
15、

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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16、

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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17、

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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18、

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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19、

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

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20、

Advanced pressurized water reactor nuclear power plant construction is the strategic decision for the national response to climate changes and energy issues.

先进压水堆核电厂建设是国家应对能源问题和气候变化所采取的战略决策。

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