反应堆安全壳

  • 网络Reactor containment
反应堆安全壳反应堆安全壳
  1. 飞机撞击核反应堆安全壳的动力学分析

    Dynamic Analysis of Reactor Containment Subjected to Aircraft Impact Loading

  2. 大亚湾核电站反应堆安全壳预应力技术

    The prestressing system for reactor containment of Daya Bay Nuclear Power Station

  3. DYTRAN软件分析了飞机撞击反应堆安全壳的动力学问题,给出了混凝土的变形图和撞击物的速度变化曲线,比较了选用不同材料模式的计算结果,并与经验公式的结果进行了对比。

    The displacement of concrete and velocity curve of airplane is ob-tained . The results of the different material model are compared with empirical formula .

  4. 核反应堆安全壳结构形式的选择

    The Choice of the Containment Structure of Nuclear Power Reactor

  5. 反应堆安全壳密封(泄漏)试验的原理与分析方法

    The Fundament and Analysis Method of Reactor Containment Leakage Test

  6. 低温核供热反应堆安全壳

    Containment for low temperature district nuclear - heating reactor

  7. 反应堆安全壳的局部泄漏率试验

    Local Leakage Rate Testing for Reactor Containment

  8. 飞机撞击核反应堆安全壳荷载-时间曲线的确定

    The determination of load-time curve for a reactor containment which undergoes the impact of an airplane

  9. 本文用时域边界积分方程提出研究半球形核反应堆安全壳在爆炸冲击波作用下动力响应分析的计算模型。

    This paper is concerned with the transient responses of semisphere containment structure of nuclear reactor to a blast wave by the boundary element method in time domain .

  10. 而大多数混凝土结构都是处于复杂应力状态的,如常见的剪力墙结构,水坝、桥梁、核反应堆安全壳、采油平台等。

    Actually considerable structural elements such as shear wall , dam , bridge , safety shell of nuclear reactor , offshore platform and so on , are generally working under multiaxial stress condition .

  11. 福岛核电站所属的东京电力公司的一名发言人称,周三清晨,第四反应堆安全壳外部再次发生火情。

    The outer housing of the containment vessel at the No4 reactor erupted in flames early Wednesday , said Hajimi Motujuku , a spokesman for the plant 's operator , Tokyo Electric Power Co.

  12. 桥梁、吊车梁、轨枕、海洋结构、压力机构和核反应堆安全壳等经常承受循环次数较多而重复荷载较大的结构,在长期的反复荷载的作用下极容易发生疲劳破坏。

    Bridge , crane beam , sleeper , ocean structure , pressure institution and nuclear reactor safety shell are often endured stress from many circle times and biggish repetition loading , and fatigue collapse is very easy accrued because of long and repeating loading .

  13. 这些结论,为受高温后的混凝土结构,如火灾后的建筑物、烟囱、核反应堆安全壳等处于双轴拉压组合荷载作用下混凝土结构的设计、分析提供理论依据。

    A failure criterion is established in principal stress space and octahedral stress space . The present work provides theoretic basis for the design and analysis of concrete structures under biaxial tension-compression combination loads , such as buildings after fire , chimneys and safety shell of nuclear reactor .

  14. 一种可能的新做法是,向反应堆的安全壳大量注水,浸没放置燃料的钢质压力容器。

    One possible new approach is to flood the reactors ' containment chambers with enough water to immerse the steel pressure vessels that hold the fuel .

  15. 含有不凝性气体的蒸汽冷凝是先进反应堆非能动安全壳冷却系统(PCCS)中重要的换热方式,是当前核反应堆热工水力学研究的一个热点。

    Condensation of steam in the presence of noncondensable gases is an important heat transfer mode in the passive containment cooling system ( PCCS ) .

  16. 用具有反照率近似的蒙特卡罗方法编制的RSCAM程序系统计算反应堆堆腔内及安全壳操作大厅中的中子辐射场。

    RSCAM program system , using Monte Carlo method with albedo approach , is used to calculate streaming neutron radiation field in reactor cavity and containment operating hall .