安全壳

核电站安全壳内氢气扩散和燃烧的分析程序GASFLOW及其应用

GASFLOW : CFD code for the distribution and combustion of hydrogen in the containment

本文介绍了CIP安全壳系统方案选择、安全壳设计、安全壳设计压力的确定以及安全壳结构的计算分析。

This paper introduces the selection of the CIP containment system , the design of containment , the determination of the design pressure for the containment and the calculation analysis of the containment structure .

压水堆安全壳喷淋系统PSA敏感性初步分析

Preliminary PSA sensitivity analysis of the containment spray system of pressurized water reactors

PWR堆芯不同状况下安全壳内辐射水平的计算

PWR containment radiation levels calculation relate to core conditions

AC-600安全壳冷却系统水力特性研究

Studies of the hydrodynamic properties for containment cooling system in AC-600

据核分析师KennethD.Bergeron所言，日本福岛第一核电站的安全壳的结实程度比切尔诺贝利的好，却没三里岛的好。

According to nuclear analyst Kenneth D. Bergeron , the containment vessels at Daiichi are stronger than Chernobyl but not as robust as Three Mile Island .

研究还认为，Tagami关系式在计算主蒸汽管道断裂事故时安全壳压力峰值最为保守。

The Tagami correlation is the most conservative one in the main steam line break accident calculated .

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 ) .

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 .

方案3C表明10台氢气复合器在24h内有效地复合了667kg氢气，安全壳大空间最大氢气摩尔浓度为3.12%，安全壳内压力约为0.4MPa。

Solution 3_C indicates the 10 PARs have successfully recombined 667 kg of hydrogen within 24 hrs . As a result , maximum hydrogen concentration is as low as 3.12 % , pressure inside the containment accumulates to about 0.4 MPa .

本文对安全壳进行长期效应的分析结果表明，AC600非能动安全壳冷却系统能够保证安全壳的完整性。

This paper gets the conclusion that the PCCS can ensure the integrality of the AC600 containment in the long-term .

本文使用三维计算流体力学软件CFX研究安全壳内的氢气浓度分布，关注在产生的混合气体中水蒸气份额对安全壳内氢气分布的影响。

The flow and distribution of hydrogen are influenced by many factors , such as the access of the containment , the production rate of hydrogen , the steam fraction in the source mixture , and so on .

本文以清华大学5MW低温核供热试验堆工程安全壳设计为例，说明采用GB150进行大法兰设计的局限性。

Taken the containment vessel of5 MW Nuclear Heating Reactor as an example , which was designed by Tsinghua University , the shortage of the large-scale flange design based on GB150 is introduced .

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 .

该程序把钢安全壳内部的工质分为水蒸汽、不可凝干空气、连续相水和非连续相水，对气相引入e-k湍流计算模型并考虑由于气体浓度差引起的扩散效应。

The code classifies the working fluid in the containment into steam , uncondensable air , continuous liquid state water and discontinuous water and includes k-e turbulence model and diffusion model for main gas flow .

常规装药侵彻预应力钢筋混凝土安全壳数值模拟

Numerical simulation of General Bomb penetration into pre-stress reinforced concrete containment

高级弹道式再入系统安全壳喷淋再循环系统

Advance ballistic reentry system ( ABRS ) containment spray recirculation system

核电站预应力混凝土安全壳的老化因素研究

Aging Factors of Prestressed Concrete Containment Vessel in Nuclear Power Plant

严重事故下核电站安全壳内氢气分布及控制分析

Analysis of Hydrogen Distribution and Control in NPP Containment during Severe Accidents

核反应堆安全壳结构形式的选择

The Choice of the Containment Structure of Nuclear Power Reactor

非能动安全壳冷却系统水分配装置设计

Design of Water Distribution Device for Passive Containment Cooling System

尾矿浆全压滤工艺在全泥氰化炭浆厂的应用秦山二期安全壳超压后的过滤及卸压

Application of whole pressure filtration technology of tailing pulp in CIP plant

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

先进核电厂安全壳结构模型试验研究

Experimental research on advanced containment model of nuclear power plant

安全壳，是一个难以置信地强大的工具。

The Secure Shell , is an incredibly powerful utility .

安装并且运行安全壳通常是一件相当简单的事情。

Installing and running the secure shell , should be dead simple .

某核电站安全壳钢衬里的焊接

Steel liner welding of containment of a nuclear power station

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

预应力安全壳强度监测方法探讨

Exploring New Methods to Monitor the Strength of Prestressed Containment

我们现在知道了那些安全壳结构事实上是多么地难当重任。

We now know how inadequate those containment structures proved to be .