reactor vessel的例句大全

Special research on sealing behaviour for reactor vessel of 300 MWe nuclear power plant

30万千瓦核电站反应堆压力容器密封性能研究

The diagram of the reactor vessel internals is used as a reference. spent or irradiated cartridge of nuclear reactors

将反应堆容器与内部构件的简化图作为参考。核试验反应堆使用过或辐照过的容器

Radioactivity measurement on the reactor vessel of the heavy water research reactor

研究性重水反应堆内壳放射性的测量

Reactor vessel water level indication system

反应堆容飘位指示系统

So annealing is another solution to reactor vessel integrity issues if replacement is not an option.

所以退火处理是另外解决反应堆管道，整体性问题的方法，如果替换不可行。

In Japan and the United States, a thick concrete and steel containment vessel surrounds the reactor vessel.

在11区和美帝，反应容器一般被一层厚厚的钢筋混凝土包裹。

The fuel rods are loaded vertically into the reactor vessel in a precise grid pattern known as the reactor core.

这些燃料棒被精确地排成格子结构，然后被竖直地插入反应容器。

The Level Monitor System for Nuclear Reactor Vessel During and After Accident

核反应堆液位事故后监测系统

Site Welding Technology on Hot Wall Hydrogenation Reactor Vessel

热壁加氢反应器的现场组焊技术

Reactor vessel cooling system is one of the important auxiliary systems in the primary system of China experimental fast reactor ( CEFR), which can cool the reactor vessel in various conditions.

堆容器冷却系统是中国实验快堆（CEFR）一回路系统中的重要辅助系统之一，用于在各种工况下对反应堆堆容器进行冷却。

Disposition of Used Reactor Vessel Head

反应堆压力容器旧顶盖处置

The Technology of Assembling and Welding for the Large "FBR" Reactor Vessel

快速沸水型反应堆容器的组装与焊接

Prestressed concrete reactor vessel

预应力混凝土反应堆容器

We notice that the differences are that the water in the reactor vessel is not allowed to boil.

我们注意到不同就在于，在反应堆管道的水是不允许油的。

Probability Analysis for External Reactor Vessel Cooling Effectiveness under Severe Accident

严重事故下反应堆压力容器外水冷有效性概率分析

Installation of reactor vessel support ring

反应堆压力容器支承环安装

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

The basic idea is to freeze the aqueous phase of traditional O/ W system to the ice, so that the monomer droplets change into micro reactor vessel with "hard wall".

其基本思路是通过速冻过程，将传统O/W体系中的水相固化为冰，使单体液滴成为具有硬壁的微反应容器。

There are many uncertainties in severe accident phenomena which affect the effectiveness of External Reactor Vessel Cooling ( ERVC) measurement.

核反应堆的严重事故现象具有较大不确定性，它们影响到反应堆压力容器外水冷措施的有效性。

Analysis of Events Sequences of Reactor Vessel Thermal Shock

反应堆容器热冲击事件列分析