Chemical Reactor Design ── Fluid Bed Reactor Design

Construct the Transformer and Reactor Design and Development System with Pro/ ENGINEER

用Pro/ENGINEER构建变压器及电抗器产品设计开发系统

Problems in Outdoor Dry Type Air Core Reactor Design

户外干式空心电抗器设计的若干问题

A flawed reactor design and inadequately trained workers caused the Chernobyl accident.

存在缺陷的核反应堆设计和训练不足的员工是造成切尔诺贝利核事故的原因。

And this is a challenge of reactor design.

这是对反应堆设计的一个挑战。

Nuclear Reactor Graph and Nuclear Reactor Cross-Section

核反应图象与核截面

The model established consists of five grades LLDPE products from the gas phase fluidized bed technology, including the reactor, gas cycle/ reactor cooling and the downstream discharges units.

建立的模型中包含了气相流化床工艺LLDPE的五个牌号，包括反应器、气体循环/反应器冷却和下游的排放气回收部分。

The problem of natural convection flow and heat transfer in a cavity has extensive applicative background in application engineering, such as heat shield of building, safe design of nuclear reactor, microelectronic device cooling etc, so it is noticed more and more widely.

封闭腔内自然对流换热问题在工程实际问题中有着广泛的应用背景，例如建筑物隔热、核反应堆安全设计、微电子设备的冷却等，因而日益得到广泛的注意。

Gas-liquid two phase flow in porous media is a central topic in many scientific and technology fields, such as the research of new concept nuclear reactor type, the cooling of debris bed, the reactor in petroleum and chemical industry.

多孔介质内的气液两相流动是许多科学和技术领域关心的一个中心话题，包括新概念反应堆堆型的研究、碎片床的冷却、石油和化学工业中的反应床都涉及多孔介质气液两相流。

In the research of new-concept reactor, debris bed cooling, and chemical industry, gas-liquid two-phase flow in porous media are involved.

在新概念反应堆堆型的研究、碎片床的冷却、石油和化学工业中的反应床中都涉及多孔介质气液两相流。

Design Consideration of On-line Burnup Measurement System for High Temperature Gas-cooling Reactor: Influence of Cooling Time for Fuel Sphere on Burnup Measurement

高温气冷堆在线燃耗测量系统的设计考虑&燃料球的冷却时间对燃耗测量的影响

In the reactor, the cooling process is a complicated process, not only because of the natural convection which is caused by the temperature difference with the volume heat source, but also the bubble drived flow by the fission gas.

在医用溶盐池中，溶液的冷却过程不仅涉及到由于内热源加热产生的温度差而引起的自然对流，而且涉及到池内裂变气体引起的气泡驱动流。

It is pointed out that the goal to prolong its life, save energy and reduce loss can be attained through improving the reactor winding and cooling system.

阐明了可以通过对电抗器绕组及冷却系统改进，以达到节能降耗，延长使用寿命的目的。

It goes into quite a lot of detail about the reactor and the cooling systems and how the systems are interconnected.

它也详细的谈到了反应堆，以及冷却系统，以及系统是，如何相互连接的。

Transformation of Stirring Reactor of Water Cooling Crystallization Cans

水冷结晶罐搅拌器的改造

Reactor core isolation cooling system

反应堆堆芯隔离冷却系统

The recirculating pit filter in containment is an important equipment of safety system in nuclear power plant. In the recirculating condition, it influences the operation of emergency reactor core cooling system and spray system in containment.

安全壳再循环地坑滤网是核电厂安全系统的重要设备，再循环工况下它的工作状况直接影响到安全注射系统（应急堆芯冷却系统）、安全壳喷淋系统的正常运行。

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。

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。

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

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