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Steam generator feed-water temperature control simulation system

A technology for steam generator and control simulation, which is applied in the direction of using electric mode for temperature control, auxiliary controller with auxiliary heating device, etc., which can solve the problem of increased difficulty in controlling the temperature of steam generator feed water and changes in the flow rate of steam generator feed water Large problems, to achieve the effect of improving energy utilization, rapid adjustment, and large flow range

Active Publication Date: 2017-09-08
NUCLEAR POWER INSTITUTE OF CHINA
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  • Description
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Problems solved by technology

[0003] The purpose of the present invention is to provide a steam generator feedwater temperature control simulation system to solve the problem in the prior art that the steam generator feedwater flow rate corresponding to different design conditions varies greatly, resulting in increased difficulty in controlling the steam generator feedwater temperature

Method used

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  • Steam generator feed-water temperature control simulation system

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Embodiment

[0018] Such as figure 1 As shown, the present invention is a steam generator feed water temperature control simulation system, the main feed water pipe of the steam generator is connected with the main feed water pump 1 and the secondary side inlet 10 of the steam generator, and is divided into two parallel branches in the middle, one flow After passing through the regenerator 2, the fluid is heated by the steam on the other primary side of the regenerator 2, and then merges with the fluid of another branch, that is, the feedwater bypass, and flows to the secondary side inlet 10 of the steam generator; the feedwater bypass is installed on the feedwater bypass The flow regulating valve 3 is used to adjust the flow rate of the feed water bypass, and the heat exchange temperature measuring device 4 is installed on the outlet pipe of the regenerator 2 to measure the temperature of the feed water coming out of the regenerator 2. The inlet temperature measuring device 5 is installed...

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Abstract

The present invention discloses a steam generator feed-water temperature control simulation system. A main feed-water pipe, arranged between a main feed pump and the secondary side inlet of a steam generator, passes through a heat regenerator, the secondary side outlet of the steam generator is connected with two parallel branch pipelines, one of the two parallel branch pipelines passes through the steam flow control valve of a main steam pipeline and is connected to a condenser, and the other one of the parallel branch pipelines passes through a steam by-pass stop valve, a steam by-pass flow control valve and the heat regenerator in order and then is connected with the condenser. According to the invention, high-temperature steam generated by the steam generator is employed as a heating source to perform preheating of feed water entering the steam generator to eliminate energy consumption caused by preheating depending on an extra power supply and improve the energy utilization rate of a test device, and high-temperature steam preheating output by the steam generator itself is employed to realize feeding water temperature control in a large flow variation range. The mode of combination of steam by-pass adjustment and feed-water by-pass adjustment is employed to rapidly, effectively and accurately realize adjustment of the feed-water temperature of the steam generator.

Description

technical field [0001] The invention relates to the field of test and research equipment related to a nuclear reactor secondary loop system, in particular to a steam generator feed water temperature control simulation system. Background technique [0002] With the development of nuclear energy technology, nuclear reactor technology has gone through three generations. The current mainstream reactor technology is the third-generation nuclear reactor technology. All countries are currently developing fourth-generation nuclear reactors and other new nuclear reactors, such as modular small reactors. For the research and development of each new type of reactor, it is necessary to conduct experiments to verify the steady state and transient design parameters of this type of reactor, especially the operating characteristics of the steam generator during the steady state and transient state. When studying the operating performance of steam generators, it is necessary to conduct exper...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G05D23/30
CPCG05D23/30
Inventor 鲁晓东张妍昝元峰黄志刚仇子铖李朋洲胡俊杨祖毛
Owner NUCLEAR POWER INSTITUTE OF CHINA
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