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Double-loop nuclear reactor steam generating plant having a blowdown and drainage system

A technology for a steam generating device and a nuclear reactor, which is applied to the steam generation, the primary side of the steam generator, the reactor, etc., can solve the problems of increasing the normalization time of water chemical working conditions, insufficient purging water flow, increasing energy loss, etc. Effect of normalizing time, reducing energy loss, guaranteeing autonomy

Active Publication Date: 2020-04-17
原子能设计股份公司
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0018] Disadvantages of known technical solutions are the need to reduce the pressure to the parameters of the deaerator by purging the expander and, therefore, return the volume of purified water to the secondary circuit, the technical connection to the engine room and the dependence of the system on the equipment of the engine room Increased energy loss, because the steam discharged from the purging expander is carried out in the steam collector of the deaerator, and the backflow of the purge water is carried out in the expander of the deaerator or the drain pipe of the machine room, and at the same time purging Insufficient water flow increases normalization time for water chemistry conditions

Method used

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  • Double-loop nuclear reactor steam generating plant having a blowdown and drainage system

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Embodiment Construction

[0026] The operation of the steam generating device is as follows. From the first circuit the coolant enters the "hot" collector 3 of each steam generator 1, transfers its heat to the water of the steam generator 1, leaves after cooling through the "cold" collector 2 to the inlet of the main circulation pump (not shown in the figure). Raw material steam 1 is supplied to the first, second, third and fourth steam generators 1 through feedwater supply pipes 6, 7, 8 and 9, respectively. Dry steam is taken out from the steam collector 5 of each steam generator 1, and then the steam pipeline is sent to a steam turbine (not shown in the figure).

[0027]Purging involves continuous and periodic withdrawal of part of the boiler water from the areas most likely to accumulate corrosion products, salts and sludge. The continuous and periodic purge flow is split through the purge line 10 of the salt chamber 4 of each steam generator 1 , the purge line 11 from the lower casing busbar and ...

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Abstract

The proposed double-loop nuclear reactor steam generating plant having a blowdown and drainage system is implemented on the basis of a closed loop without the conventional blowdown tanks and is designed for maximum pressure of the working fluid in the steam generators. Steam generator blowdown water is brought together into a single line, cooled in a regenerative heat exchanger then in a blowdownand drainage aftercooler, and removed from the containment building. Outside the containment building, the steam generator blowdown water is fed for treatment into a system for the specialized treatment of steam generator blowdown water, designed for maximum pressure of the working fluid in the steam generators. After treatment, the blowdown water is returned to the containment building and, via the regenerative heat exchanger, to feed pipes of each steam generator. The technical result is an increase in steam generator blowdown flow, which leads to the accelerated normalization of the water chemistry conditions even in the event of significant deviations and, as a result, to an increase in the working life of each steam generator and of the steam generating plant as a whole, and also leads to a reduction in energy losses during the return of the treated blowdown water to the second loop, while at the same time rendering the system autonomous due to the absence of a link to turbine hall equipment.

Description

technical field [0001] The invention relates to the field of energy, and can be used in nuclear power plants with pressurized water-water power reactors and double-circuit nuclear power plants in steam generator sets with horizontal steam generators. Background technique [0002] In order to understand the description of the present invention, the terms used refer to: [0003] "Hot" collectors - collectors for steam generators, including coolant from the main reactor loop; [0004] The "cold" collector is the collector where the coolant from the primary circuit leaves the steam generator and enters the main circulation pump suction line; [0005] Collector "pockets" are stagnant areas that form between the primary reactor loop collector and the inner surface of the bottom of the steam generator, compromising purge quality; [0006] The "hot" bottom is the bottom of the steam generator, from the side of the "hot" collector; [0007] The "cold" bottom is the bottom of the s...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): F22B37/52F28G9/00G21C1/00
CPCF22B37/52F28G9/00G21C1/00Y02E30/30F22B37/54F22B37/483F22B35/004Y02E30/00G21C15/14G21C19/28G21D1/006
Inventor K·V·多罗钦A·V·舍斯塔科夫
Owner 原子能设计股份公司
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