CN207486768U - A kind of continuous steam generator of nuclear power station - Google Patents

A kind of continuous steam generator of nuclear power station Download PDF

Info

Publication number
CN207486768U
CN207486768U CN201721478763.2U CN201721478763U CN207486768U CN 207486768 U CN207486768 U CN 207486768U CN 201721478763 U CN201721478763 U CN 201721478763U CN 207486768 U CN207486768 U CN 207486768U
Authority
CN
China
Prior art keywords
header
steam
steam generator
heat
reallocation
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
CN201721478763.2U
Other languages
Chinese (zh)
Inventor
武心壮
施伟
邱健
夏栓
黄若涛
倪超
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Shanghai Nuclear Engineering Research and Design Institute Co Ltd
Original Assignee
Shanghai Nuclear Engineering Research and Design Institute Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Shanghai Nuclear Engineering Research and Design Institute Co Ltd filed Critical Shanghai Nuclear Engineering Research and Design Institute Co Ltd
Priority to CN201721478763.2U priority Critical patent/CN207486768U/en
Application granted granted Critical
Publication of CN207486768U publication Critical patent/CN207486768U/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The utility model provides a kind of continuous steam generator of nuclear power station, including:Feed water distributor box, heat-transfer pipe, reallocation header and steam header;The feedwater distributor box, reallocation header and steam header are sequentially communicated;Wherein, the feedwater distributor box is connected by the heat-transfer pipe with the reallocation header, and the reallocation header is connected by the heat-transfer pipe with the steam header.The continuous steam generator of nuclear power station provided by the utility model, it is different from traditional continuous steam generator, reallocation header is added in once through steam generator, for alleviating due to the uneven flow resistance problem of non-uniform brought that flows and conduct heat, particularly alleviate under low-power and steam quality unevenness problem during Load Regulation, header of reallocating simultaneously is also provided with heat-transfer pipe manhole, it is operated convenient for the inservice inspection and plugging of heat-transfer pipe, which improves stabilization and the safety of steam generator operation.

Description

一种核电站的直流式蒸汽发生器A once-through steam generator for a nuclear power plant

技术领域technical field

本实用新型涉及核电站蒸汽发生器,具体涉及一种核电站的直流式蒸汽发生器。The utility model relates to a steam generator for a nuclear power plant, in particular to a direct-flow steam generator for a nuclear power plant.

背景技术Background technique

在压水堆核电厂中广泛使用的蒸汽发生器有两种,一种是带汽水分离器的饱和蒸汽发生器,一种是直流式蒸汽发生器。对于饱和式蒸汽发生器,一回路水在由管板连接的U型管组成的管束内流动,在管束上方装有汽水分离器和蒸汽干燥装置。饱和蒸汽发生器具有传热系数大,蓄水容积大、对给水和蒸汽控制系统要求不高等优点,但是饱和蒸汽温度和压力相对较低,对应的二回路效率低,此外蒸汽发生器结构复杂,体积大。直流式蒸汽发生器出口得到的通常是过热蒸汽,有较高的热效率,它的传热管是直管式,且不带汽水分离器、蒸汽干燥装置等,便于制造和组装。但是直流蒸汽发生器的二回路水容量小,对给水控制的要求很高。There are two types of steam generators widely used in pressurized water reactor nuclear power plants, one is a saturated steam generator with a steam-water separator, and the other is a once-through steam generator. For the saturated steam generator, the water in the primary circuit flows in the tube bundle composed of U-shaped tubes connected by the tube plate, and a steam-water separator and a steam drying device are installed above the tube bundle. The saturated steam generator has the advantages of large heat transfer coefficient, large water storage volume, and low requirements on the feed water and steam control system, but the saturated steam temperature and pressure are relatively low, and the corresponding secondary circuit efficiency is low. In addition, the structure of the steam generator is complex, Big size. The outlet of the once-through steam generator is usually superheated steam, which has high thermal efficiency. Its heat transfer tube is a straight tube without a steam-water separator, steam drying device, etc., which is easy to manufacture and assemble. However, the water capacity of the secondary circuit of the once-through steam generator is small, and the requirements for water supply control are very high.

近些年,小型反应堆得到了快速的发展,由于直流蒸汽发生器具有体积小、热效率高等优点被广泛采用。但是由于小型反应堆功率小,负荷调节要求比较高,导致直流蒸汽发生器传热管中的流动和换热不均匀更加明显。In recent years, small reactors have developed rapidly, and once-through steam generators have been widely used due to their small size and high thermal efficiency. However, due to the small power of the small reactor, the load adjustment requirements are relatively high, resulting in more obvious flow and heat transfer inhomogeneity in the heat transfer tube of the once-through steam generator.

实用新型内容Utility model content

本实用新型针对现有技术的不足,提出一种核电站的直流式蒸汽发生器。Aiming at the deficiencies of the prior art, the utility model proposes a direct-flow steam generator of a nuclear power plant.

本实用新型提供一种核电站的直流式蒸汽发生器,其包括:给水分配箱、传热管、再分配联箱和蒸汽集箱;所述给水分配箱、再分配联箱和蒸汽集箱依次连通;其中,所述给水分配箱通过所述传热管与所述再分配联箱连通,所述再分配联箱通过所述传热管与所述蒸汽集箱连通。The utility model provides a once-through steam generator of a nuclear power plant, which comprises: a water supply distribution box, a heat transfer pipe, a redistribution header and a steam header; the water supply distribution box, the redistribution header and the steam header are connected in sequence ; Wherein, the water distribution tank communicates with the redistribution header through the heat transfer pipe, and the redistribution header communicates with the steam header through the heat transfer pipe.

优选地,还包括传热管检修孔;所述检修孔与所述再分配联箱联通,所述检修孔通过法兰密封。Preferably, a heat transfer pipe inspection hole is also included; the inspection hole communicates with the redistribution header, and the inspection hole is sealed by a flange.

优选地,所述给水分配箱经配置以将给水均匀分配至与所述再分配联箱连通的传热管。Preferably, the feed water distribution tank is configured to evenly distribute feed water to heat transfer tubes in communication with the redistribution header.

优选地,所述蒸汽集箱经配置以对进入主蒸汽管道的蒸汽均匀混合。Preferably, the steam header is configured to uniformly mix the steam entering the main steam conduit.

与现有技术相比,本实用新型具有以下有益效果:Compared with the prior art, the utility model has the following beneficial effects:

1、本实用新型提供的核电站的直流式蒸汽发生器,与传统的直流式蒸汽发生器不同,在直流蒸汽发生器中增设再分配联箱,用于缓解由于流动和传热不均带来的流动阻力不均匀问题,特别是缓解在低功率下和负荷调节时蒸汽品质不均问题,同时再分配联箱还设置了传热管检修孔,便于传热管的在役检查和堵管操作,该设计提高了蒸汽发生器运行的稳定和安全性。1. The once-through steam generator of the nuclear power plant provided by the utility model is different from the traditional once-through steam generator. A redistribution header is added to the once-through steam generator to alleviate the problems caused by uneven flow and heat transfer. The problem of uneven flow resistance, especially to alleviate the problem of uneven steam quality under low power and load adjustment, and at the same time, the redistribution header is also equipped with inspection holes for heat transfer tubes, which is convenient for in-service inspection and plugging operations of heat transfer tubes. This design improves the stability and safety of the steam generator operation.

附图说明Description of drawings

图1为符合本实用新型优选实施例的核电站的直流式蒸汽发生器示意图。Fig. 1 is a schematic diagram of a once-through steam generator of a nuclear power plant according to a preferred embodiment of the present invention.

其中:1—反应堆冷却剂入口;2—反应堆冷却剂流道;3—直流式蒸汽发生器;4—反应堆冷却剂出口;5—给水;6—给水分配箱;7—传热管;8—传热管检查孔;9—再分配联箱;10—蒸汽集箱;11—主蒸汽。Among them: 1—reactor coolant inlet; 2—reactor coolant flow channel; 3—once-through steam generator; 4—reactor coolant outlet; 5—feed water; 6—feed water distribution box; 7—heat transfer tube; 8— Inspection hole of heat transfer tube; 9—redistribution header; 10—steam header; 11—main steam.

具体实施方式Detailed ways

为使本实用新型的上述目的、特征和优点能够更加明显易懂,下面结合附图和具体实施方式对本实用新型作进一步详细的说明。In order to make the above purpose, features and advantages of the utility model more obvious and understandable, the utility model will be further described in detail below in conjunction with the accompanying drawings and specific embodiments.

如图1所示,核电站的直流式蒸汽发生器其包括:给水分配箱6、传热管7、再分配联箱9和蒸汽集箱10;所述给水分配箱6、再分配联箱9和蒸汽集箱10依次连通;其中,所述给水分配箱6通过所述传热管7与所述再分配联箱9连通,所述再分配联箱9通过所述传热管7与所述蒸汽集箱10连通。As shown in Figure 1, the once-through steam generator of a nuclear power plant comprises: a feedwater distribution box 6, a heat transfer pipe 7, a redistribution header 9 and a steam header 10; the feedwater distribution box 6, a redistribution header 9 and The steam headers 10 are connected in sequence; wherein, the water distribution tank 6 communicates with the redistribution header 9 through the heat transfer tube 7, and the redistribution header 9 communicates with the steam header 9 through the heat transfer tube 7 The header 10 is connected.

核电站的直流式蒸汽发生器还包括传热管检修孔8,便于传热管的在役检查和堵管操作。检修孔8与再分配联箱9联通,检修孔8通过法兰密封The once-through steam generator of the nuclear power plant also includes a heat transfer tube inspection hole 8, which is convenient for the in-service inspection and plugging operation of the heat transfer tube. The inspection hole 8 is in communication with the redistribution header 9, and the inspection hole 8 is sealed by a flange

所述给水分配箱6经配置以将给水均匀分配至与所述再分配联箱9连通的传热管7,使给水均匀的进入蒸汽发生器传热管。The feed water distribution box 6 is configured to evenly distribute the feed water to the heat transfer tubes 7 communicating with the redistribution header 9, so that the feed water evenly enters the heat transfer tubes of the steam generator.

所述蒸汽集箱10,使蒸汽进入主蒸汽管道之前混合均匀、压力稳定。The steam header 10 makes the steam mix uniformly and the pressure stable before entering the main steam pipeline.

核电站的直流式蒸汽发生器中的再分配联箱9,用于缓解由于流动和传热不均带来的流动阻力不均匀问题,特别是缓解在低功率下和负荷调节时蒸汽品质不均问题,该设计提高了蒸汽发生器运行的稳定和安全性。The redistribution header 9 in the once-through steam generator of a nuclear power plant is used to alleviate the problem of uneven flow resistance caused by uneven flow and heat transfer, especially to alleviate the problem of uneven steam quality at low power and load regulation , the design improves the stability and safety of the steam generator operation.

具体的,如图1所示,本实施例的核电站的直流式蒸汽发生器,主要包括给水分配箱6、传热管7、再分配联箱9、传热管检查孔8和蒸汽集箱10。正常运行情况下,反应堆冷却剂热流体从反应堆冷却剂入口1进入反应堆冷却剂流道2,将热量传递给直流式蒸汽发生器3后,冷流体从反应堆冷却剂出口4流出。给水5进入给水分配箱6,给水均匀的进入传热管7,被加热后进入再分配联箱9,流体在再分配联箱9中混合均匀后进入下一段传热管,如有需要,可设置多个再分配联箱,以缓解由于流动和传热不均带来的流动阻力不均匀问题,特别是缓解在低功率下和负荷调节时蒸汽品质不均问题。流体经过最后一段传热管后进入蒸汽集箱10,混合稳定后进入主蒸汽管道。当需要对传热管进行检修或堵管操作时,打开传热管检修孔8进行在役检查和堵管。Specifically, as shown in Figure 1, the once-through steam generator of the nuclear power plant of this embodiment mainly includes a feed water distribution box 6, a heat transfer pipe 7, a redistribution header 9, a heat transfer pipe inspection hole 8 and a steam header 10 . Under normal operating conditions, the reactor coolant hot fluid enters the reactor coolant flow channel 2 from the reactor coolant inlet 1, and after transferring heat to the once-through steam generator 3, the cold fluid flows out from the reactor coolant outlet 4. The feed water 5 enters the feed water distribution box 6, and the feed water enters the heat transfer tube 7 evenly, and enters the redistribution header 9 after being heated. The fluid is mixed evenly in the redistribution header 9 and then enters the next heat transfer tube. Set up multiple redistribution headers to alleviate the problem of uneven flow resistance caused by uneven flow and heat transfer, especially to alleviate the problem of uneven steam quality at low power and load regulation. The fluid enters the steam header 10 after passing through the last heat transfer tube, and enters the main steam pipeline after mixing stably. When the heat transfer tube needs to be overhauled or plugged, the heat transfer tube inspection hole 8 is opened for in-service inspection and tube plugging.

与现有技术相比,本实施例具有以下有益效果:Compared with the prior art, this embodiment has the following beneficial effects:

1、本实施例提供的核电站的直流式蒸汽发生器,与传统的直流式蒸汽发生器不同,在直流蒸汽发生器中增设再分配联箱,用于缓解由于流动和传热不均带来的流动阻力不均匀问题,特别是缓解在低功率下和负荷调节时蒸汽品质不均问题,同时再分配联箱还设置了传热管检修孔,便于传热管的在役检查和堵管操作,该设计提高了蒸汽发生器运行的稳定和安全性。1. The once-through steam generator of the nuclear power plant provided in this embodiment is different from the traditional once-through steam generator. A redistribution header is added to the once-through steam generator to alleviate the problems caused by uneven flow and heat transfer. The problem of uneven flow resistance, especially to alleviate the problem of uneven steam quality under low power and load adjustment, and at the same time, the redistribution header is also equipped with inspection holes for heat transfer tubes, which is convenient for in-service inspection and plugging operations of heat transfer tubes. This design improves the stability and safety of the steam generator operation.

本说明书中各个实施例采用递进的方式描述,每个实施例重点说明的都是与其他实施例的不同之处,各个实施例之间相同相似部分互相参见即可。对于实施例公开的系统而言,由于与实施例公开的方法相对应,所以描述的比较简单,相关之处参见方法部分说明即可。Each embodiment in this specification is described in a progressive manner, each embodiment focuses on the difference from other embodiments, and the same and similar parts of each embodiment can be referred to each other. As for the system disclosed in the embodiment, since it corresponds to the method disclosed in the embodiment, the description is relatively simple, and for relevant information, please refer to the description of the method part.

本领域技术人员可以对每个特定的应用来使用不同方法来实现所描述的功能,但是这种实现不应认为超出本实用新型的范围。Those skilled in the art may use different methods to implement the described functions for each specific application, but such implementation should not be regarded as exceeding the scope of the present invention.

显然,本领域的技术人员可以对实用新型进行各种改动和变型而不脱离本实用新型的精神和范围。这样,倘若本实用新型的这些修改和变型属于本实用新型权利要求及其等同技术的范围之内,则本实用新型也意图包括这些改动和变型在内。Apparently, those skilled in the art can make various changes and modifications to the utility model without departing from the spirit and scope of the utility model. In this way, if these modifications and variations of the utility model fall within the scope of the claims of the utility model and their equivalent technologies, the utility model is also intended to include these modifications and variations.

Claims (4)

1. a kind of continuous steam generator of nuclear power station, which is characterized in that including:Feed water distributor box, heat-transfer pipe, connection of reallocating Case and steam header;The feedwater distributor box, reallocation header and steam header are sequentially communicated;Wherein, the feedwater distributor box It is connected by the heat-transfer pipe with the reallocation header, the reallocation header passes through the heat-transfer pipe and the steam header Connection.
2. the continuous steam generator of nuclear power station as described in claim 1, which is characterized in that further include heat-transfer pipe maintenance Hole;The manhole and the reallocation header unicom, the manhole pass through flange seal.
3. the continuous steam generator of nuclear power station as described in claim 1, which is characterized in that the feedwater distributor box is through matching It puts with the heat-transfer pipe that evenly distributes to being connected with the reallocation header of feeding water.
4. the continuous steam generator of nuclear power station as described in claim 1, which is characterized in that the steam header is configured Uniformly to be mixed to the steam for entering main steam line.
CN201721478763.2U 2017-11-08 2017-11-08 A kind of continuous steam generator of nuclear power station Active CN207486768U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201721478763.2U CN207486768U (en) 2017-11-08 2017-11-08 A kind of continuous steam generator of nuclear power station

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201721478763.2U CN207486768U (en) 2017-11-08 2017-11-08 A kind of continuous steam generator of nuclear power station

Publications (1)

Publication Number Publication Date
CN207486768U true CN207486768U (en) 2018-06-12

Family

ID=62475811

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201721478763.2U Active CN207486768U (en) 2017-11-08 2017-11-08 A kind of continuous steam generator of nuclear power station

Country Status (1)

Country Link
CN (1) CN207486768U (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107631280A (en) * 2017-11-08 2018-01-26 上海核工程研究设计院有限公司 A kind of continuous steam generator of nuclear power station
CN112652414A (en) * 2020-12-16 2021-04-13 中国人民解放军海军工程大学 C-shaped tube bundle of reactor steam generator

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107631280A (en) * 2017-11-08 2018-01-26 上海核工程研究设计院有限公司 A kind of continuous steam generator of nuclear power station
CN112652414A (en) * 2020-12-16 2021-04-13 中国人民解放军海军工程大学 C-shaped tube bundle of reactor steam generator
CN112652414B (en) * 2020-12-16 2022-11-01 中国人民解放军海军工程大学 Reactor steam generator C-tube bundle

Similar Documents

Publication Publication Date Title
US20220205630A1 (en) Test Loop for Simulating Steam Generator with or without Axial Economizer and Test Method Thereof
CN105627276A (en) Molten salt heat storage single-tank internal arrangement heat exchange off-peak electricity steam boiler and heat exchange method
CN207486768U (en) A kind of continuous steam generator of nuclear power station
CN107223194B (en) A sewage and deoxygenation water supply system
CN201503005U (en) Four-chamber two-way flow heat exchange tube pressurized water reactor steam generator on the primary side
CN203657532U (en) Energy-saving heat exchange device
CN203311741U (en) Simulation structure of downward channel of steam generator
CN106642040B (en) A kind of uniform compact steam generator of assignment of traffic
CN205447689U (en) Single jar of built -in heat transfer millet electric steam boiler of fused salt heat -retaining
CN107500461A (en) Chemically and thermally power acts on deaerating type of cycles to a kind of boiler soft water altogether
CN209213962U (en) A kind of normal pressure mixed flow pipeline heating system
CN104990065A (en) Boiler feed water circulating deoxidation system in turbine generator set
CN209926904U (en) An oxidation steam heat exchange system
CN110848967A (en) Mill is with instant heating type pipeline water supply equipment
CN208889338U (en) A kind of nuclear power plant's nested type reactor coolant pipe
CN211346477U (en) Circulating mother liquor heat transfer device
CN203453198U (en) A hydraulic apparatus cooling device
CN203990568U (en) Modified hydrolysis reactor
CN207366225U (en) The experimental system of model steam generator secondary side operating mode
CN107676841B (en) Flue gas waste heat recovery method for heating heat supply network water with different pressures
CN105443508A (en) Efficient hydraulic apparatus cooling device
CN208414292U (en) A kind of production of toluene diisocyanate methylbenzene nitration process heat utilization device
CN207247959U (en) Overheat of steaming Integral vertical thin tubesheet waste heat recovery plant
CN206514698U (en) High-efficiency flue gas waste heat recovery thermodynamic system
CN216159019U (en) Intelligent heat storage and heat storage steam system

Legal Events

Date Code Title Description
GR01 Patent grant
GR01 Patent grant
CP01 Change in the name or title of a patent holder

Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai

Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd.

Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai

Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd.

CP01 Change in the name or title of a patent holder