CN-121983358-A - Nuclear power station pressure relief bubbling device

CN121983358ACN 121983358 ACN121983358 ACN 121983358ACN-121983358-A

Abstract

The application discloses a pressure relief bubbling device of a nuclear power station, which comprises a steam inlet pipeline, a cyclone, a bubbler and a damping ring, wherein the cyclone is communicated with the steam inlet pipeline, a plurality of nozzles are arranged on the cyclone, the nozzles are circumferentially arranged, the outlets of the nozzles are tangentially arranged, so that cooling medium is driven to form a cyclone when steam is sprayed out, the bubbler is communicated with the steam inlet pipeline, the bubbler is positioned below the cyclone, a plurality of bubbling holes are formed in the bubbler, the bubbling holes are uniformly distributed on the surface of the bubbler, and the damping ring surrounds the cyclone and the bubbler to separate the cyclone, the bubbler and the inner wall of a vertical pressure relief box. The pressure relief bubbling device for the nuclear power station provided by the application can realize rapid cooling and depressurization of steam in the vertical pressure relief box, and can also isolate the transmission of condensation pressure oscillation to the surrounding, reduce the influence of pressure waves on the pressure relief box and reduce pressure pulsation caused by the phenomenon of 'water hammer' in the steam condensation process.

Inventors

WEI WEI
Su Zhengda
SONG TAO
XU HANYING
TANG SHUJIAN
YE LIANG
MA QINGJUN
YU JIANG
CHENG XIANGHUI
CHENG RUIXIANG

Assignees

中广核研究院有限公司
中国广核电力股份有限公司

Dates

Publication Date: 20260505
Application Date: 20260105

Claims (10)

1. The nuclear power station pressure relief bubbling device is applied to a vertical pressure relief box, cooling medium is filled in the vertical pressure relief box, and the nuclear power station pressure relief bubbling device is immersed in the cooling medium and is characterized by comprising a steam inlet pipeline, a cyclone, a bubbler and a damping ring; The steam inlet pipeline is used for inputting steam; The cyclone is communicated with the steam inlet pipeline, a plurality of nozzles are arranged on the cyclone, the nozzles are circumferentially arranged, and the outlets of the nozzles are tangentially arranged, so that cooling medium is driven to form a cyclone when steam is sprayed out; The bubbler is communicated with the steam inlet pipeline and is positioned below the cyclone, a plurality of bubbling holes are formed in the bubbler, and the bubbling holes are uniformly distributed on the surface of the bubbler; The damping ring is arranged in the vertical pressure relief box and encloses the cyclone and the bubbler so as to separate the cyclone, the bubbler and the inner wall of the vertical pressure relief box.
2. The nuclear power plant pressure relief and bubbling device as recited in claim 1, wherein a plurality of rows of said nozzles are provided on said cyclone, and wherein said plurality of rows of said nozzles are each configured to spray clockwise or said plurality of rows of said nozzles are each configured to spray counter-clockwise.
3. The nuclear power plant pressure relief and bubbling device according to claim 2, wherein said shock ring has a height that is higher than a height of said nozzles located in an uppermost row of said cyclones.
4. The nuclear power plant pressure relief and bubbling device as recited in claim 1, wherein said bubbler comprises at least one bubbler ring, said bubbler ring being concentric with said swirler and having a larger radius than said swirler, said bubbler holes being uniformly disposed on a surface of said bubbler ring such that steam is ejected through said bubbler holes in a plurality of directions and uniformly enters the cooling medium.
5. The nuclear power plant pressure relief and bubbling device according to claim 4, wherein said bubbling ring is connected to said inlet pipe by a connecting arm, said connecting arm being hollow inside to communicate said inlet pipe with said bubbling ring.
6. The nuclear power plant pressure relief and bubbling device as recited in claim 5, wherein said connecting arms are provided in two or more, said connecting arms being circumferentially and evenly distributed.
7. A nuclear power plant pressure relief and bubbling device as recited in any one of claims 4-6, wherein said shock absorbing ring and said bubbling ring are concentric.
8. The nuclear power station pressure relief and bubbling device as recited in claim 1, wherein the bubbler comprises a plurality of extending arms, one ends of the extending arms are connected with the steam inlet pipeline, the other ends of the extending arms extend outwards, the extending arms are circumferentially distributed around the steam inlet pipeline as a center, and a plurality of bubbling holes are formed in the surface of each extending arm.
9. The nuclear power plant pressure relief and bubbling device according to claim 1, wherein said air inlet pipe and said cyclone are integrally provided.
10. The nuclear power plant pressure relief and bubbling device of claim 1, wherein the air inlet pipe, the cyclone and the bubbler are all made of stainless steel.

Description

Nuclear power station pressure relief bubbling device Technical Field The application relates to the field of pressure relief and temperature reduction of high-temperature and high-pressure steam of a nuclear power station, in particular to a pressure relief bubbling device of the nuclear power station. Background The pressure relief box is an important device in the accident safety system of the modern nuclear reactor, under the accident condition, high-temperature and high-pressure steam is violently sprayed, enters the bubbler through the pressure relief valve, is discharged into the pressure relief box in a jet flow mode to be condensed, and reduces the pressure of the pressure stabilizer, so that the stability of the pressure of a primary loop is maintained. The pressure relief boxes are generally divided into vertical and horizontal types according to the placement location. In the pressure relief and cooling process, the flow fields in the vertical container and the horizontal container are obviously different, however, in the presently disclosed patent, related improvement is not made on the bubbling device of the opposite vertical pressure relief box according to the flow field characteristics, and a matched bubbling device structure is required to be designed according to the flow field characteristics of the vertical pressure relief box. Disclosure of Invention In order to solve one of the technical problems in the prior art, the application provides a pressure relief bubbling device for a nuclear power station, which is mainly applied to a vertical pressure relief box. The nuclear power station pressure relief bubbling device is applied to a vertical pressure relief box, cooling medium is filled in the vertical pressure relief box, the nuclear power station pressure relief bubbling device is immersed in the cooling medium and comprises a steam inlet pipeline, a cyclone, a bubbler and a damping ring, the steam inlet pipeline is used for inputting steam, the cyclone is communicated with the steam inlet pipeline, a plurality of nozzles are arranged on the cyclone, the nozzles are circumferentially arranged, the outlets of the nozzles are arranged in a tangential direction, so that cooling medium is driven to form a cyclone when the steam is sprayed out, the bubbler is communicated with the steam inlet pipeline, the bubbler is located below the cyclone, a plurality of bubbling holes are formed in the bubbler, the bubbling holes are uniformly distributed on the surface of the bubbler, the damping ring is arranged in the vertical pressure relief box, and the damping ring encloses the cyclone and the bubbler so as to separate the cyclone and the bubbler from the inner wall of the vertical pressure relief box. According to the nuclear power station pressure relief bubbling device provided by the first aspect of the application, a plurality of rows of the nozzles are arranged on the cyclone, and the nozzles in the plurality of rows are respectively sprayed clockwise or the nozzles in the plurality of rows are respectively sprayed anticlockwise. According to the nuclear power station pressure relief bubbling device provided by the first aspect of the application, the height of the damping ring is higher than the height of the nozzles positioned at the uppermost row of the cyclones. According to the nuclear power station pressure relief bubbling device provided by the first aspect of the application, the bubbler comprises at least one bubbling ring, the bubbling ring and the cyclone are concentrically arranged, the radius of the bubbling ring is larger than that of the cyclone, and the bubbling holes are uniformly arranged on the surface of the bubbling ring so that steam is sprayed out in a plurality of directions through the bubbling holes and uniformly enters a cooling medium. According to the nuclear power station pressure relief bubbling device provided by the first aspect of the application, the bubbling ring is connected with the steam inlet pipeline through the connecting arm, and the connecting arm is hollow so as to be communicated with the steam inlet pipeline and the bubbling ring. According to the nuclear power station pressure relief bubbling device provided by the first aspect of the application, two or more connecting arms are arranged, and the connecting arms are uniformly distributed circumferentially. According to the nuclear power station pressure relief bubbling device provided by the first aspect of the application, the damping ring and the bubbling ring are of a concentric structure. According to the nuclear power station pressure relief bubbling device provided by the first aspect of the application, the bubbler comprises a plurality of stretching arms, one ends of the stretching arms are connected with the steam inlet pipeline, the other ends of the stretching arms extend outwards, the plurality of stretching arms are circumferentially distributed by taking the steam inlet pipeline