Vapor-water conversion type bubbler of nuclear power station

A technology for bubblers and nuclear power plants, applied in chemical instruments and methods, dissolving, mixing methods, etc., can solve problems such as high labor consumption

Pending Publication Date: 2020-10-27
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

In particular, the pressure oscillation generated by the condensation process brings challenges to the analysis of the impact on the equipment in the water tank. At present, no satisfacto

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  • Vapor-water conversion type bubbler of nuclear power station
  • Vapor-water conversion type bubbler of nuclear power station

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Embodiment Construction

[0012] In order to make the above objects, features and advantages of the present invention more comprehensible, the present invention will be further described in detail below in conjunction with the accompanying drawings and specific embodiments.

[0013] The steam-water conversion type bubbler of the nuclear power plant is usually set in the normal temperature water tank of the containment, submerged in water, and the pipeline of the pressure relief system is connected with the steam inlet pipeline of the bubbler. The steam-water conversion type bubbler itself mainly includes a steam inlet pipe, a water inlet chamber, a water inlet hole, a shrinkage chamber, a mixing chamber, a boost chamber, a bubble chamber, a bubble hole, a scaling nozzle and a support plate. During normal operation, when there is no steam discharge from the pressure relief system, the steam-water conversion type bubbler is filled with water. When the pressure relief system discharges steam, the steam is ...

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Abstract

The invention discloses a vapor-water conversion type bubbler of a nuclear power station. The device comprises a water inlet chamber (2), a contraction chamber (4), a mixing chamber (5), a boosting chamber (6) and a bubbling chamber (7) which are connected in sequence, wherein a vapor inlet pipeline (1) is inserted into the water inlet chamber (2), an outlet of the vapor inlet pipeline (1) is connected with an inlet of a contraction and enlargement nozzle (9), the inlet and the outlet of the contraction and enlargement nozzle (9) are slightly contracted, and an outlet of the contraction and enlargement nozzle (9) is arranged in a contraction chamber (4) of the bubbler. According to the invention, a vapor-liquid two-phase mixed boosting principle is utilized; after the vapor is acceleratedthrough the contraction and enlargement nozzle, water around is sucked into the mixing chamber to complete the condensation process, enters the bubbling chamber through the pressure boosting chamber and finally uniformly enters the water tank after the flow speed is reduced through the small holes in the bubbling chamber, pressure oscillation generated by condensation of steam in the water tank isavoided, meanwhile, water mixing is enhanced, and the safety of equipment is improved.

Description

technical field [0001] The invention belongs to the field of pressure relief systems of nuclear power plants, in particular to the technical field of pressure relief devices for containment refueling water tanks. Background technique [0002] The phenomenon of steam jetting into supercooled water for direct contact condensation is common in many industrial occasions. Because steam immersion in supercooled water jet condensation has efficient mixing and heat transfer capabilities, it is widely used in chemical industry, electric power, metallurgy, refrigeration, military industry and nuclear industry. It has been widely used in industry and other fields, such as direct contact heat exchanger, steam jet pump, underwater propulsion system, especially the pressure relief system of PWR. The pressure relief of the bubbler in the refueling water tank in the containment of the third-generation passive PWR adopts the mechanism of steam jet condensation and heat exchange. The design o...

Claims

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Application Information

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IPC IPC(8): B01F3/04
CPCB01F23/2319
Inventor 武心壮夏栓黄镜宇向文娟张翔云刘汉臣邱健施伟
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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