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Water gate pressure keeping device for safe shell overall pressurization test

A technology for pressure test and holding device, which is applied in the fields of reducing greenhouse gases, climate sustainability, and monitoring of nuclear reactors, etc., which can solve the problems such as the inability of personnel to supply air, fill in, and the sealing effect of the rubber strip.

Pending Publication Date: 2018-04-27
JIANGSU NUCLEAR POWER CORP
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] During the continuous pressurization of the containment, if the rubber strips on the two gates of FAB20AB902 / 903 are not supplemented with air to maintain pressure, the air pressure inside the sealing strips will be offset by the external environmental pressure, the strips will not be able to seal, and the boric acid water in the fuel pool will be filled. into the reactor shaft, with dire consequences
However, during the overall pressure test of the containment vessel, personnel could not enter the reactor hall to replenish gas to the gate rubber strips according to the normal method of gas replenishment.

Method used

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  • Water gate pressure keeping device for safe shell overall pressurization test
  • Water gate pressure keeping device for safe shell overall pressurization test
  • Water gate pressure keeping device for safe shell overall pressurization test

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Embodiment Construction

[0020] Below in conjunction with accompanying drawing and embodiment the present invention is further introduced:

[0021] A device for maintaining the pressure of the water gate during the overall containment pressure test, including a spare penetration piece for the containment vessel 1, a formal pressure joint 3, a gas supply ferrule joint 4, a penetration piece seal test joint 5, a nitrogen cylinder 6, and a pressure reducing valve 7 , stainless steel braided hose 8, shut-off valve 9, pressure gauge 10, temporary blocking plate 11 of the penetration piece, and water gate 12; wherein the spare penetration piece 1 of the containment vessel passes through the outer containment vessel and the inner containment vessel, and the containment vessel The two short ends of the spare penetration 1 are respectively provided with a temporary blocking plate 11 for the penetration, and the temporary blocking plate 11 for the penetration on the side of the outer containment is provided with...

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Abstract

The invention belongs to the technical field of nuclear power station reactor maintenance and particularly relates to a water gate pressure keeping device for realizing remote monitoring and pressuremaintenance of relative pressure of two water gate rubber strips and guaranteeing the sealing effect of the water gate rubber strips in the safe shell overall pressurization test. The water gate pressure keeping device comprises a safe shell spare penetration piece (1), formal pressurization joints (3), a gas supplying clamping sleeve joint (4), a penetration piece seal test joint (5), a nitrogengas cylinder (6), a pressure reducing valve (7), a stainless steel braided hose (8), a stop valve (9), a pressure gauge (10), penetration piece temporary blockage plates (11) and a water gate (12). The safe shell spare penetration piece (1) passes through an outer safe shell and an inner safe shell. Two short parts of the safe shell spare penetration piece (1) are respectively provided with the penetration piece temporary blockage plates (11). The penetration piece temporary blockage plates (11) in one side of the outer safe shell are provided with the formal pressurization joints (3).

Description

technical field [0001] The invention belongs to the technical field of maintenance of nuclear power plant reactors, and in particular relates to a device for maintaining the pressure of a sluice gate during an integral pressure test of a containment vessel. Background technique [0002] The new-generation core trap is used in nuclear power plants where a core blowout accident with a probability of once in a million years collects all radioactive products and prevents them from flowing into the environment. Cooling the core trap requires 1,400 tons of boric acid water. In consideration of the overhaul needs of the nuclear power plant, during normal operation of the unit, the reactor internals inspection well and the fuel pool on both sides of the reactor shaft each hold 700 tons of boric acid water. Water gates are used during normal operation of the unit (see Figure 1 ) to isolate the reactor shaft from the fuel pool and inspection wells for reactor internals. The gate us...

Claims

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Application Information

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IPC IPC(8): G21C17/003
CPCG21C17/003Y02E30/30
Inventor 尤晓波赵亚明兰晓伟曾振华曹晔胡宇刘勇易良川李高超胡彬隋震吴磊张建军高生华张宾
Owner JIANGSU NUCLEAR POWER CORP