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A Pressure Relief System and Method for AP1000 Containment Overall Leakage Rate Test

A technology of containment and leakage rate, which is applied in the field of overall containment leakage rate test, can solve the problems of unsuitable for renovation and expansion, long time of occupying the main line, and limited space, so as to shorten the time of refueling and overhaul, shorten the time of occupying the main line, and improve The effect of economic benefits

Active Publication Date: 2022-03-18
SANMEN NUCLEAR POWER CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

During the overall leak rate test of the containment, in order to realize the pressure filling and unloading of the containment, the VFS-PL-V202 and VFS-PL-V009 on the filling and unloading flow channel are kept open and cannot be closed or adjusted.
However, VFS-PL-V010 and VFS-PL-V005 are used as on-off valves, which do not have the ability to adjust the exhaust gas of 0.402MPa to the pressure range that the downstream pipeline can withstand.
And the limited space is not suitable for retrofitting and adding valves, so it is not directly applicable to the pressure relief after the overall leakage rate test of the containment
[0004] In addition, the existing nuclear power units have the defects of low pressure relief speed and long time of occupying the main line during the refueling and overhaul phase of the overall containment leakage rate test.

Method used

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  • A Pressure Relief System and Method for AP1000 Containment Overall Leakage Rate Test

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Embodiment Construction

[0032] The technical solutions of the present invention will be further described below in conjunction with the accompanying drawings and through specific implementation methods.

[0033] Such as figure 1 As shown, a pressure relief system for AP1000 containment overall leakage rate test, including pressure relief valve 1 3, pressure relief valve 2 4, isolation valve 6, three-way one 1, butterfly valve 2, three-way two 5, VFS exhaust air Filter unit, temporary pressure relief hose 7 and local pressure gauge 8.

[0034] Pressure relief valve 1 3 is used to realize the adjustment function of pressure relief for the overall containment leakage rate test, pressure relief valve 2 4 is used to assist pressure relief valve 1 3 to realize the adjustment function of pressure relief for the overall containment leakage rate test, isolation valve 6 is always in a closed state, which is used to isolate the air flow on the upstream and downstream sides of the isolation valve 6 . Tee one 1...

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Abstract

The invention relates to the technical field of overall containment leakage rate testing, in particular to a pressure relief system and method for an AP1000 overall containment leakage rate test. An AP1000 containment overall leak rate test pressure relief system, including pressure relief valve 1 and pressure relief valve 2 arranged side by side, and an isolation valve; three-way one, located in the downstream of the pressure relief valve 1 and pressure relief valve 2 On the discharge pipeline; Butterfly valve, located on the discharge pipeline between the three-way one and the chimney; Three-way two, located on the exhaust pipeline between the downstream of the isolation valve and the chimney; VFS exhaust air filter unit, Set on the exhaust pipeline between the tee two and the chimney; a temporary pressure relief hose, one end is connected to the tee one, and the other end is connected to the tee two. The AP1000 overall containment leakage rate test pressure relief system of this application combines VUS and VFS to change the pressure relief flow path of the unit overhaul containment overall leakage rate test to achieve the purpose of purifying the pressure relief air, thereby meeting the nuclear safety guidelines.

Description

technical field [0001] The invention relates to the technical field of the overall containment leak rate test, in particular to a pressure relief system and method for the AP1000 containment overall leak rate test. Background technique [0002] According to the requirements of nuclear safety guidelines (HAD401 / 02), during the refueling and overhaul phase of nuclear power plants, the depressurized air used for performing the overall containment leakage rate test must be filtered and purified before being discharged. However, the flow path of the existing AP1000 containment leak rate test system (VUS) cannot meet the nuclear safety guidelines: the pressure relief and exhaust path of the pre-operation containment leak rate test performed during commissioning is from the containment exhaust filter through the exhaust air. After passing through the containment penetration, the pipeline is decompressed by VUS-PL-V002 / 003 and then discharged to the high altitude of the chimney of t...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/00G21C19/00G21D1/02
CPCG21C17/002G21C19/00G21D1/02Y02E30/30Y02E30/00
Inventor 缪骐远白东进熊壮王子虎
Owner SANMEN NUCLEAR POWER CO LTD
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