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Pre-service hydrostatic test integrated system on secondary side of steam generator

A steam generator and hydraulic test technology, which is applied in nuclear power generation, nuclear reactor monitoring, and reactors, etc., can solve the problems of poor safety of the suppression system, many temporary interfaces on site, and many test operators, so as to shorten the test period and reduce the volume. , the effect of high safety

Active Publication Date: 2011-09-21
NUCLEAR POWER INSTITUTE OF CHINA
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Problems solved by technology

This kind of temporary system mainly has the following disadvantages: the system heats up very slowly, resulting in a long test period; the equipment is scattered and arranged, occupying a large space, there are many temporary interfaces on site, and the equipment installation period is long; the temporary connection of the pressure system is poor in safety and stable in performance Poor performance and many test operators required

Method used

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  • Pre-service hydrostatic test integrated system on secondary side of steam generator
  • Pre-service hydrostatic test integrated system on secondary side of steam generator

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Embodiment Construction

[0014] The present invention will be described in further detail below in conjunction with the accompanying drawings and embodiments.

[0015] Such as figure 1 As shown in the figure, an integrated system for hydraulic pressure test before the secondary side of the steam generator in the PWR nuclear power plant includes a high power density electric heating water tank 4, a circulation pump 5, a front booster pump 6, and a large flow pressure pump 7 , small flow pressure pump 8, bypass pressure relief regulating valve 9, adjustable pressure return device 10, pressure outlet safety valve 11, pressure outlet solenoid valve 12, heating water tank level gauge 13, system drainage interface 14, system water replenishment interface 15 , water tank thermometer 16, water tank outlet thermometer 17, water tank return water thermometer 18, heating circulation flow meter 19, pressure gauge at the pressure outlet 20, local pressure gauge 21 at the pressure outlet, water tank replenishment i...

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Abstract

The invention belongs to the field of pressurized water reactor nuclear power plants, particularly disclosing a pre-service hydrostatic test integrated system on a secondary side of a steam generator of the pressurized water reactor nuclear power plant. The system comprises a pressurizing pump capable of pressurizing to the secondary side of the steam generator, an electric heating water tank anda circulating pump, wherein the pressurizing pump is connected with the circulating pump in parallel; both an inlet of the pressurizing pump and a suction port of the circulating pump are communicated with a water tank outlet pipe of the electric heating water tank; both an outlet of the pressurizing pump and an outlet of the circulating pump are communicated with a hand hole temporary port on the secondary side of the steam generator; and a water tank water return pipe of the electric heating water tank is communicated with a high-position temporary port on the secondary side of the steam generator. The system has stable and reliable performance, can realize uniform and rapid temperature rise of a shell on the secondary side of the steam generator, can be safely and stably pressurized and unpressurized during pressurizing test, and has a small size and high safety, stability and adjusting accuracy; test period can be effectively shortened; and efficiency can be increased.

Description

technical field [0001] The invention belongs to the field of pressurized water reactor nuclear power plants (pressurized water reactor nuclear power plants), and in particular relates to an integrated system for hydraulic test before secondary side service of a steam generator applied in a pressurized water reactor nuclear power plant (station). Background technique [0002] The pre-service hydraulic test of the secondary side of the steam generator is an important node and milestone in the installation process of the nuclear island equipment of the PWR nuclear power plant. Its scope covers the secondary side of the steam generator and its related systems (including main water supply system, auxiliary water supply system, main steam system, sewage system, etc.) piping and isolation boundary-valve. The test includes multiple technological processes such as temperature rise of the steam generator shell, pressure increase on the secondary side of the steam generator, pressure m...

Claims

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Application Information

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IPC IPC(8): G21C17/00
CPCY02E30/30
Inventor 崔怀明张文其唐辉黄伟钟发杰
Owner NUCLEAR POWER INSTITUTE OF CHINA
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