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Passive accident discharge and cooling system and method of steam generator in nuclear power station

A steam generator and accidental discharge technology, applied in nuclear power generation, cooling devices, nuclear engineering, etc., can solve the problems of how to cool and recycle the high-temperature steam-water mixture without considering the radioactivity, and achieve high reliability, stable operating pressure, Compensate for the effect of water volume changes

Pending Publication Date: 2019-07-09
XIAN THERMAL POWER RES INST CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, the original supporting system did not consider how to cool and recycle the radioactive high-temperature soda-water mixture.

Method used

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  • Passive accident discharge and cooling system and method of steam generator in nuclear power station

Examples

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Effect test

Embodiment 1

[0035] In this embodiment, the pressurized water reactor nuclear power unit is taken as an example. The steam generator 1 of the pressurized water reactor nuclear power unit is a saturated steam generator 1 with a steam-water separator, which is a vertical U-shaped tube natural circulation structure. Each 1000MW pressurized water reactor nuclear power unit needs three steam generators 1, the tube bundle of the steam generator 1 is the reactor primary loop system coolant, and the tube shell side is the secondary loop steam-water mixture. The design pressure of the primary side is 17.23MPa, and the design temperature is 343°C; the design pressure of the secondary side is 8.6MPa, and the design temperature is 316°C. When any one of the steam generators 1 has a heat transfer tube rupture (SGTR) emergency, the passive accident discharge and cooling process of the steam generator 1 is as follows:

[0036] Since the pressure on the primary side of the steam generator 1 is much higher...

Embodiment 2

[0043] This embodiment takes a high temperature gas-cooled reactor nuclear power unit as an example. The steam generator 1 of the high-temperature gas-cooled reactor nuclear power unit is a vertical, direct-flow spiral tube assembly structure. Each 200MW high-temperature gas-cooled reactor nuclear power unit has two steam generators 1, and the tube bundle of the steam generator 1 is a secondary circuit steam-water mixture. The side of the tube shell is helium in the primary circuit of the reactor, the operating pressure of the primary circuit is 7MPa, and the average temperature is 750°C; the operating pressure of the secondary circuit is 13.9MPa, the feedwater temperature is 205°C, and the steam temperature is 566°C. In the event of a steam generator 1 heat transfer tube rupture (SGTR) emergency, the passive accident discharge and cooling process of the steam generator 1 is as follows:

[0044] The pressure of the primary circuit of steam generator 1 is much lower than that o...

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Abstract

The present invention discloses passive accident discharge and cooling system and method of a steam generator in a nuclear power station. The system includes a main water feeding pipe, a main water feeding isolation valve, the steam generator, a main steam isolation valve, a discharge tank, a water cooling wall upper header, a water cooling wall lower header, a discharge liquid recovery unit, an air cooler, an elevated expansion tank, an exhaust valve and an air cooling tower. The system and method can quickly and reliably cool and recover a radioactive high-temperature steam water mixture without relying on an external power source when a heat transfer pipe breaks in the steam generator of the nuclear power station.

Description

technical field [0001] The invention belongs to the technical field of nuclear power safety facilities, and relates to a passive accident discharge and cooling system and method for steam generators in nuclear power plants. Background technique [0002] The steam generator of a nuclear power plant is a heat exchange device in which the coolant of the primary circuit transfers the heat of the nuclear steam supply system to the feed water of the secondary circuit to generate steam of a certain pressure, temperature and dryness. The steam generator, the pressure vessel and the primary circuit piping together constitute the third safety barrier to prevent the radioactive fission products from overflowing. As the hub connecting the primary and secondary circuit equipment of the nuclear power plant, the steam generator has the operation characteristics of the instability of the vapor-liquid two-phase flow and the complex and changeable boiling heat transfer. According to the acci...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C15/18G21C15/243G21C15/253
CPCG21C15/18G21C15/243G21C15/253Y02E30/30
Inventor 刘俊峰韩传高董雷马晓珑张卫军余俨
Owner XIAN THERMAL POWER RES INST CO LTD
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