Long-term cooling system for loss-of-coolant accident during isolation failure of modular small reactor containment

A water loss accident and cooling system technology, used in cooling devices, reactors, nuclear power generation, etc., can solve the problems of long-term core cooling and the inability of the cooling system to achieve water loss accidents, etc., to reduce steam resistance, long-term effective cooling, and mitigation. effect of stress

Inactive Publication Date: 2019-06-14
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] The purpose of the present invention is to provide a long-term cooling system for the loss of water accident when the isolation of the containment of the modular small reactor fails, and solve the problem of long-term cooling of the core after the loss of water accident when the existing cooling system cannot realize the isolation failure

Method used

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  • Long-term cooling system for loss-of-coolant accident during isolation failure of modular small reactor containment

Examples

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Effect test

Embodiment 1

[0039] Such as figure 1 As shown, the long-term cooling system for a loss of water accident when the isolation of the modular small reactor containment fails includes a primary cooling circuit, a secondary cooling circuit and a tertiary cooling circuit. The primary cooling circuit is the core make-up water tank 4 and the pressure The circuit formed between the containers 12, the boron-containing water in the core make-up water tank 4 is directly injected into the pipeline 8 through the pressure vessel and enters the pressure vessel 12 to supplement the boron-containing water to the core 7, and the boron-containing water in the pressure vessel 12 is returned through the pipeline. In the core makeup water tank 4, the primary cooling circuit also includes a safety injection tank 5, and the secondary cooling circuit is a circuit formed between the built-in refueling water tank 3 and the pressure vessel 12, and the built-in refueling water tank 3 The boron-containing water is direc...

Embodiment 2

[0045] Such as figure 1 As shown, this embodiment is based on Embodiment 1. The tertiary cooling circuit also includes a stack top exhaust pipeline 11 arranged at the top of the pressure vessel 12, and the steam generated by the core 7 passes through the third-level pipeline 9 of the pressure relief system and the stack. The top exhaust pipeline 11 is discharged into the containment at the same time; the stack top exhaust pipeline 11 is directly connected to the top exhaust valve on the top of the pressure vessel 12. A liquid level sensor is installed in the built-in refueling water tank 3, and the liquid The level sensor and the exhaust valve at the top of the pile are all connected to the controller in communication, and the controller is also connected to the pit recirculation isolation valve 13 in communication. Trigger "open pit recirculation isolation valve 13" and "open stack top exhaust valve"; two exhaust pipes are arranged in parallel at the outlet end of the stack t...

Embodiment 3

[0048] Such as figure 1 As shown, this embodiment is based on Embodiment 1 or Embodiment 2. The water inlet of the pipeline where the pit recirculation isolation valve is located is provided with a filter screen 6; the safety injection tank 5 is directly injected into the pipeline 8 and the pressure vessel through the pressure vessel 12 connected, when the system pressure is lower than the initial pressure of the safety injection tank, the boron-containing water in the safety injection tank is injected into the core under the action of nitrogen pressure; the first stage pipe 1 of the automatic pressure relief system and the first stage pipe 1 of the automatic pressure relief system The secondary pipeline 2 is led out from the top of the pressurizer 10 and is connected to the built-in refueling water tank 3; the built-in refueling water tank 3 is arranged above the pressure vessel 12.

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Abstract

The invention discloses a long-term cooling system for a loss-of-coolant accident during the isolation failure of a modular small reactor containment. The cooling system comprises a primary cooling loop, a secondary cooling loop and a tertiary cooling loop, the primary cooling loop is a loop formed between a reactor core water supply tank and a pressure container, boron-containing water in the reactor core water supply tank enters the pressure container through a pressure container direct-injection pipeline and is supplied to the reactor core, the boron-containing water in the pressure container returns into the reactor core water supply tank through a pipeline, the secondary cooling loop is a loop formed between a built-in refueling water storage tank and the pressure container, the boron-containing water in the built-in refueling water storage tank enters the pressure container through the pressure container direct-injection pipeline, and is supplied to the reactor core, steam generated by the reactor core returns into the built-in refueling water storage tank through an automatic pressure relief system, and the tertiary cooling loop is a natural circulation loop formed between aground pit and the reactor core. The problem that existing cooling systems cannot achieve long-term cooling of the reactor core after the loss-of-coolant accident during isolation failure of the containment is solved in the invention.

Description

technical field [0001] The invention relates to the technical field of accident response in a pressurized water reactor nuclear power plant, in particular to a long-term cooling system for a loss of water accident when the isolation of the containment vessel of a modular small reactor fails. Background technique [0002] For the pressurized water reactor nuclear power plant (such as AP1000) that adopts passive safety injection system, the long-term cooling after the loss of water accident uses the containment passive cooling system as the final heat sink. realized by the natural circulation process. The condensed water collected in the pit is injected into the core through the cold water injection pipeline (pit recirculation pipeline-pressure vessel direct injection pipeline), and the steam generated in the core is discharged into the containment through the discharge pipeline (automatic pressure relief system pipeline and breach) , and is condensed back to the pit, re-inje...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C15/18G21C15/14G21C9/004
CPCY02E30/30
Inventor 党高健李喆邓坚蒋孝蔚邱志方丁书华高颖贤陈伟吴丹钱立波申亚欧李仲春鲁剑超刘定明吴清宋丹戎
Owner NUCLEAR POWER INSTITUTE OF CHINA
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