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A method for responding to a very small breach loss of water accident in a pressurized water reactor nuclear power plant

A coping method and technology for water loss accidents, which can be used in nuclear power generation, power plant safety devices, and greenhouse gas reduction, etc., and can solve problems such as water loss accidents.

Active Publication Date: 2022-02-11
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0003] The technical problem to be solved by the present invention is: when an extremely small breach loss of water accident occurs, the continuous operation of the safety injection pump will lead to a more serious loss of water accident. method, by stopping the operation of the safety injection pump at the right time and reasonable measures, it solves the problem of safely and effectively controlling the nuclear power plant to ensure the safety of the reactor when a very small breach loss of water accident occurs

Method used

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  • A method for responding to a very small breach loss of water accident in a pressurized water reactor nuclear power plant

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Experimental program
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Effect test

Embodiment 1

[0025] This embodiment is a method for responding to a very small breach loss of water accident in a pressurized water reactor nuclear power plant. The method includes the following steps:

[0026] (1) Detect the operating status of the PWR nuclear power plant. The operating status includes: main system overcooling status, secondary side heat sink status, main system pressure status and pressurizer water level status;

[0027] (2) According to the test results in (1), it is judged whether the operation status of the PWR nuclear power plant satisfies the termination safety injection criterion, and when the operation status meets the termination safety injection criterion, the safety injection pumps are sequentially shut down;

[0028] The termination criteria include:

[0029] The main system is in a supercooled state: the supercooling degree of the core outlet is greater than 15°C;

[0030] There are enough secondary side heat sinks: the total flow of the steam generator is g...

Embodiment 2

[0040] This embodiment is a method for responding to a very small breach loss of water accident in a pressurized water reactor nuclear power plant. The method includes the following steps:

[0041] (1) Detect the operating status of the PWR nuclear power plant. The operating status includes: main system overcooling status, secondary side heat sink status, main system pressure status and pressurizer water level status;

[0042] (2) According to the detection results in (1), it is judged whether the operation state of the PWR nuclear power plant satisfies the termination safety injection criterion, and when the operation state meets the termination safety injection criterion, the safety injection pumps are sequentially shut down;

[0043] The termination criteria include:

[0044] The main system is in a supercooled state: the supercooling degree of the core outlet is greater than 25°C;

[0045] There are enough secondary side heat sinks: the total flow rate of the steam genera...

Embodiment 3

[0055] This embodiment is an accident response measure for a pressurized water reactor nuclear power plant. It is proposed that in the event of a loss of water accident with a very small break in the primary circuit, by setting effective safety injection termination criteria, formulating reasonable safety injection termination steps, and adopting reliable The waste heat export method controls the nuclear power plant in a safe and stable state.

[0056] The present invention is used to control and restore the state of the nuclear power plant after a very small breach loss of water accident occurs in the pressurized water reactor nuclear power plant, and the specific content is as follows:

[0057] (1) According to the important state parameters of the nuclear power plant and the state of the main equipment, the safety injection criteria that can be terminated are: the main system is in a supercooled state, there are sufficient secondary side heat sinks, the pressure of the main ...

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Abstract

The invention discloses a method for responding to an extremely small breach loss of water accident in a pressurized water reactor nuclear power plant, which includes: detecting the overcooling state of the main system of the pressurized water reactor nuclear power plant, the state of the secondary side heat sink, the pressure state of the main system and the voltage stabilization According to the detection results, it is judged whether the safety injection termination criterion is satisfied, and when the safety injection termination criterion is met, the safety injection pump is shut down sequentially; during the operation of stopping the safety injection pump, the main system is monitored in real time Supercooling status and regulator water level status, if the main system subcooling status or regulator water level status does not meet the termination safety injection criteria, start the shutdown safety injection pump; repeat the above steps until all safety injection pumps stop running . The present invention can effectively terminate the safety injection and maintain the nuclear power plant in a safe and stable state after the occurrence of a small breach accident in the primary circuit by setting effective safety injection termination criteria and formulating reasonable safety injection termination steps.

Description

technical field [0001] The invention relates to an accident response plan of a pressurized water reactor nuclear power plant (pressurized water reactor nuclear power plant), in particular to a method for responding to an extremely small breach loss of water accident in a pressurized water reactor nuclear power plant. Background technique [0002] In the PWR nuclear power plant, there is a very small breach loss of water accident that causes the reactor to shut down. For this kind of accident, after the breach occurred, due to the high pressure of the main system, the breach flow was greater than the topfill flow, resulting in a continuous drop in the main system pressure and the water level of the pressurizer, triggering the shutdown of the reactor and the operation of the safety injection pump. After shutdown, as the pressure of the main system drops, when the breach flow is lower than the topfill flow, there is no need for the safety injection pump to continue to run, and ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21D3/06
CPCG21D3/06Y02E30/00
Inventor 党高健丁书华冉旭吴清冷贵君刘昌文陈伟吴丹钱立波申亚欧李仲春蒋孝蔚何晓强
Owner NUCLEAR POWER INSTITUTE OF CHINA