Unlock instant, AI-driven research and patent intelligence for your innovation.

Method for coping with minimal crevasse water loss accident of 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: 2020-08-18
NUCLEAR POWER INSTITUTE OF CHINA
View PDF17 Cites 7 Cited by
  • 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

the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
View more

Image

Smart Image Click on the blue labels to locate them in the text.
Viewing Examples
Smart Image
  • Method for coping with minimal crevasse water loss accident of pressurized water reactor nuclear power plant

Examples

Experimental program
Comparison scheme
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 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;

[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 generator...

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 ...

the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
Login to View More

PUM

No PUM Login to View More

Abstract

The invention discloses a method for coping with a minimal crevasse water loss accident of a pressurized water reactor nuclear power plant. The method comprises the steps: detecting a main system supercooling state, a secondary side hot trap state, a main system pressure state and a pressure stabilizer water level state of the pressurized water reactor nuclear power plant; judging whether a safetyinjection termination criterion is met or not according to a detection result, and when the safety injection termination criterion is met, sequentially executing shutdown operation on safety injection pumps; in the process of executing the operation of stopping the safety injection pumps, monitoring the supercooling state of a main system and the water level state of a pressure stabilizer in realtime, and if the supercooling state of the main system or the water level state of the pressure stabilizer does not meet the safety injection stopping criterion, starting the stopped safety injectionpumps; and repeating the steps until all the safety injection pumps stop running. By setting effective safety injection termination criteria, formulating reasonable safety injection termination stepsand the like, safety injection can be effectively terminated and a nuclear power plant can be kept in a safe and stable state after a primary loop minimal crevasse accident occurs.

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

the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
Login to View More

Application Information

Patent Timeline
no application Login to View More
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