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Method for controlling secondary side pressure relief accidents of all vapor generators

A technology of steam generator and control method, which is applied in the field of reactor control, and can solve the problems of containment temperature and pressure rise, heat transfer tube thermal shock, nuclear power rise, etc.

Active Publication Date: 2020-08-21
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0003] 1. Due to the negative feedback effect in the core, too much positive feedback may be introduced in the accident, which will eventually increase the nuclear power and cause the risk of damage to the integrity of the fuel elements;
[0004] 2. If the discharge point on the secondary side of the steam generator appears in the containment, a large amount of high-energy fluid will be discharged into the containment after the accident, which will cause the temperature and pressure in the containment to rise, and the safety of the containment will be threatened;
The drastic change in pressure during this process will also pose a threat to the integrity of the equipment;
[0006] 4. In a short period of time, the fluid on the secondary side of the steam generator is quickly discharged, resulting in partial or even complete exposure of the heat transfer tubes, and the heat transfer tubes are in a dry state. When too much low-temperature feed water is injected into the steam generator during the subsequent recovery of the power plant, the heat transfer Tubes may be affected by thermal shock

Method used

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  • Method for controlling secondary side pressure relief accidents of all vapor generators
  • Method for controlling secondary side pressure relief accidents of all vapor generators

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0063] Such as figure 1 As shown, the existing nuclear power plant system includes: reactor, steam generator (can be more than one), and steam turbine. The device is equipped with auxiliary water supply and exhaust steam bypass. The secondary circuit is equipped with an isolation valve that can be activated for isolation when the circuit breaks. The primary circuit is equipped with a safety injection system and a normal waste heat discharge system.

[0064] Such as figure 2 As shown, the general route of the present invention is: first use the measurable data of the system to make a judgment, obtain the cause of the secondary side pressure relief accident, perform the corresponding troubleshooting operation according to the cause, and then determine the execution according to the success of the troubleshooting operation. Differently, the steam generator is used to lower the temperature and pressure of the primary circuit system. In order to quickly and accurately realize th...

Embodiment 2

[0079] Further examples are:

[0080] The feedwater control operation includes: starting the auxiliary feedwater of the steam generator, closing the auxiliary feedwater of the steam generator, and adjusting the flow rate of the auxiliary feedwater of the steam generator;

[0081] The exhaust steam control operation includes: starting the exhaust steam bypass of the steam generator, closing the exhaust steam bypass of the steam generator, and adjusting the steam discharge flow of the steam generator.

[0082] Further examples are:

[0083] S31 is specifically:

[0084] Carry out feed water control operation on the intact steam generator until the water loading is restored;

[0085] When the state parameter of the primary circuit reaches the safety injection termination condition, turn to the safety injection system corresponding to the reactor coolant system to terminate the operation;

[0086] After the safety injection system is terminated, turn to the intact steam generat...

Embodiment 3

[0107] to attach figure 1 And attached figure 2 For example:

[0108] When an uncontrolled pressure drop accident occurs on the secondary side of all steam generators in a nuclear power plant, before the operator does not intervene, the emergency shutdown signal that occurs during the accident triggers the emergency shutdown and the ad hoc safety device activation signal that appears Trigger safety systems including safety injection system and auxiliary water supply system into operation.

[0109] After the operator intervenes, the operation is carried out according to the specific content of the present invention, the detailed content is as follows:

[0110] (1) Determine the cause of the accident based on the important status parameters and equipment status of the nuclear power plant. The specific method is to combine the changes in the pressure and water content of the steam generator, the changes in the internal environment of the containment, the valves and Identify t...

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PUM

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Abstract

The invention discloses a method for controlling secondary side pressure relief accidents of all vapor generators. The method for controlling the secondary side pressure relief accidents of all the vapor generators comprises the following steps that S1, the accident occurrence reason is judged according to the important state parameters of a nuclear power plant and the equipment state condition; S2, trouble clearing operation of corresponding measures is carried out according to the judged accident occurrence reason; S3, if the trouble clearing operation succeeds, the step S31 is executed, andif the trouble clearing operation does not succeed, the step S32 is executed; S31, the vapor generators in a good state are selected, and water supply control operation and vapor exhaust control operation are carried out on the vapor generators until the vapor generators reach a cold shut-down amplifier state; and S32, the vapor generators in a failure state are selected, and water supply controloperation is carried out on the vapor generators until the vapor generators the cold shut-down amplifier state.

Description

technical field [0001] The invention relates to the field of reactor control, in particular to a control method for secondary side pressure relief accidents of all steam generators. Background technique [0002] When the following accident conditions occur in a nuclear power plant, the pressure on the secondary side of all steam generators will drop uncontrollably: the main steam pipe or the main feedwater pipe on the secondary side of the steam generator ruptures, and the valve used to isolate the breach cannot be closed ; The control system used to control steam discharge sends out a wrong valve opening signal, resulting in uncontrolled discharge of steam from the steam generator; the steam discharge valve on the steam pipeline is stuck in the open position and cannot be closed. These types of accidents will lead to an uncontrolled decrease in the pressure on the secondary side of the steam generator, which in turn will lead to a rapid drop in temperature and pressure in t...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): F22B35/00G21D3/06
CPCF22B35/004G21D3/06Y02E30/00
Inventor 喻娜冉旭李峰吴清冷贵君刘昌文钱立波陈伟丁书华张丹方红宇邱志方陈宏霞初晓
Owner NUCLEAR POWER INSTITUTE OF CHINA
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