Load control method and system for adjustment of steam turbine of nuclear power station

A technology of steam turbines and nuclear power plants, applied in the field of nuclear power, which can solve problems such as the operation of nuclear power plant units, the impact of service life, and disturbances

Active Publication Date: 2015-04-08
中广核工程有限公司 +1
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

In some working conditions of nuclear power plants, due to the GRE automatic load control function, the reactor R rods are unnecessarily disturbed, which has an extremely adverse impact on the operation and service life of the nuclear power plant units.

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  • Load control method and system for adjustment of steam turbine of nuclear power station
  • Load control method and system for adjustment of steam turbine of nuclear power station
  • Load control method and system for adjustment of steam turbine of nuclear power station

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Embodiment Construction

[0032] In order to make the purpose, technical solutions and beneficial technical effects of the present invention clearer, the present invention will be further described in detail below in conjunction with the accompanying drawings and specific embodiments. It should be emphasized that the specific implementations described in this specification are only for explaining the present invention, not for limiting the application occasions of the present invention.

[0033] In the process of nuclear power plant steam turbine adjustment, load open-loop control is also called manual control mode, that is, in the load P or PI adjustment link, the operator manually sets the load target value, and the actual load feedback link is cut off, that is, feedback is not considered. Load closed-loop control, also known as automatic control mode, is in the load P or PI adjustment link, the operator manually sets the load target value, the actual load feedback link is not cut off, and feedback needs...

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Abstract

The invention discloses a load control method for adjustment of a steam turbine of a nuclear power station. The method comprises the following steps: acquiring a set rotating speed value and an actual rotating speed value of the steam turbine of the nuclear power station; judging whether a difference value between an actual load value of the steam turbine for the nuclear power station and a set load value of the steam turbine of the nuclear power station exceeds a preset range or not according to the set rotating speed value and the actual rotating speed value; if the difference value between the actual load value of the steam turbine for the nuclear power station and the set load value of the steam turbine of the nuclear power station exceeds the preset range, sending a steam flow limiting signal to a main control chamber. The load control method for adjustment of the steam turbine of the nuclear power station is a reliable technology for controlling a load in the adjustment of the steam turbine of the nuclear power station, so that safe operation of a nuclear power unit can be guaranteed. Furthermore, the invention also discloses a load control system for adjustment of the steam turbine of the nuclear power station.

Description

Technical field [0001] The invention belongs to the technical field of nuclear power. More specifically, the invention relates to a load control method and system based on the regulation of a nuclear power plant steam turbine. Background technique [0002] In some new nuclear power projects of CPR1000, the steam turbine regulation system (GRE) controls the load and frequency of the unit by adjusting the steam intake of the steam turbine, so that the unit can operate safely and economically in various working conditions and meet the quality requirements of power supply. At the same time, considering the safety and reliability of nuclear power plant reactors, GRE should have a load open-loop control function to avoid inconsistencies in the load matching process between the reactor and the turbine. If the reactor is not matched, it will cause unnecessary disturbance of the R rod of the reactor, which will have extremely adverse effects on the operation and service life of the nuclea...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): F01D17/00G21D3/08
CPCY02E30/00
Inventor 王旭峰白乐园张冲展晓磊尹刚吕爱国曾彬
Owner 中广核工程有限公司
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