Overpressure protection method for reactor startup/shutdown condition of PWR (pressurized water reactor) nuclear power plant

A pressurized water reactor nuclear power plant, overpressure protection technology, applied in nuclear power generation, power plant safety devices, greenhouse gas reduction, etc., can solve problems such as brittle fracture of pressure vessels, and achieve the effect of reducing the risk of integrity damage

Active Publication Date: 2015-02-04
NUCLEAR POWER INSTITUTE OF CHINA
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  • Application Information

AI Technical Summary

Problems solved by technology

Especially when the coolant temperature is lower than the reference non-ductile transition temperature (RTNDT) of the reactor pressure vessel material, once the RCS pressure exceeds the pressure limit at low temperature, it may cause local brittle fracture of the pressure vessel

Method used

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Embodiment Construction

[0038] The present invention is further described below in conjunction with embodiment.

[0039] The present invention a kind of overpressure protection method of pressurized water reactor nuclear power plant startup / shutdown condition, specifically comprises the following steps:

[0040] Step 1. Overpressure protection in power plant shutdown conditions

[0041] 1.1 Normal cooling operation

[0042] The operator controls the cooling of the main cooling system of the power plant so that it changes from the hot shutdown condition to the cold shutdown condition. During this period, the safety valve of the voltage regulator works in the normal operation protection mode. At this time, there is a certain In the steam space, the operator first connects the waste heat discharge system to the main coolant system; the normal operation protection mode is a mode in which the safety valve of the voltage stabilizer is opened and the setting value is 16-18MPa;

[0043] 1.2 Surplus row saf...

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PUM

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Abstract

The invention relates to an overpressure protection method for reactor startup/shutdown condition of a PWR (pressurized water reactor) nuclear power plant. The method comprises the following steps: the step 1) carrying out power plant reactor shutdown condition overpressure protection; and the step 2) carrying out power plant reactor startup condition overpressure protection: 2.1 carrying out temperature rise period overpressure protection which comprises the following steps: 2.1.1 carrying out temperature rise alarming operation; 2.1.2 carrying out pressure stabilizer safety valve function switching operation; and 2.1.3 carrying out normal temperature rise operation; and 2.2 carrying out hydrostatic test overpressure protection comprising the following steps: 2.2.1 setting coolant protection temperature of the hydrostatic test to be T1=70-120 DEG; 2.2.2 carrying out temperature rising operation according to the temperature rise period overpressure protection operation in the step 2.1, and when the temperature reaches a set temperature T1, switching the low temperature protection mode after the reactor shutdown to the normal operation protection mode; and 2.2.3 carrying out hydrostatic test on a reactor coolant system. The method helps to improve the capability of the RCS for coping with overpressure transient event, and reduce pressure boundary integrity damage risk of the coolant system greatly; and the method facilities the RCS overpressure protection under the operating conditions of reactor startup/shutdown, and hydrostatic test and the like.

Description

technical field [0001] The invention relates to the technical field of transient mitigation measures and accident prevention of a pressurized water reactor nuclear power plant, in particular to an overpressure protection method for the pressurized water reactor nuclear power plant start / stop working condition. Background technique [0002] During the start-up / shutdown conditions of nuclear power plants, due to the malfunction of related equipment, mass input or energy input may occur in the reactor coolant system (RCS). This transient condition will cause the RCS pressure to rise. Especially when the coolant temperature is lower than the reference non-ductile transition temperature (RTNDT) of the reactor pressure vessel material, once the RCS pressure exceeds the pressure limit at low temperature, it may cause local brittle fracture of the pressure vessel. The pressure limit of RCS in low temperature state is much lower than that in power operation condition. Therefore, over...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21D3/06
CPCG21D3/06Y02E30/00
Inventor 李健刘余杜思佳
Owner NUCLEAR POWER INSTITUTE OF CHINA
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