A method for alleviating the consequences of the main steam pipeline rupture accident

A main steam and accident technology, applied in the safety field of pressurized water reactor nuclear power plants, can solve the problem of fast cooling rate of coolant, and achieve the effect of slowing down the cooling rate, avoiding the influence of human factors, and reducing the risk of burnout

Active Publication Date: 2022-02-22
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] The technical problem to be solved by the present invention is: the problem of fast cooling rate of the coolant during the main steam pipeline rupture accident process

Method used

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Embodiment

[0017] The present invention is further described below in conjunction with embodiment.

[0018] The present invention is a method for alleviating the consequence of a main steam pipeline rupture accident, comprising the following steps:

[0019] Step 1: After the main steam pipeline rupture accident occurs in a nuclear power plant, due to the rapid discharge of a large amount of steam in the secondary circuit, when the steam flow rate and steam pressure of the secondary circuit increase or decrease to the corresponding high flow rate or low pressure setting respectively; or When the steam flow rate of the secondary circuit and the average temperature of the reactor increase or decrease respectively to the high flow rate setting value or the low temperature setting value; Close all main steam isolation valves and main feedwater isolation valves;

[0020] Step 2: After all main steam isolation valves and main feedwater isolation valves are closed, since the main steam isolatio...

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Abstract

The invention relates to a method for mitigating the consequences of a main steam pipeline rupture accident in a pressurized water reactor nuclear power plant, comprising the following steps: the first step: after the main steam pipeline rupture accident occurs, "the steam flow rate is high and the average temperature of the reactor coolant is low or the compensation steam pipeline The signal of "low pressure meets" is triggered, and all main steam and main feed water isolation valves are closed; the second step: the signal of "steam line pressure low-3" triggers the shutdown of the coolant pump. The present invention requires the addition of a "steam line pressure low-3" shutdown coolant pump signal to the reactor protection system. The invention can significantly slow down the cooling rate of the coolant in the rupture accident of the main steam pipeline, and solves the essential problem of fast cooling rate of the coolant in the rupture accident process of the main steam pipeline in the prior art. The invention effectively reduces the risk of fuel element burnout by reducing the power peak value after the core returns to the critical state, and achieves the purpose of alleviating the consequences of the accident.

Description

technical field [0001] The invention relates to the safety field of a pressurized water reactor nuclear power plant, in particular to a method for alleviating the consequence of a rupture accident of a main steam pipeline. Background technique [0002] For the steam system pipe rupture accident, the most serious situation is the double-end shear rupture of the steam pipe, which will cause a large amount of steam to be discharged rapidly, resulting in an increase in the energy derived from the reactor coolant system, and a sharp drop in the temperature and pressure of the coolant . Due to the introduction of positive reactivity into the core due to moderator temperature effects, the reactor could return to criticality and return to power operation, possibly resulting in burnout of the fuel elements. Therefore, mitigation measures need to be considered in the design to deal with the risk of fuel element burnout in the event of a main steam pipeline rupture. [0003] When the...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C15/18
CPCY02E30/30
Inventor 张舒邱志方黄代顺陈宏霞喻娜方红宇吴鹏蔡容郑强冉旭李峰杨帆张丹张卓华张渝邓坚吴清
Owner NUCLEAR POWER INSTITUTE OF CHINA
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