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A device for studying the impact of power outages and large breaches in the containment on the containment

A containment and large breach technology, applied in the field of passive heat export of containment, to achieve the effect of less additional cost, safe and controllable test process, and simple operation

Active Publication Date: 2020-01-03
CNNC FUJIAN FUQING NUCLEAR POWER
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0003] The purpose of the present invention is to provide a device for studying the impact of power outages in the whole plant and large breach accidents in the shell on the containment, so as to solve the research needs of introducing the precondition that the cooling water pool is heated to the saturation temperature in advance, and studied the Hualong-1 The establishment of natural circulation of the system under the conditions of plant-wide power outage (SBO) and primary circuit / main steam breach accident occurred successively in No. 1 nuclear power plant to prove the effectiveness of the system design

Method used

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  • A device for studying the impact of power outages and large breaches in the containment on the containment

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Embodiment Construction

[0014] The present invention will be described in detail below in conjunction with the accompanying drawings and specific embodiments.

[0015] like figure 1 As shown in , it is the structure diagram of the device for studying the influence of the power outage of the whole plant and the large breach accident in the containment on the containment. The electric boiler 1 is connected to the containment simulation body 2 through the lower containment steam inlet pipeline 8 and the upper containment steam inlet pipeline 9 respectively, the outlet of the electric boiler 1 is provided with a flow meter 13, and the heat exchanger 3 is placed in the containment simulation body 2 Inside, the two ends of the heat exchanger 3 are respectively connected to the bottom of the cooling water tank 4 through the natural circulation descending pipeline 10 and the natural circulation ascending pipeline 11. The natural circulation descending pipeline 10 is provided with a descending isolation valve...

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Abstract

Belonging to the technical field of containment passive heat export, the invention in particular relates to a device for studying the influence of station blackout and in-containment large break accidents on a containment. An electric boiler is connected to a containment simulator respectively through a containment lower steam inlet pipeline and a containment upper steam inlet pipeline, a heat exchanger is placed in the containment simulator, two ends of the heat exchanger are connected to the bottom of a cooling water tank respectively through a natural circulation descending section pipelineand a natural circulation ascending section pipeline, the natural circulation descending section pipeline is equipped with a descending section isolation valve, the electric boiler is connected to asteam heating pipeline in the cooling water tank, and the pipeline is equipped with a water tank heating section isolation valve and a water tank heating section flowmeter. The device provided by theinvention is the experimental device used for a CNNCC Hualong No.1 containment passive heat export system for the first time at home to study the system response characteristic under the working condition that station blackout accident and large break extreme accident successively occur to a nuclear power station, and has great practical significance.

Description

technical field [0001] The invention belongs to the technical field of passive heat derivation of containment shells, and in particular relates to a device for studying the effects of plant-wide power outages and large breach accidents in the containment shells on containment shells. Background technique [0002] China Nuclear Hualong One is designed to share the cooling water pool between the containment passive heat removal system (PCS) and the secondary circuit passive waste heat removal system (PRS). The possibility of a large breach accident, when the PRS system has overheated the cooling water tank and other possible extreme accident conditions, the cooling water tank has been heated to a higher temperature or even saturated before the PCS system is put into operation temperature. At this time, the temperature (normal temperature) of the cooling water in the PCS system loop pipeline is lower than that in the cooling water tank, which is different from the relatively u...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/00
CPCG21C17/001Y02E30/30
Inventor 李泽军吴其方刘洪印薛峻峰王志强孟兆明周剑丁铭张楠孙中宁张明兴祝圆郑静黄晓景郝禄禄仇苏辰
Owner CNNC FUJIAN FUQING NUCLEAR POWER
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