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Passive waste heat removal system for floating nuclear power plant

A passive waste heat and nuclear power plant technology, applied in the field of safety systems, can solve problems such as unfavorable natural circulation, long pipelines, and large flow resistance, and achieve the effects of small seawater flow, reduced resistance, and reduced flow resistance

Active Publication Date: 2014-07-02
HARBIN ENG UNIV
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, the position of the reactor is generally in the center of the floating platform. Whether the primary coolant is drawn out to the seawater side or the seawater is introduced into the vicinity of the reactor, a long pipeline is required.
This will bring greater flow resistance, which is not conducive to the establishment of a stable natural circulation.

Method used

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  • Passive waste heat removal system for floating nuclear power plant

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Embodiment Construction

[0017] The present invention will be further described below in conjunction with the accompanying drawings.

[0018] The passive waste heat removal system of a floating nuclear power plant as shown in Figure 1 includes a reactor pressure vessel 1, a passive waste heat discharge heat exchanger 8 and a passive emergency cooling water tank 11; the passive waste heat discharge heat exchanger 8 is located in the emergency cooling water tank 11 The bottom, which is higher than the reactor core, ensures that the main cooling system of the primary circuit has sufficient natural circulation to drive the pressure head. At least one set of main coolant pipes on the reactor pressure vessel 1 is connected with the steam generator 2 . The inlet pipe of the passive waste heat discharge heat exchanger 8 is connected to the hot pipe section 5 of the main cooling system pipe of the primary circuit, and the outlet is connected to the cold pipe section 6 of the main cooling system pipe of the pri...

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Abstract

The invention relates to a passive waste heat removal system for a floating nuclear power plant. The system consists of a reactor pressure vessel 1, a passive waste heat removal heat exchanger 8 and a passive emergency cooling water tank 11, wherein the passive waste heat removal heat exchanger 8 is arranged in the emergency cooling water tank 11; an inlet / outlet of the heat exchanger is connected with a loop main coolant pipeline; the emergency cooling water tank 11 is arranged in the pressure vessel; the bottom of the water tank is connected with an ocean through a seawater pipeline; a water level in the water tank is kept consistent with the sea level, and the passive waste heat removal heat exchanger 8 is completely submerged. The passive waste heat removal system is operated under accident conditions, and heat in a loop is finally taken into an atmospheric environment by means of evaporation of water in the water tank. When the water level in the water tank is reduced, seawater automatically enters the water tank through a seawater pipeline, the water level in the water tank is kept, and the reactor is cooled for a long time.

Description

technical field [0001] The present invention relates to a safety system of a nuclear power plant, in particular to a non-conductive cooling system suitable for floating nuclear power plants that can introduce seawater into an emergency cooling water tank under accident conditions, and export the decay heat of the reactor through the continuous evaporation of the working medium in the water tank. Active waste heat removal system. Background technique [0002] After the nuclear reactor is shut down, there will still be a large amount of decay heat generated, and this part of heat accumulation may cause the temperature and pressure in the reactor pressure vessel to be too high and destroy the integrity of the pressure boundary. In order to export the waste heat from the core, a waste heat export system is designed in the nuclear power plant. [0003] A floating nuclear power plant is a mobile nuclear power plant built on a floating platform. Floating nuclear power plants have...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C15/18
CPCY02E30/40Y02E30/30
Inventor 彭敏俊夏庚磊杜雪吕星郑勇
Owner HARBIN ENG UNIV
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