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System for discharging residual power of pressurized water nuclear reactor

A technology of nuclear reactors and reactors, applied in the direction of nuclear reactors, reactors, overall reactors, etc.

Active Publication Date: 2014-12-10
SOC TECH POUR LENERGIE ATOMIQUE TECHNICATOME
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0011] Furthermore, the fact that the steam generators used are used during the energy operation of the reactor means that they are subject to aging and wear

Method used

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  • System for discharging residual power of pressurized water nuclear reactor

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Embodiment Construction

[0058] figure 1 A nuclear reaction 100 comprising a system for removing residual energy according to the invention is thus schematically shown. Reactor 100 includes two main elements:

[0059] - containment shell 101;

[0060] - Water reservoir 102 .

[0061] The water reservoir 102 is shown here on the side of the containment vessel 101 , but it is understood that it could be arranged around or above the containment vessel 101 . This light water reservoir 102 must contain a large amount of water 103 . Since the purpose is to delay anyone's movement the size is always large. As a magnitude or scale, the volume of water above the outlet of line 108 is several hundred m 3 For 72 hours of operation; for example, and without limitation, for a 300MWth reactor this volume is less than 1000m 3 .

[0062] The water in the water reservoir 102 can be treated with light water to ensure its long-term quality, without which the use of untreated water can be excluded in an accident s...

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PUM

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Abstract

A system for removing the residual power of a pressurised water nuclear reactor, includes a reserve of water, a steam generator, wherein the primary water heated by the core either circulates in a forced manner during power operation, or circulates naturally when the primary pump is stopped, and a condenser housed in the containment vessel. The condenser includes a recovery unit for recovering the condensed water and a condenser link to ensure the circulation of water in a closed circuit between the reserve and the condenser. The system further includes a device for circulating the secondary water between the steam generator and the condenser, the device being activated without an external supply of electrical energy, when an operating parameter characteristic of excessive heating of the primary water reaches a certain threshold, such that the primary water heated by the core and circulating in the steam generator vaporises the secondary water.

Description

technical field [0001] The present invention relates to the field of pressurized water nuclear reactors and more particularly to the removal of residual energy from the core of the reactor after its shutdown. Background technique [0002] Typically when a reactor is shut down by introducing a high level of negative reaction into the core, the amount of fission in the latter becomes very quickly negligible at the end of a time interval of the order of a few seconds. On the other hand, the radioactivity of fission products developed in the core during normal operation continues to release large amounts of energy, which can represent 6-7% of the reactor's operating energy when it is shut down. [0003] At the end of the few hours after shutdown, there is still a residual energy of 1-2% of the operating energy of the reactor, the subsequent decrease is relatively slow: this residual energy has to be removed. It is therefore necessary to have means to remove this residual energy...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C15/18
CPCG21C15/26G21C1/322G21C15/18Y02E30/40Y02E30/30
Inventor C·马利O·科斯特F·马丁
Owner SOC TECH POUR LENERGIE ATOMIQUE TECHNICATOME