Reactor residual heat removal system and method based on DC (direct-current) vapor generator

A waste heat removal system and steam generator technology, applied in the field of nuclear reactors, can solve problems such as complex operation, achieve the effects of simplifying the system, reducing radiation protection requirements, and reducing construction costs

Inactive Publication Date: 2019-04-26
CHINA NUCLEAR POWER TECH RES INST CO LTD +2
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0006] 4. The heat of the primary circuit is exported by setting the waste heat discharge system, and the operation is more complicated

Method used

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  • Reactor residual heat removal system and method based on DC (direct-current) vapor generator
  • Reactor residual heat removal system and method based on DC (direct-current) vapor generator
  • Reactor residual heat removal system and method based on DC (direct-current) vapor generator

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Embodiment Construction

[0062] In order to have a clearer understanding of the technical features, purposes and effects of the present invention, the specific implementation manners of the present invention will now be described in detail with reference to the accompanying drawings.

[0063] figure 1 A preferred embodiment of the reactor waste heat removal system based on the once-through steam generator of the present invention is shown. The reactor waste heat discharge system based on the once-through steam generator is applied to the reactor waste heat discharge method based on the once-through steam generator of the present invention. The reactor waste heat discharge system based on the once-through steam generator has simple structure and low construction cost.

[0064] like figure 1 As shown, the reactor waste heat removal system based on the once-through steam generator includes a once-through steam generator 10, a main water supply system 20, and a steam discharge system 30; the once-throug...

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Abstract

The invention relates to a reactor residual heat removal system and method based on a DC (direct-current) vapor generator. The reactor residual heat removal method based on the DC vapor generator comprises a downlink process step A and / or an uplink process step B, wherein the downlink process step comprises procedures as follows: when average temperature of a primary loop coolant is first temperature, the primary loop coolant passes through the primary side of the DC vapor generator and passes through the secondary side of the DC vapor generator for vapor-liquid heat exchange to conduct out heat, and the temperature is reduced from the first temperature to second temperature; when the average temperature of the primary loop coolant is the second temperature, the primary loop coolant passesthrough the primary side of the DC vapor generator and passes through the secondary side of the DC vapor generator for liquid-liquid heat exchange to conduct out heat, and the temperature is reducedfrom the second temperature to third temperature. According to the method, the vapor-liquid heat exchange and the liquid-liquid heat exchange are realized by the DC vapor generator, so that the primary loop heat is not required to be conducted out by the residual heat removal system, and the system and the method have the advantages of being simple and convenient to operate and high in safety performance.

Description

technical field [0001] The invention relates to the technical field of nuclear reactors, in particular to a reactor waste heat discharge system and method based on a once-through steam generator. Background technique [0002] The normal operating status of CPR1000 nuclear power unit is divided into six operating modes. The six operating modes are: reactor power operating mode, steam generator cooling normal shutdown mode, RRA cooling normal shutdown mode, maintenance shutdown mode, refueling shutdown mode and complete reactor discharge mode. In the steam generator cooling normal shutdown mode before the RRA cooling normal shutdown mode is put into operation, the coolant of the primary circuit passes through the tube side of the saturated steam generator, and the feed water of the secondary circuit enters the shell side of the saturated steam generator, and is passed through the control shell side The water level generates steam to bring out a circuit of heat. The RRA cooli...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C15/18
CPCG21C15/182Y02E30/30
Inventor 李翔李海阳魏川清帅剑云张立德张守杰
Owner CHINA NUCLEAR POWER TECH RES INST CO LTD
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