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Pool type sodium cooled fast reactor accident afterheat exhausting system

A sodium-cooled fast reactor and exhaust system technology, which is applied to reactors, cooling devices, and greenhouse gas reduction, and can solve problems such as poor passive performance

Inactive Publication Date: 2008-07-16
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
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  • Description
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Problems solved by technology

[0005] The object of the present invention is to provide a method that can discharge the residual heat of the core by relying on natural circulation, and has better passive performance for the poor passive performance of the accident waste heat discharge system of the existing pool-type sodium-cooled fast reactor. Accident Waste Heat Discharge System of Pool Type Sodium Cooled Fast Reactor with Safety Features

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  • Pool type sodium cooled fast reactor accident afterheat exhausting system

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Embodiment Construction

[0014] The technical solutions of the present invention will be further described below in conjunction with the accompanying drawings.

[0015] As shown in Figures 1 and 2, the present invention consists of two mutually independent loops with the same structure, and each loop can effectively ensure the discharge of the remaining heat release of the reactor core. Each loop is composed of an independent heat exchanger 5, an air heat exchanger 3, a double-layer main pipeline 7 with electric heating wire and insulation layer, and measuring and controlling instruments. The independent heat exchanger 5 and the air heat exchanger 3 are connected in series, the lower part of the independent heat exchanger 5 is immersed in the sodium pool of the reactor core, and the air heat exchanger 3 is connected with the draft chimney 1 outside.

[0016] Wherein, the independent heat exchanger 5 is an immersed passive sodium-sodium heat exchanger. It includes a safety shell, an outer tube is arra...

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Abstract

The invention discloses an accidental afterheat discharge system of a pool type SFR. The afterheat discharge system is an independent heat-transfer system and is formed by an independent heat exchanger and an air heat exchanger which are connected in series, wherein, the lower part of the independent heat exchanger is immersed into a sodium pool of an active zone, the air heat exchanger is connected with a down-draught chimney outside. The accidental afterheat discharge system provided by the invention has independence and nonmotility. In the accidental condition, the invention can effectively discharge the remaining releasing heat of the active zone.

Description

technical field [0001] The invention belongs to the technical field of safety facilities for sodium-cooled fast reactors, and in particular relates to an accident waste heat discharge system for pool-type sodium-cooled fast reactors. Background technique [0002] The fast neutron breeder reactor is referred to as fast reactor, and its simple working process is: the heat generated by the reactor core is carried out by liquid sodium and sent to the intermediate heat exchanger; in the intermediate heat exchanger, the primary circuit of sodium transfers the heat to the secondary Sodium in the loop; the sodium in the secondary loop enters the steam generator, transfers heat to the water in the third loop, and the water in the third loop turns into steam, which drives the turbogenerator to generate electricity. The purpose of separating the primary and tertiary circuits with the secondary circuit is to prevent the water in the tertiary circuit from leaking into the reactor core an...

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Application Information

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IPC IPC(8): G21C15/18
CPCY02E30/34Y02E30/30
Inventor 徐銤刘莲萍杨福昌叶原武余华金刘嘉一唐龙许义军杨志民张东辉
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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