Sodium-cooled fast reactor intermediate-circuit passive-accident residual heat removal system

Abstract

The invention belongs to the technical field of nuclear power station cooling and particularly relates to a sodium-cooled fast reactor intermediate-circuit passive-accident residual heat removal system. The sodium-cooled fast reactor intermediate-circuit passive-accident residual heat removal system is formed by three circuits respectively including a primary circuit formed by a primary side in asodium pool and an intermediate heat exchanger, a secondary circuit projected on the secondary side of the intermediate heat exchanger and the pipe side of an air heat exchanger, and a tertiary circuit formed by the air heat exchanger and atmosphere. By the arrangement, the problem that the independent heat exchanger (DHX) cannot establish the natural circulation in the sodium pool is solved; fournew residual heat removal circuits in addition to the two circuits of the independent residue heat removal system are obtained; support is provided for diversity and redundancy of reactor system safety design; under the condition of power outage of the whole plant, long-term effective cooling through natural circulation for the reactor is provided.

Description

technical field [0001] The invention belongs to the technical field of nuclear power plant cooling, and in particular relates to a passive accident waste heat discharge system for a sodium-cooled fast reactor intermediate circuit. Background technique [0002] After the reactor is shut down under the condition of power failure of the whole plant, the intermediate circuit cannot rely on forced flow to discharge the residual heat of the core. If a large amount of decay heat cannot be discharged from the core in time, it will cause damage to the core or even leakage of radioactive substances. Therefore, it is particularly important to ensure the removal of residual heat from the core with a passive system under accident conditions. [0003] The passive waste heat removal system is one of the specially designed safety facilities for sodium-cooled fast reactors. At present, the independent waste heat removal system used by domestic sodium-cooled fast reactors includes 2 independe...

AI Technical Summary

Problems solved by technology

This arrangement is mainly to ensure less waste of efficiency caused by the heat taken away by the independent heat exchanger (DHX) under normal operating conditions, but under accident conditions, this arrangement weakens the independent heat exchanger (DHX) DHX) ability to establish natural circulation

[0005] In addition, when the whole plant is powered off, if the damper in the circuit of an independent waste heat removal system cannot be opened normally due to a mechanical failure, the only remaining circuit of the independent waste heat removal system cannot fully guarantee the safety of the core and the reactor under accident conditions. Heat removal capability, which is also a major safety hazard in the design of sodium-cooled fast reactors

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