Lead-cooled fast reactor afterheat discharging system and method

Abstract

The invention discloses a lead-cooled fast reactor afterheat discharging system and a lead-cooled fast reactor afterheat discharging method. The afterheat discharging system consists of three independent working subsystems, namely a magnetic-type heat exchanger active afterheat discharging system, an afterheat-driven passive reactor core cooling system and a passive afterheat discharging system. Through use of a pneumatic pump for supplying water to the secondary side of a steam generator, the problem that the heat releasing function of a secondary loop is lost when a main water supply pump cannot work normally under a power-off working condition is solved; meanwhile, through adoption of a magnetic-type heat exchanger natural circulating cooling loop independent of the active afterheat discharging system in the active afterheat discharging system, the defect that the conventional heat exchanger cannot exchange heat with a reactor core under the power-off working condition is overcome;and therefore, the heat exchange flow of a coolant in the reactor core is greatly increased and discharge of reactor core afterheat is accelerated, so that not only is a guarantee provided for the safety of a reactor, but also a safety guarantee is provided for research of a nuclear submarine powered by a lead-cooled fast reactor, and thus the purpose of enhancing the intrinsic safety of the reactor is achieved.

Description

technical field [0001] The invention belongs to the technical field of nuclear safety control, and in particular relates to an intrinsically safe integrated lead-cooled fast reactor waste heat discharge system and a discharge method combining active and passive. Background technique [0002] In recent years, lead-cooled fast reactors have broad application prospects in the field of nuclear submarine power plants due to their characteristics of hard neutron energy spectrum, strong heat-carrying and heat-transfer capabilities of coolant, and compact structure. my country is also vigorously promoting the development of nuclear submarines powered by lead-cooled fast reactors. A new type of nuclear-powered submarine must meet safety criteria, and one of the most important issues is to ensure the release of nuclear fuel heat release under any circumstances. [0003] At present, the heat energy released by the nuclear fuel after the core shutdown is mainly derived from the steam g...

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Problems solved by technology

[0004] The purpose of the present invention is to provide an intrinsically safe integrated lead-cooled fast reactor waste heat discharge that combines active and passive components in order to solve the problem that the core heat cannot be discharged in time under power-off conditions in the prior art and there are potential safety hazards. The system and discharge method solve the problem that the heat release function of the secondary circuit is lost when the main feed water pump in the active core cooling system cannot work normally under power-off conditions by using a pneumatic pump to supply water to the secondary side of the steam generator; at the same time In the active waste heat removal system, the natural circulation cooling circuit of the magnetic suction heat exchanger independent of the active waste heat removal system is adopted, which solves the disadvantage that the traditional heat exchanger cannot exchange heat for the core under power-off conditions, thus realizing Timely Discharge of Core Waste Heat in Power-off Conditions

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