A thermal conversion system

Abstract

The invention belongs to the technical field of nuclear reactor engineering, and in particular relates to a thermally-operated conversion system which adopts lead or lead-bismuth alloy intermediate loops. The system comprises three loops; a first loop comprises a cold pool, a main pump, a reactor core, a thermal pool and an intermediate heat exchanger arranged in a main container and connected in sequence; a second loop comprises a second loop circulating pump, the intermediate heat exchanger and a steam generator connected in sequence; a third loop comprises a water supplying pump, the steam generator and a steam turbine connected in sequence; a working medium of the first loop is liquid metallic sodium, a working medium of the second loop is liquid metallic lead or a liquid lead-bismuth alloy, and the third loop is a conventional water-steam loop. By adopting the system disclosed by the invention, heat generated by the reactor core can be safely and efficiently brought out of a reactor, so that high-temperature steam is generated in the steam generator and used for pushing the steam turbine to apply work, and heat energy generated by the reactor is converted into mechanical energy.

Description

technical field [0001] The invention belongs to the technical field of nuclear reactor engineering, and in particular relates to a thermal conversion system adopting a lead or lead-bismuth alloy intermediate circuit. Background technique [0002] The thermal conversion system of the reactor uses coolant as the carrier to take the heat generated by the reactor core out of the reactor, so that it can generate high-temperature steam in the steam generator, and drive the steam turbine to do work, converting the thermal energy generated by the reactor into mechanical energy. [0003] Compared with traditional pressurized water reactors, the most notable feature of fast neutron reactors (hereinafter referred to as fast reactors) is that the neutrons in the reactor have higher energy, which enables fast reactors to have the ability to breed nuclear fuel and transmute high-level nuclear waste. It can significantly improve the utilization rate of natural uranium resources, thereby re...

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Problems solved by technology

[0007] But at the same time, lead-cooled fast reactors are also facing great challenges: in terms of thermal properties, compared with sodium, lead has poor thermal conductivity; it has a high density, is corrosive at high temperatures, and severely corrodes structural materials. The flow rate and core outlet temperature are limited, so that the lead-cooled fast reactor cannot reach a high power density, and the lead circuit cannot have too high equipment, and it is also difficult to refuel in a high-temperature lead environment; after irradiation, it will generate Polonium-210, increasing radioactive hazards

[0008] To sum up, the existing fast reactor thermal conversion system has shortcomings such as complex system and low power density.

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