A multipurpose small modular fluoride-salt-cooled high-temperature reactor energy system includes: a reactor body system, a passive residual heat removal system, a compact supercritical carbon dioxide Brayton cycle system, a secondary loop system, and a comprehensive utilization supercritical carbon dioxide Brayton cycle system. Nuclear reactor adopts helical cruciform fuel and graphite matrix material filled with TRISO element, which can improve heat transfer performance and inherent safety. Thermal efficiency of the compact supercritical carbon dioxide Brayton cycle system is above 48%, which can be used in places with limited space. Thermal efficiency of the comprehensive utilization supercritical carbon dioxide Brayton cycle system is above 54%, which can be applied to places with abundant resources. The present invention not only realizes efficient and compact utilization of energy, but also meets the needs of multiple purposes, integrated production, storage and conversion of energy.

A multipurpose small modular fluoride-salt-cooled high-temperature reactor energy system includes: a reactor body system, a passive residual heat removal system, a compact supercritical carbon dioxide Brayton cycle system, a secondary loop system, and a comprehensive utilization supercritical carbon dioxide Brayton cycle system. Nuclear reactor adopts helical cruciform fuel and graphite matrix material filled with TRISO element, which can improve heat transfer performance and inherent safety. Thermal efficiency of the compact supercritical carbon dioxide Brayton cycle system is above 48%, which can be used in places with limited space. Thermal efficiency of the comprehensive utilization supercritical carbon dioxide Brayton cycle system is above 54%, which can be applied to places with abundant resources. The present invention not only realizes efficient and compact utilization of energy, but also meets the needs of multiple purposes, integrated production, storage and conversion of energy.

A system includes a containment vessel configured to prohibit a release of a coolant, and a reactor vessel mounted inside the containment vessel. An outer surface of the reactor vessel is exposed to below atmospheric pressure, wherein substantially all gases are evacuated from within the containment vessel.

A system includes a containment vessel configured to prohibit a release of a coolant, and a reactor vessel mounted inside the containment vessel. An outer surface of the reactor vessel is exposed to below atmospheric pressure, wherein substantially all gases are evacuated from within the containment vessel.

Provided is a secondary shutdown structure of a nuclear reactor, which uses sliding doors, and more particularly, to a secondary shutdown structure of a nuclear reactor, which uses sliding doors and is capable of shutting down a nuclear reactor reliably with a simple structure without using a boric acid solution.

Provided is a secondary shutdown structure of a nuclear reactor, which uses sliding doors, and more particularly, to a secondary shutdown structure of a nuclear reactor, which uses sliding doors and is capable of shutting down a nuclear reactor reliably with a simple structure without using a boric acid solution.

The method and system for bringing a nuclear power plant to a safe state after extreme effect reduce the temperature of the coolant after extreme effect. The system includes inlet and outlet pipelines, a steam generator, a storage tank and a heat exchanger, a separation tank above the steam generator and connected by two pipelines to a storage tank, a pump, a control unit. The method involves filling the system with coolant, feeding the coolant from the steam generator through the inlet pipeline and the storage tank to the heat exchanger, and feeding the coolant through the outlet pipeline back to the steam generator, wherein the pump is turned on for feeding the coolant and subsequent operation of the system. The first air valve is used to maintain pressure in the system, ensuring the absence of boiling of the coolant.

The method and system for bringing a nuclear power plant to a safe state after extreme effect reduce the temperature of the coolant after extreme effect. The system includes inlet and outlet pipelines, a steam generator, a storage tank and a heat exchanger, a separation tank above the steam generator and connected by two pipelines to a storage tank, a pump, a control unit. The method involves filling the system with coolant, feeding the coolant from the steam generator through the inlet pipeline and the storage tank to the heat exchanger, and feeding the coolant through the outlet pipeline back to the steam generator, wherein the pump is turned on for feeding the coolant and subsequent operation of the system. The first air valve is used to maintain pressure in the system, ensuring the absence of boiling of the coolant.

The present invention provides an integrated passive reactor system comprising a pressure vessel, a containment vessel arranged outside the pressure vessel and a reactor core arranged inside the pressure vessel, wherein the primary loop operates in full natural circulation. The integrated reactor system is also provided with a secondary side passive residual heat removal system comprising primary loop heat exchanger(s) arranged inside the pressure vessel and passive residual heat removal heat exchanger(s) arranged outside the containment vessel, wherein the primary loop heat exchanger(s) is/are arranged above the reactor core, the passive residual heat removal heat exchanger(s) is/are arranged inside water tank(s) which is/are fixed outside the containment vessel, and the primary heat exchanger(s) and the passive residual heat removal heat exchanger(s) are connected by heat exchanger inlet pipelines and heat exchanger outlet pipelines. By adopting passive safety technology and passive residual heat removal system, and with the help of top double-layer structure of pressure vessel and break isolation measures, the integrated reactor system according to the present invention can reduce the loss of coolant to the greatest extent, thus meeting the requirements for mitigating design basis accidents, ensuring reactor safety and simplifying the design of the system.

The present invention provides an integrated passive reactor system comprising a pressure vessel, a containment vessel arranged outside the pressure vessel and a reactor core arranged inside the pressure vessel, wherein the primary loop operates in full natural circulation. The integrated reactor system is also provided with a secondary side passive residual heat removal system comprising primary loop heat exchanger(s) arranged inside the pressure vessel and passive residual heat removal heat exchanger(s) arranged outside the containment vessel, wherein the primary loop heat exchanger(s) is/are arranged above the reactor core, the passive residual heat removal heat exchanger(s) is/are arranged inside water tank(s) which is/are fixed outside the containment vessel, and the primary heat exchanger(s) and the passive residual heat removal heat exchanger(s) are connected by heat exchanger inlet pipelines and heat exchanger outlet pipelines. By adopting passive safety technology and passive residual heat removal system, and with the help of top double-layer structure of pressure vessel and break isolation measures, the integrated reactor system according to the present invention can reduce the loss of coolant to the greatest extent, thus meeting the requirements for mitigating design basis accidents, ensuring reactor safety and simplifying the design of the system.