The invention discloses a protection method for digitalized instrument control diversity of a nuclear power station. The method comprises the following steps that a diverse actuation system (DAS) is used for obtaining a common cause failure (CCF) which is formed by overlapping abnormal working status of the nuclear power station; the DAS is used for driving manual control on operation and control of a key safe function in the CCF, the key safe function comprises at least one of reaction control, waste heat elimination, a reactor coolant device, containment isolation and containment integrity; if the operation and control of the key safe function can not be subjected to the manual control according to the requirement of response time, the DAS is used for implementing automatic driving operation. According to the protection method for the digitalized instrument control diversity of the nuclear power station, occurrence of the CCF can be effectively prevented. Additionally, the invention further discloses a protection system for the digitalized instrument control diversity of the nuclear station.

Protection method and system for digitalized instrument control diversity of nuclear power station

The invention belongs to the technical field of nuclear power design, and particularly relates to a function analysis method for operational control under accident condition of a nuclear plant with a digital human machine interface. The method comprises the following steps of firstly determining a selecting rule of function modules in accident operation regulations, screening the functions in the accident operation regulations according to the rule, obtaining a lift of functions which need to be treated with modularization design, then, integrating and screening the information of the function modules to determine an information list of comprehensive display control function, and finally, arranging the information list of comprehensive display control function according to an arrangement principle. The function analysis method is used for designing a related accident regulation comprehensive display control function, providing comprehensive monitoring and control information needed in the accident management process for operators, and improving accident management efficiency so as to reduce risks caused by accidents.

Function analysis method for operational control under accident condition of nuclear plant with digital human machine interface

The invention provides an internal part cooling power generation system for a future tokamak fusion reactor. The system comprises a divertor cooling circuit, a cladding cooling circuit and a main cooling circuit. The system is characterized in that the divertor cooling circuit comprises a first heat exchanger, a pump and a divertor; a coolant is inflated by the pump from one side of the first heat exchanger, flows into the divertor, and flows back to the first heat exchanger from the other side of the divertor; the cladding cooling circuit comprises a first main circuit, a first auxiliary circuit and a supplemental coolant circuit; and the main cooling circuit comprises a second main circuit and a second auxiliary circuit. According to the invention, on the premise that a tokamak device can continuously stably operate, cooling and power generation are integrated, and the system has the advantages of stability, safety, reliability and high efficiency.

Internal part cooling power generation system for future tokamak fusion reactor

The invention discloses a Z-pinch driven fusion-fission hybrid energy reactor The Z-pinch driven fusion-fission hybrid energy reactor comprises a Z-pinch inertial confinement fusion reactor core, a subcritical fission cladding and energy output system, and a tritium production cladding and deuterium-tritium circulation system The fusion reactor core comprises a fusion load, fusion targets, a fusion driver and a fusion target chamber supporting continuous operation of fusion The subcritical fission cladding and energy output system comprises a subcritical cladding, a cooling loop, a steam generator and a voltage stabilizer The tritium production cladding and deuterium-tritium circulation system comprises a tritium production cladding, a reactor core residual tritium recovery system and an out-of-reactor tritium factory According to the Z-pinch driven fusion-fission hybrid energy reactor, the inertial confinement fusion reactor core scheme based on the integrated ignition technology is high in realizability and reliable in performance, depleted uranium and thorium can be fully utilized, and therefore the fission resource utilization efficiency is improved; the whole fusion-fission hybrid energy reactor is reasonable and balanced in design, the subcritical cladding is driven through the Z-pinch fusion reactor core, and long-term sufficient clean electrical energy can be provided

Z-pinch driven fusion-fission hybrid energy reactor

The invention relates to a double-layer fresh fuel storage system capable of meeting the requirement on criticality safety The storage system is arranged in a dry storage well (1) and comprises a plurality of small storage chambers (2); an upper fresh fuel component and a lower fresh fuel component (3) are arranged in each small storage chamber (2); each fresh fuel component (3) is arranged in the corresponding small storage chamber (2) by a storage hanging bracket (4) According to the storage system, the effective space in unit area is fully utilized to improve the fresh fuel storage capacity in the storage well, and thus the problem that the plant capacity is limited can be solved; furthermore, the neutron coupling effect between the upper layer of fuel components and the lower layer of fuel components of the storage system is almost zero, so that the requirement on storage criticality safety can be met

Double-layer fresh fuel storage system capable of meeting requirement on criticality safety

The invention relates to an accident analysis method for a digital control diversity protection system of a million-kilowatt nuclear power station. The method analyzes that a pile main protection system of a 'digital control system (DCS)' in a million-kilowatt nuclear power project is in software common cause failure, and simultaneously, the method superposes the expected operation transient or design basis accident, in the case that an operator has no time to perform manual intervention, the method further researches on adding a diverse actuation system (DAS) in the DCS to ensure the safety of the pile. A DAS scheme is determined after rounded accident analysis of the nuclear power station, and the DAS scheme comprises corresponding automatic protection signals and setting values, so as to guarantee that the accident consequence meets the requirement of a 'diversity and defense in depth (3D)' acceptance criterion.

Accident analysis method for digital control diversity protection system of million-kilowatt nuclear power station

The invention relates to a boron-untrusted controlling method for criticality safety of a spent fuel pool framework. Isolation regions are arranged around the spent fuel pool framework so as to prevent increase of reactivity caused by falling-off of a fuel assembly, and storage space of spent fuel assemblies is increased to reduce reactivity of a whole system. With such a technical scheme provided by the invention, under normal and credible accident working conditions, a spent fuel storage pool can realize high density storage in virtue of addition of solid neutron poison and combustion of trusted spent fuel assemblies while guaranteeing criticality safety, without trusting of soluble boron in water at the same time.

Boron-untrusted controlling method for criticality safety of spent fuel pool framework

The invention belongs to the technology of nuclear power design, and particularly relates to design of an advanced fusion-fission subcritical energy reactor core tritium-production blanket. The advanced fusion-fission subcritical energy reactor core tritium-production blanket structurally comprises multiple layers of tritium-production materials, moderator water is arranged between every two adjacent layers of tritium-production materials, zirconium partition boards are arranged between the tritium-production materials and the moderator water, and a zirconium casing is arranged outside the tritium-production blanket. According to the advanced fusion-fission subcritical energy reactor core tritium-production blanket, the tritium-production materials and the moderator water are arranged at intervals and are separated through zirconium layers with certain thicknesses; interval arrangement is optimized so that the tritium breeding ratio can be as large as possible, and the tritium-production blanket can meet the design requirement for the tritium breeding ratio of a subcritical energy reactor core.

Advanced fusion-fission subcritical energy reactor core tritium-production blanket

The invention belongs to a nuclear power design technique, and particularly relates to a loading scheme of an advanced fusion-fission subcritical energy reactor core The reactor core structure comprises a plurality of fuel assembly modules which are arranged in a hoop along an annular plasma fusion area, wherein each fuel assembly module comprises a plurality of fuel assemblies arranged in a polar direction of the plasma fusion area; a first heat-resistant and radiation-resistant wall is arranged at one side of each fuel assembly towards the plasma fusion area; a tritium-producing coating is arranged at the other side of each fuel assembly opposite to each first wall; an outer shielding layer is arranged outside each tritium-producing coating By adopting the advanced fusion-fission subcritical energy reactor core, the design requirements of the energy magnification factor and the tritium breeding ratio can be simultaneously met; the continuous growth of the magnification factor and the tritium breeding ratio can be maintained within a long period of time; the breeding performance of the reactor core is good

Yi Xuan

Papers

Accident analysis method for digital control diversity protection system of million-kilowatt nuclear power station

Boron-untrusted controlling method for criticality safety of spent fuel pool framework

Advanced fusion-fission subcritical energy reactor core tritium-production blanket

Advanced fusion-fission subcritical energy reactor core

Double-layer fresh fuel storage system capable of meeting requirement on criticality safety