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 subcritical energy cladding accident mitigation system. The subcritical energy cladding accident mitigation system comprises a passive water injection system and at least one group of passive cooling systems, wherein the passive water injection system is arranged in a containment shell and is used for injecting water into a subcritical energy cladding arranged in the containment shell, so that heat of the subcritical energy cladding is conducted into the containment shell; the passive cooling system penetrates through the containment shell in a sealing manner, so as to conduct the heat in the containment shell out of the containment shell; the passive water injection system can automatically conduct the heat of the subcritical energy cladding into the containment shell, cooling mediums are circulated in the passive cooling system, so as to conduct the heat in the containment shell into atmospheric environment; heat can be conducted passively from a hybrid reactor core to the containment shell and from the inside of the containment shell to the outside of the containment shell under an accident, all waste heat of the subcritical energy cladding during running can be completely covered and exhausted, serious accidents such as hybrid reactor core melting, high-pressure molten reactor, and hydrogen gas explosion can be effectively prevented, and the integrity of the subcritical energy cladding is ensured.

Subcritical energy cladding accident mitigation system

The invention discloses a thin-wall fusion target chamber for a Z-pinch driven fusion-fission hybrid power reactor and belongs to the field of a nuclear reactor device The thin-wall fusion target chamber comprises a target chamber enclosed by a plasma facing first wall The inner wall surface of the plasma facing first wall is provided with a thermal ablation protective layer; the target chamber is in a ball-shaped housing structure; the upper end of the target chamber is provided with a refueling (target) channel opening, and the lower end is provided with a waste-removing channel opening; the ball-shaped housing structure carries out segmentation on a plurality of faces passing the three points of the center of the refuelingchannel opening, the center of the ball-shaped housing structure and the center of the waste-removing channel opening to form a plurality of structure units; the ball-shaped housing structure of the target chamber is formed by splicing the plurality of structure units; and the cross section of each structure unit is in arc shape which protrudes to the inner portion of the target chamber The target chamber designed in the invention can deal with the thermodynamic impact and mechanical impact produced during the fusion reaction, and can meet the Z-FFR neutron physics performance requirements

Thin-wall fusion target chamber for Z-pinch driven fusion-fission hybrid power reactor

The invention discloses a method applied to fusion reactor cladding accurate engineering design. The method comprises the following steps: firstly, performing plasma calculation to obtain anisotropicneutron source distribution and cladding first wall surface heat flux density distribution; combining anisotropic neutron source distribution obtained through plasma calculation in neutron transport physics calculation with material temperature distribution obtained through thermohydraulics calculation, and obtaining cladding core heat source distribution and cladding tritium propagation rate; obtaining material temperature distribution of different areas in the cladding by utilizing cladding first wall surface heat flux density distribution provided by plasma calculation and nuclear heat source distribution provided by neutron transport calculation in thermal hydraulics calculation; neutron transport calculation and thermal hydraulics calculation needing to be mutually iterated until therequirements of material temperature safe operation limitation and cladding tritium propagation rate are met. According to the method, engineering design can be carried out on the fusion reactor cladding in the real service environment of the cladding, the defect that in a traditional method, an isotropic neutron source and the surface heat flux of the first wall of the uniform cladding are adopted is overcome, and accurate engineering design of the cladding is achieved.

Method applied to fusion reactor cladding accurate engineering design

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

Zhou Zhe

Papers

Advanced fusion-fission subcritical energy reactor core