Abstract: The present disclosure relates to the technical field of reactor engineering, and particularly, to a nuclear power plant spent fuel negative pressure unloading system, comprising a fuel element transport pipe and a gas transport pipe. The fuel element transport pipe comprises a fuel element output pipe, a fuel element lifting pipe, and a fuel element unloading pipe connected in series. The fuel element unloading pipe is arranged obliquely downward in the direction of fuel element movement. The distal end of the fuel element unloading pipe is connected sequentially to fuel loading apparatus and a transfer apparatus. Two nozzles of the gas transport pipe are connected to set positions on the fuel element output pipe and the fuel element unloading pipe respectively. Gas driving mechanisms are connected to the gas transport pipe. An inlet of the gas driving mechanism is arranged at one end in proximity to the fuel element unloading pipe.

Abstract: A system for continuously preparing coated particles in a large scale comprises: a coating furnace, a cooling facility, a solid by-product treatment device, and a gas by-product treatment device connected in sequence. The coating furnace is used for coating particles. The cooling facility is used for cooling the coated particles. The solid by-product treatment device is used for treating solid by-products generated in the coating furnace during the particle coating process. The gas by-product treatment device is used for treating gas by-products generated in the coating furnace during the particle coating process. The system for continuously preparing coated particles resolves the problem that a system in the prior art, aiming at batch production, has a time interval between two batches, wherein a temperature increase process and a temperature decrease process both exist, and is small in scale, does not completely break through laboratory research and cannot achieve real industrial continuous preparation.

Abstract: A spherical fuel element forming apparatus comprises a fuel area forming system, a fuel-free area shaping system and a green sphere pressing system connected sequentially. The fuel area forming system is used for evenly mixing a core sphere matrix powder with nuclear fuel particles and then pressing the mixed core sphere matrix powder and nuclear fuel particles into core spheres. The fuel-free area shaping system is used for preparing a spherical fuel element from the core spheres covered by a fuel-free matrix powder. The green sphere pressing system is used for pressing the spherical fuel elements into green spheres. The spherical fuel element forming apparatus is distributed according to a technical process flow line operation, and is compact in structure and convenient to operate. Sphere greens after being finally pressed are high in sphericity, fuel element cost is lowered, and the finished product rate is high.

Abstract: A residual heat removal ventilation system for spent fuel dry storage facility of nuclear power plant includes a natural ventilation apparatus and a forced ventilation apparatus, comprising a cold air intake chamber, a hot air removal chamber, a pipeline, a ventilation heat shield cylinder, a heat removal fan, and an air cooling equipment having certain connecting relationships and being correspondingly arranged in a storeroom, an operating room and a ventilation equipment room. The system doesn't require storing spent fuel in a pool storage manner. The safety of the spent fuel doesn't rely on power equipment, thus not only reducing routine maintenance, saving energy, but also has inherent safety. Furthermore, the system can be used to cool spent fuel storage canisters within spent fuel storage facility of pebble bed high temperature gas-cooled reactor nuclear power plant, and discharge residual heat of spent fuel storage canisters to the external environment.

Abstract: A channel baffle structure comprises a pipe, a swing check plate and a driving apparatus, wherein the main part of the swing check plate is located inside the pipe, and the driving apparatus is disposed outside the pipe. A connection structure is used for connecting the driving apparatus and the swing check plate. The check plate can be opened and closed passively by gravity and fluid pressure, but can also be actively opened and closed by the driving apparatus, such that requirements for multiple operating conditions of the channel can be satisfied.

Abstract: A reactor lateral reflection layer telescoped control rod capable of separately achieving cold shutdown includes an inner rod, an outer rod and a guide cylinder assembly which are vertically and coaxially arranged, wherein the outer rod and the guide cylinder assembly are hollow cylindrical bodies; the top end of the inner rod can move up and down inside the outer rod and the other end of the inner rod moves up and down, along with the top end, inside a control rod passage which is positioned below the guide cylinder assembly and is coaxial with the guide cylinder assembly; and the top end of the outer rod can move up and down in the guide cylinder assembly and the other end of the outer rod moves up and down, along with the top end, inside the control rod passage.

Abstract: A high-temperature gas-cooled reactor steam generating system comprises a plurality of nuclear steam supply systems, a high-pressure cylinder (21), a low-pressure cylinder (22), a condenser (23), a condensate pump (24), a low-pressure heater (25), a deaerator (26), a water supply pump (27), and a high-pressure heater (28) which are sequentially connected end to end to form a close steam loop. On one hand, the inherent safety of the reactor is guaranteed and the generating system is simplified with the inherent safety. On the other hand, the scale economy of the steam engine system and other systems of a whole power station is guaranteed through batch copy, a shared auxiliary system and a scale effect.

Abstract: A steam generator includes a heat exchanger, a liquid header and a steam header. The heat exchanger is assembled by several heat exchanging subassemblies with the same structure. The heat exchanging subassembly includes a spiral heat transmission pipe bundle, a central cylinder and a sleeve. The spiral heat transmission pipes with different radii are concentrically and spirally arranged in an annular space between the central cylinder and the sleeve, to form one or more concentric heat exchanging pillar surfaces. One end of the liquid header is connected with a main water feeding pipe, and the other end of the liquid header is connected with the spiral heat transmission pipe bundle. One end of the steam header is connected with a main steam pipe, and the other end of the steam header is connected with the spiral heat transmission pipe bundle.

Abstract: A sealed transmission device for a helium space of a high temperature gas cooled reactor and a drive device thereof are disclosed. The helium space (1) is enclosed by a chamber body (2), a pressure-bearing casing (3), a fastener (4) and a sealing element (5). A transmission member (8) is connected with an executing member (6) inside the helium space (1) and a motive member (7) outside the helium space (1) and transmits movements between them. The transmission member (8) is a magnetic shaft coupling which includes the pressure-bearing casing (3), a driving magnetic component (9) arranged outside the pressure-bearing casing (3) and a driven magnetic component (10) arranged inside the pressure-bearing casing (3). The motive member (7) and the driving magnetic component (9) are connected to each other to form a driving member, and the executing member (6) and the driven magnetic component (10) are connected to each other to form a driven member.

Abstract: A steam generator includes a heat exchanger, a liquid header and a steam header. The heat exchanger is assembled by several heat exchanging subassemblies with the same structure. The heat exchanging subassembly includes a spiral heat transmission pipe bundle, a central cylinder and a sleeve. The spiral heat transmission pipes with different radii are concentrically and spirally arranged in an annular space between the central cylinder and the sleeve, to form one or more concentric heat exchanging pillar surfaces. One end of the liquid header is connected with a main water feeding pipe, and the other end of the liquid header is connected with the spiral heat transmission pipe bundle. One end of the steam header is connected with a main steam pipe, and the other end of the steam header is connected with the spiral heat transmission pipe bundle.

Abstract: A sealed transmission device for a helium space of a high temperature gas cooled reactor and a drive device thereof are disclosed. The helium space (1) is enclosed by a chamber body (2), a pressure-bearing casing (3), a fastener (4) and a sealing element (5). A transmission member (8) is connected with an executing member (6) inside the helium space (1) and a motive member (7) outside the helium space (1) and transmits movements between them. The transmission member (8) is a magnetic shaft coupling which includes the pressure-bearing casing (3), a driving magnetic component (9) arranged outside the pressure-bearing casing (3) and a driven magnetic component (10) arranged inside the pressure-bearing casing (3). The motive member (7) and the driving magnetic component (9) are connected to each other to form a driving member, and the executing member (6) and the driven magnetic component (10) are connected to each other to form a driven member.

Abstract: A high-temperature gas-cooled reactor steam generating system comprises a plurality of nuclear steam supply systems, a high-pressure cylinder (21), a low-pressure cylinder (22), a condenser (23), a condensate pump (24), a low-pressure heater (25), a deaerator (26), a water supply pump (27), and a high-pressure heater (28) which are sequentially connected end to end to form a close steam loop. On one hand, the inherent safety of the reactor is guaranteed and the generating system is simplified with the inherent safety. On the other hand, the scale economy of the steam engine system and other systems of a whole power station is guaranteed through batch copy, a shared auxiliary system and a scale effect.

Abstract: A steam generator includes a heat exchanger, a liquid header and a steam header. The heat exchanger is assembled by several heat exchanging subassemblies with the same structure. The heat exchanging subassembly includes a spiral heat transmission pipe bundle, a central cylinder and a sleeve. The spiral heat transmission pipes with different radii are concentrically and spirally arranged in an annular space between the central cylinder and the sleeve, to form one or more concentric heat exchanging pillar surfaces. One end of the liquid header is connected with a main water feeding pipe, and the other end of the liquid header is connected with the spiral heat transmission pipe bundle. One end of the steam header is connected with a main steam pipe, and the other end of the steam header is connected with the spiral heat transmission pipe bundle.