36 results about "Neutron multiplication" patented technology

The invention discloses a <99>Mo sub-critical production device and method based on accelerator driving. The <99>Mo sub-critical production device based on accelerator driving comprises an acceleratorunit, a radiation production unit and a separation and purification unit; the accelerator unit sequentially comprises a high-energy particle source, a collimator, an accelerator, a target and a target cavity in an output direction; the high-energy particle source accurately bombards the target positioned in the target cavity at the center of the radiation production unit through the collimator and the accelerator to generate neutron; the radiation production unit adopts a concentric cylindrical structure and sequentially comprises neutron slowing layer, a neutron multiplying layer, a low enriched uranium salt solution and a neutron reflecting layer from inside to outside; and the low enriched uranium salt solution is placed into a fission reaction container to be sealed, the reflecting neutron generated by the target in the target cavity passes through the neutron slowing layer and the neutron multiplying layer to obtain high neutron flux and react with the low enriched uranium salt solution, the solution after reaction enters the separation and purification unit through a pipeline, and the neutron reflecting layer and a shielding layer are arranged sequentially from inside to outside, are positioned on an outer layer and are used for reducing neutron loss.

A hexagon accelerator driven subcritical reactor fuel assembly and a design method thereof are disclosed. The assembly includes a hexagon base the top surface of which is provided with a plurality ofbase units for fuel rod mounting, with one of the base units being at the center of the base, other base units surrounding the center base unit and being arranged in an annular array manner, distancesbetween adjacent base units being equal; a shell including a prismatic sleeve the cross section of which adapts to the shape of the base and the bottom of which is mounted on the base; an inner sleeve including a prismatic sleeve, disposed inside the shell with a gap between the inner sleeve and the shell, with the bottom of the inner sleeve being mounted on the base; and a plurality of fuel rods, wherein each fuel rod includes a cylindric casing and a core rod in the casing and made of fuel, the bottom of each casing is mounted in one base unit, and the number of the fuel rods is equal to the number of the base units. The assembly and the method are used for solving a problem that neutron performance is poor, and technical effects that economic performance and neutron performance are high are achieved.

The invention belongs to the field of fusion and fission hybrid energy reactors and cladding design, and particularly relates to a hybrid reactor system arranged by means of water-cooling thorium fuel modules and water-cooling uranium fuel modules in a staggered mode and an operating method. Natural thorium fuel reaction modules and natural uranium fuel reaction modules are annularly and alternately arranged in an optimized mode, a seed-cladding strategy is made full use of to improve overall neutron economy of the system, the aim of making the best of thorium fuel under high-energy magnification is achieved, namely good neutron performance of the water-cooling natural uranium modules is used for compensating for defects of natural thorium neutron multiplication and energy amplification, achievement of energy amplification and neutron multiplication of the system mainly depends on natural uranium, and redundant neutrons generated from the natural uranium are used for driving natural thorium to operate and multiplying 233U. When 233U in the natural thorium is accumulated to a certain quantity, the natural uranium can be extracted step by step and replaced by new natural thorium, a hybrid reactor can be filled with thorium fuel ultimately, and cycle operations of thorium and uranium are achieved.

The invention discloses a fusion reactor water-helium cold ceramic breeder cladding, which comprises parts such as a first wall, a cooling plate, separators and side plates. The cladding simultaneously adopts water and helium as a coolant, the water is used for cooling the first wall, and the helium is used for cooling the parts except the first wall. The first wall is a U-shaped plate; the cooling plate is in a shape like a Chinese character ao; the cooling plate is located at the inner side of the first wall and is connected with the side wall of the first wall; the cooling plate is crossed with the separators and the side plates, the inner space of the cladding is divided to multiple independent cavities arranged along a radial direction, cavities contacted with the first wall are filled with Li2TiO3 / Be12Ti mixed ball beds as tritium breeding zones, and cavities not contacted with the first wall are filled with Be ball beds as neutron multiplication zones. The fusion reactor water-helium cold ceramic breeder cladding has the advantages that the surface heat flow endurance capability is strong, the tritium production performance is good, the coolant outlet temperature is high, the coolant is well compatible with the neutron multiplication zone material, the flow of the coolant is easy to control, and the development prospect is good.

A method of controlling the criticality of a nuclear fuel cycle facility includes steps of producing a reactor fuel by adding less than 0.1% by weight of gadolinia to a uranium dioxide powder with a uranium enrichment of greater than 5% by weight and controlling the effective neutron multiplication factor of a uranium dioxide system in a step of handling the reactor fuel to be less than or equal to the maximum of the effective neutron multiplication factor of a uranium dioxide system with a uranium enrichment of 5% by weight.

The invention belongs to the field of cladding designs of a fusion and fission hybrid reactor, and particularly relates to a Th-U self-sustaining circulating full fused salt fuel hybrid reactor system and an operation method thereof. The Th-U self-sustaining circulating full fused salt fuel hybrid reactor system is characterized in that a fast fission breeder reactor provides an initial easily fission fuel required by starting of a thermal fission reactor, a cladding design of the thermal fission reactor utilizes an arrangement strategy of a seed-cladding to improve the entirety neutron economy of the system, and the purposes of a high energy enlargement factor of the system, tritium breeding and thorium-uranium self-sustaining circulating of the system are realized; <233>U is loaded in an energy generating region, so that the energy generating region has a good neutronics property and is mainly used for realizing the purposes of energy amplification of the system, neutron multiplication and most <233>U breeding of the system; superfluous neutrons enter a tritium producing region and are used for tritium breeding and part of <233>U breeding of the system. According to the hybrid reactor, due to self-sustaining circulating of thorium and uranium, a thorium fuel is converted into <233>U and is gradually burn up in an operation process, and the Th-U self-sustaining circulating full fused salt fuel hybrid reactor system can effectively and stably operate for a long time just by gradually adding the thorium fuel and removing the generated fission product.

A novel cladding structure for a fusion reactor comprises a U-shaped first wall, cover plates, a front back plate, a rear back plate and a proliferation unit, the U-shaped first wall and the upper andlower cover plates are internally provided with slots, and the upper and lower cover plate and the U-shaped first wall are welded to the front and rear back plates, thereby forming a sealed outer box. The proliferation unit is inserted in the front and rear back plates to be fixedly connected, an internal tritium proliferation agent is wrapped by a cooling plate in the form of a pebble bed, and the pebble bed and the cooling plate are sealed in a neutron multiplication agent. The front and rear back plates and the upper and lower cover plate and the U-shaped first wall form a six-layer platelike gas header which is used for collecting and reallocating coolants and purge gas. According to the novel cladding structure for a fusion reactor, on the premise of ensuring a module proliferation effect, a central area adopts an M-shaped cooling channel, thus a cooling effect can be better improved, and installation procedures are reduced, thereby facilitating replacement and maintenance.