48 results about "Natural uranium" patented technology

A laser inertial-confinement fusion-fission energy power plant is described. The fusion-fission hybrid system uses inertial confinement fusion to produce neutrons from a fusion reaction of deuterium and tritium. The fusion neutrons drive a sub-critical blanket of fissile or fertile fuel. A coolant circulated through the fuel extracts heat from the fuel that is used to generate electricity. The inertial confinement fusion reaction can be implemented using central hot spot or fast ignition fusion, and direct or indirect drive. The fusion neutrons result in ultra-deep burn-up of the fuel in the fission blanket, thus enabling the burning of nuclear waste. Fuels include depleted uranium, natural uranium, enriched uranium, spent nuclear fuel, thorium, and weapons grade plutonium. LIFE engines can meet worldwide electricity needs in a safe and sustainable manner, while drastically shrinking the highly undesirable stockpiles of depleted uranium, spent nuclear fuel and excess weapons materials.

A method with which uranium from a natural uranium concentrate may be purified, includinga) extracting the uranium present as uranyl nitrate in an aqueous phase A1 resulting from the dissolution of the natural uranium concentrate in nitric acid, by means of an organic phase which contains an extractant in an organic diluent;b) washing the organic phase obtained at the end of step a), with an aqueous phase A2; andc) stripping the uranyl nitrate of the organic phase obtained at the end of step b), by circulating this organic phase in an apparatus, as a counter current against an aqueous phase A3.The extractant is an N,N-dialkylamide and the ratio between the flow rate at which the organic phase obtained at the end of step b) and the aqueous phase A3 circulate in the apparatus where step c) occurs, is greater than 1.

The invention relates to a high-temperature supercritical nuclear reactor. A spherical solid is used as a coolant of the nuclear reactor, which is different from common nuclear reactors that adopt light water, heavy water, gas and liquid sodium. The spherical solid coolant can be graphite spheres coated with silicon carbide, stainless steel spheres, graphite spheres coated with stainless steel and the like. The spherical solid has the characteristic of good rolling ability, so that the spherical solid can roll to a steam generator under the action of gravity after heating in the reactor, and the purpose of transferring heat from the reactor to the steam generator is achieved. The reactor is applicable to both thermal neutron reactor and fast neutron reactor, and natural uranium, low-enriched uranium, plutonium and thorium can be used as nuclear fuel. The temperature of high-temperature steam / water outputted by the steam generator can reach 900 DEG C, the same parameters to a thermal power station can be reached, the requirement of supercritical even ultra-supercritical can be satisfied, and the high-temperature supercritical nuclear reactor has high safety and reliability.

The invention relates to a method using a reciprocating sieve plate column to extract and purify native uranium, and the method belongs to the field of extraction. When a pulsed sieve-plate column carries out the extraction and the purification of the native uranium, the energy dissipation is big, the impulse action for feed liquid is not easy to be uniform, and the input and the operation of energy are more difficult. The method has the steps that: when the top interface operation is made and the continuous water phase is adopted, materials are charged towards the reciprocating sieve plate column from an inlet of a water phase, and when a column body which contains a sieve plate series, the water phase stops feeding; a driving device is started, and the vibration frequency is regulated to 80 to 240 per minute according to an organic phase; the flow ratio of the water phase ranges from 1.5 to 3, and an extracting agent is charged towards the column from an inlet of the organic phase; when an interface is established, the rafinate is discharged form an outlet of the water phase through a lower bellend; after the extracting agent of the organic phase begins to pass through an upper bellend to overflow from an outlet of the organic phase, the feeding and the discharging holes of the organic phase and the water phase are respectively provided with the extracting agent and materials to pass in and out according to the flow ratio, and the sieve plate series vibrates. The method has the advantages of simple equipment, stable operation, large flooding loading and low energy consumption.

The invention belongs to the technical field of natural uranium hexafluoride gas-phase transfer, in particular to a natural uranium hexafluoride gas-phase transfer system and a natural uranium hexafluoride gas-phase transfer method. A secondary condenser and a tertiary condenser are arranged above two electronic scales respectively, and ethylene glycol and steam serve as a cold medium and a heat medium respectively. The secondary condenser is provided with two outlets, one of the outlets is connected to an inlet of a primary condenser through a valve J1, and the other outlet is connected to an inlet of the tertiary condenser through a valve J2, a valve J3, a valve J4 and a valve J5. The tertiary condenser is provided with two outlets, one of the outlets is connected to the inlet of the primary condenser through the valve J5 and a valve J7, and the other outlet is connected to an external tail gas treatment process system through a valve J6 and a valve J8. By the system and the method, assistance in pressure-relieved purification and gas-phase transfer of UF6 products in a cold trap can be realized, purity of the natural UF6 products is improved, the metal direct recovery rate is increased, and safety risks in a transfer process are reduced.

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 multi-type fuel assembly mixed-loaded metal cooling reactor and a management method. The core structure of the reactor is an integral honeycomb-shaped regular hexagonal assembly channel, and the channel includes an internal fuel assembly channel, an external fuel assembly channel, and a control system. The rod assembly passage, the internal fuel assembly passage, the external fuel assembly passage, and the control rod assembly passage are provided with multiple cartridges of fuel assemblies in the axial direction, the external fuel assembly passage is arranged on the periphery of the internal fuel assembly passage, and the control rod assembly The channel is arranged crosswise with the internal fuel assembly channel, and the upper and lower ends of the internal fuel assembly channel are arranged with low-cost natural uranium fuel assemblies, and the middle is arranged with enriched uranium fuel assemblies. The invention solves the problems of large loading capacity, high enrichment degree and low utilization rate of the existing metal-cooled reactor core fuel.