47 results about "Natural uranium" patented technology

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 discloses a natural gamma-ray spectral logging instrument, which comprises a probe, an operating platform and a winch cable, wherein the probe is connected and communicates with the operating platform through the winch cable, and the probe comprises a detector and an electronics system; the detector comprises a spectrum stabilization device, a detecting element, a photoconductive element, a photomultiplier and a pre-amplification circuit; the electronics system inside the probe comprises an amplifier, a multichannel analyzer, a controller, a memory, a high-voltage power supply and a low-voltage power supply; the detecting element is one of a BGO crystal or a LaBr3 (Ce) crystal; the spectrum stabilization device comprises a shell body and a spectrum stabilization substance arranged in the shell body; and the spectrum stabilization substance is pressed into a pie shape and arranged in the shell body. The natural gamma-ray spectral logging instrument provided by the invention adopts the BGO or LaBr3 (Ce) crystal detector, is high in sensitivity, has good resolution, is internally provided with the natural substance for automatic spectrum stabilization, is convenient to use, and mainly measures gross-count rate caused by natural radioactivity in underground rock and contents and distribution data of natural uranium, thorium and potassium.

The present invention provides a method for quickly investigating and evaluating the radioactive radiation environment of a coalfield with multiple parameters on site, which uses a multi-channel gamma energy spectrometer on the ground or in a well to measure natural uranium, uranium, The nuclide content of thorium and potassium and the total radioactivity of gamma can be used to calculate the activity concentration of uranium, thorium and potassium in the coal field by using the conversion coefficient of the radionuclide content and the activity concentration unit; according to the activity concentration of uranium, thorium and potassium in the coal field On-site calculation of gamma radiation dose rate; on-site estimation of the effective dose equivalent of coal field environment gamma radiation to residents based on gamma radiation dose rate; finally, this technology can replace laboratory analysis and on-site gamma radiation dose rate measurement, and provide uranium, thorium, Nuclide content of potassium, activity concentration of uranium, thorium, and potassium, environmental gamma radiation dose rate, effective dose equivalent of gamma radiation to residents, in order to achieve rapid, economical and multi-parameter completion of coal field radioactive radiation environmental investigation and evaluation.

The invention belongs to the design technique of nuclear power and particularly relates to an advanced fusion-fission subcritical energy source reactor core fuel assembly. The fuel assembly comprises multiple layers of structures sequentially arranged along the thickness direction, wherein each layer of structure comprises a plurality of grid units, the grid units are arranged along the height direction and are provided with uranium-zirconium alloy fuels, a cooling tube horizontally penetrates through the uranium-zirconium alloy fuels of each grid unit, the extending direction of the cooling tube is vertical to the thickness direction of the fuel assembly, and flowable cooling agents are filled in the cooling tubes. According to the advanced fusion-fission subcritical energy source reactor core fuel assembly, the natural uranium and zirconium alloys are taken as fission fuels, the cooling tubes are arranged in the fuels in a regular triangle manner, and the cooling of the fuels can be guaranteed due to the arrangement manner of the cooling tubes. The fuel assembly has the advantages that the uranium-water volume ratio is proper, and a reactor core can have an enough energy amplification factor.

The invention discloses a vibrating ring-shaped traverse baffle extracting tower belonging to the field of extraction and a method for extracting and purifying natural uranium by using the extracting tower. The extracting tower comprises a central shaft arranged at the center in a tower body, and an internal ring plate, one pipe spacer, an external ring plate and the other pipe spacer are sleeved on the central shaft one by one at intervals, so that a traverse baffle string can be formed; a motor fixedly arranged on the upper part of the upper expansion end at the upper end of the tower body drives the traverse baffle string to move up and down by a cam; and the upper expansion end and a lower expansion end arranged on the lower part of the tower body are respectively provided with a light/heavy phase inlet and a light/heavy phase outlet. The method for extracting and purifying the natural uranium by the extracting tower comprises the following steps of: charging a material into the tower from the heavy phase inlet of the upper end; and turning on a motor, and charging an extracting agent into the tower from the light phase inlet of the lower end in a flow ratio of organic phase to water phase of 0.5-10, so that the countercurrent extraction of downward water phase and upward organic phase can be formed. The extracting tower disclosed by the invention is simple in structure, large in flux and high in efficiency; and the method disclosed by the invention is environment-friendly and energy-saving, and is low in cost.

In a method for improving the energy generating output of a nuclear reactor containing one or more fuel rods in one or more fuel rod bundles while satisfying a maximum subcritical banked withdrawal position (MSBWP) reactivity limit, enrichments of individual fuel rods in an axial cross-section of a lattice being evaluated at the top of the fuel bundle are ranked, and the fuel pins of the highest ranked rod location in the lattice are replaced with natural uranium pins. A core simulation is then performed to determine whether there is any margin to a MSBWP reactivity limit. For each lower ranked candidate rod position, the pin replacing and core simulation functions are repeated until no rod location violates the MSBWP reactivity limit, so as to achieve a desired lattice design for the top of the fuel bundle.

The invention belongs to the field of nuclear reactor engineering, in particular to a follower component driven by a driving mechanism in a pressure shell and a water reactor adopting the same. The invention realizes the spectral shift control of a reactor and compansates the decrease of reactivity in a burn-up process by a depleted uranium (or thorium) compound follower, and adopts a dense weir and residential uranium compound fuel postprocessed by partially utilizing natural uranium and spent fuel, thereby greatly saving nuclear fuel and decreasing fuel cycle cost. A driving mechanisms driving a great amount of follower components are arranged in the pressure shell, so as to prevent the joint sections of the driving mechanism from penetrating through the upper sealing head of the pressure shell, carry out the spectral shift control under the condition without influencing the reliability of the pressure shell, lower the boron concentration of the water reactor in water in an operation process, avoid the occurrence of the problem of serious corrosion of the joint sections and the upper sealing head of the driving mechanism due to the penetration of boric acid through the upper sealing head of the pressure shell, reduce the possibility of elastic rod accidents and improve the safety.

The invention relates to the technical field of nuclear fuel transportation systems, and in particular, discloses a container for natural uranium hexafluoride transportation. The container for natural uranium hexafluoride transportation comprises a cylinder, a left seal and a right seal, wherein two ends of the cylindrical cylinder are fixedly sealed through the left seal and the right seal with standard elliptic structures; a thick wall skirt base is arranged on the left seal; a valve is arranged on the left seal; a thin wall skirt base is arranged on the right seal; and a plug is arranged on the right seal. The container for natural uranium hexafluoride transportation can satisfy the performance test requirements after free fall in the radioactive substance safe transportation management regulation.

The invention relates to equipment capable of detecting a uranium ore in real time in a coring drilling process. A while-drilling gamma uranium measuring instrument based on rock core drilling is characterized by comprising an outer pipe, an inner pipe, a battery component, a fastening pressure spring and a sensor, wherein the outer pipe is a non-magnetic drill rod; the inner pipe is positioned in the outer pipe, and comprises a power supply switch fixing piece, a battery bin compression-resisting cylinder, a first compression-resisting cylinder connecting head, a circuit board bin compression-resisting cylinder, a second compression-resisting cylinder connecting head, a sensor bin compression-resisting cylinder and a plug screw; the battery component supplies power to a signal processing circuit and the sensor; the sensor is positioned in the sensor bin compression-resisting cylinder, and is connected with a sensor signal input end of the signal processing circuit; the signal processing circuit comprises a single-chip microcomputer; and the single-chip microcomputer is connected with a storer through an interface circuit. The instrument can perform the uranium ore exploration for a stratum difficult to obtain a rock core, through measuring natural gamma strength of the stratum, and measures the natural gamma strength while drilling in the coring drilling process to judge if the drilled stratum is the uranium ore.

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.

A method with which uranium from a natural uranium concentrate may be purified, including

a) 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; and

c) 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 provides a method for applying uranium recycled from a pressurized water reactor to a heavy water reactor. The method replaces natural uranium with natural uranium equivalent to produce a fuel for the heavy water reactor on a heavy water reactor fuel production line. The natural uranium equivalent is prepared through the following steps: (1) measuring the metal uranium content, uranium isotope composition and/or uranium isotope distribution of recycled uranium and depleted uranium by using a mass spectrometer; (2) according to the uranium isotope composition of the recycled uranium and depleted uranium, calculating the mixing ratios alpha and 1-alpha of the recycled uranium and depleted uranium and target value of natural uranium equivalent according to a formula or mixing computation procedure so as to achieve the effect equivalent to the effect of natural uranium; 3) accurately measuring the recycled uranium and depleted uranium and then carrying out physical mixing so as to form natural uranium equivalent; (4) carrying out sampling analysis on the natural uranium equivalent formed through mixing; and (5) replacing natural uranium with the natural uranium equivalent to produce the fuel for the heavy water reactor. The method provided by the invention avoids the influence of high radioactivity of the recycled uranium, realizes economic high-efficiency utilization of the recycled uranium and reduces cost of the fuel of the heavy water reactor.

The invention belongs to the technical field of a nuclear fuel circulating natural uranium purification process and particularly relates to a fixing method of a pulse baffle column plate string. Meanwhile, fixation between baffles is enhanced through adopting a self-gravity effect of the baffles. Compared with other fixing methods including traditional welding and the like, an active fixing method is adopted, so that the linearity and concentricity between a central column and the plate string are effectively reduced. A distance sink tube guarantees that the distance between the baffles is strictly equal, so that the whole fixation of each baffle is facilitated and an easy-to-move part is not adopted; and fluid can conveniently and regularly flow in a baffle pulse column, and the stability and the two-phase mass transferring effect are enhanced.

The invention provides a method for replacing and repairing underground water of an in-situ leaching uranium mining base by adopting sewage pumping and clean water injection, and belongs to the technical field of underground water treatment. The method comprises the following steps that clean water is injected into surrounding liquid injection holes while underground water is pumped out of liquid pumping holes of the in-situ leaching uranium mining base; and according to the method, the underground water is repaired by adopting a pollution-pumping, clean-water-injection and replacement repair technology, a specific liquid pumping hole is selected to pump out polluted water, and a liquid injection hole is selected to inject clean water to replace the polluted water with the clean water, so that the radionuclide natural uranium, radium-226 and non-radioactive pollutant concentration of the underground water of the in-situ leaching well site reach a repair target value.

The invention discloses a high-burnup fast neutron reactor metal fuel, a reactor core is loaded with a metal fuel, and the metal fuel adopts a natural uranium U-50Zr alloy. Phase change is achieved by manually controlling the temperature, fuel consumption is improved, and the service life of fuel is prolonged; the burnup of fuel is increased, the utilization rate of uranium is increased, and the pressure for treating nuclear waste is reduced; the service life of the fuel is prolonged, the nuclear power cost is reduced, and the nuclear energy economy is improved; and timely release of fission gas and periodic elimination of fuel defects are effectively carried out, core-cladding mechanical interaction caused by swelling is reduced, and safety is improved.

Tester for monitoring alpha contamination of fuel elements containing tandem loading module and unloading module of fuel elements, each having a fixed frame with cradles, position indicators of fuel elements, measurement module located between the loading module and unloading module, which includes the detection units of alpha radiation from the surface of fuel elements, pneumatic cylinders with position indicators of the rods for samples forwarding with the source of alpha radiation. The loading module is supplied with a movable automated carriage with cradles for forwarding fuel elements to the measurement module and then to the unloading module, besides the loading and unloading modules are provided with movable racks for placing the fuel elements on the cradles of the modules and carriage, and the samples with natural uranium isotopes are used as the source of alpha radiation for setup of the measurement module.