12 results about "Natural uranium" patented technology

The present application relates to a kind of large-scale industrial grade natural uranium extraction column modeling simulation method.Establish the mass transfer diffusion model of pulse baffle extraction column, establish the thermodynamic model of uranyl nitrate extraction process, establish the hydraulics model of pulse baffle extraction column, the thermodynamic model of uranyl nitrate extraction process and the hydraulics model of pulse baffle extraction column are combined, mass transfer diffusion model is solved using Runge-Kutta method, i.e., the uranyl nitrate concentration result of outlet water phase and organic phase of pulse baffle extraction column can be calculated;The calculation result is checked, the final calculation result is obtained for the output meeting the requirements, and the calculation is returned again for the output not meeting the requirements.The present application can simulate the extraction process of uranyl nitrate with concentration up to 450g / L in industrial pulse baffle column, the simulation result has high precision, and the error between simulation result and measured value of uranyl nitrate extracted by real pulse baffle extraction column is within 8%.

The invention discloses a logistics intelligent management system and method applied to natural uranium buckets, and relates to the technical field of logistics managements.According to the logistics intelligent management system and method, information is obtained and classified by scanning labels of the natural uranium buckets, the unused, used and unqualified natural uranium buckets are treated respectively, it is ensured that the natural uranium buckets to be used are safe and reliable, and the logistics management efficiency is improved. And a qualified container is provided for subsequent uranium loading and transportation. By checking transportation tools and personnel qualifications, monitoring data such as position, pressure and radiation in real time in the transportation process, detecting and feeding back the data by using a safety sensor, and adjusting a transportation strategy according to road conditions, congestion degrees and the like, full-chain radioactive safe transportation after natural uranium barrels are filled with uranium is realized. Through obtaining the used natural uranium barrels approved by the supervision department, performing classified storage, performing regular inspection and maintenance, and recording and archiving related information, the subsequent use safety of the natural uranium barrels is ensured, and the whole-process intelligent management of the natural uranium barrels is realized.

The invention discloses a natural uranium barrel transportation device with a dynamic balance adjusting function, and relates to the technical field of nuclear raw material transportation devices.A natural uranium barrel is placed on a bearing seat, a fixing mechanism is driven by the gravity of the natural uranium barrel to clamp and fix the natural uranium barrel, and a compensation mechanism compensates for temperature change or pressure change caused by impact; and the bearing seat is adjusted in the reverse direction of inclination of the base in real time through the balance mechanism, then the bearing seat is kept in dynamic horizontal balance, the multi-stage damping effect is formed through the damping mechanism, and therefore it is ensured that the natural uranium barrel is stable.

The invention discloses a natural uranium barrel logistics storage data transmission system and method based on the Internet of Things, and relates to the technical field of the Internet of Things. According to the natural uranium barrel storage data, abnormal state judgment and abnormal screening processing are carried out on all the natural uranium barrels, and real-time storage state evaluation is carried out on the processed natural uranium barrels; constructing a space storage model by combining the storage space data of the storage area to which the corresponding natural uranium barrel belongs, and performing real-time storage space state evaluation analysis on the storage space data of each storage area according to the space storage model; according to real-time storage space state evaluation analysis data of the storage space data of each storage area, regulating and controlling the storage space data of each storage area, and marking a natural uranium barrel ex-warehouse sequence of a corresponding storage space; according to the invention, automatic data acquisition and state supervision of the natural uranium barrels are realized, automatic analysis and flexible regulation and control are carried out on the bin position data, and the bin management efficiency and accuracy of the natural uranium barrels are improved.

The invention provides a method for preparing nuclear pure grade uranium hexafluoride, which comprises the following steps: (1) adding fluoride containing molybdenum, tungsten, vanadium, titanium, chromium and antimony and crude uranium hexafluoride of hydrogen fluoride impurities into a distillation kettle, and carrying out pressurized distillation to obtain a gaseous mixture; (2) introducing the gaseous mixture obtained in the step (1) into a calcium fluoride adsorption column, and removing hydrogen fluoride in the mixture through selective adsorption of calcium fluoride; and (3) carrying out single-tower pressurized distillation on the gaseous mixture treated in the step (2) to obtain nuclear pure grade uranium hexafluoride. The method solves the problems of low uranium hexafluoride purity, high energy consumption and high cost of the existing uranium purification conversion technology in the conversion technology of the high-impurity-content natural uranium concentrate, realizes cost reduction and efficiency improvement of uranium hexafluoride purification on the premise of ensuring that uranium hexafluoride reaches the nuclear purity grade standard, and has a wide application prospect. Rapid popularization of a dry uranium purification and conversion process is boosted, and the technical level of uranium purification and conversion in China is further improved.

A method for crystallizing, separating, and purifying uranyl nitrate hexahydrate comprises crystallizing uranyl nitrate hexahydrate crystals from a concentrated uranyl nitrate nitric acid solution, countercurrently washing the crystals, collecting the uranyl nitrate hexahydrate crystals into a collection container while squeezing washing liquid from a container into a washing area, and unloading the washed product. The uranyl nitrate hexahydrate crystals are crystallized from a feed stream under isothermal conditions, washed, and collected. The technical achievement simplifies the process flow, achieving high and independent recovery and product purity indicators. This method can be used in nuclear fuel cycle water metallurgy processes during the refining stage of natural uranium or recycled uranium.

The present invention relates to the field of nuclear technology, in particular to uranium-plutonium oxide nuclear fuel for nuclear power plants with thermal neutron reactors. The technical result of the present invention is the development of a REMIX-type fuel component that allows nuclear fissionable material recovered from spent nuclear fuel to enter the nuclear fuel cycle and simultaneously use enriched natural uranium, as well as ensuring that the problem of handling previously separated plutonium (including weapon-grade plutonium) is solved. By recycling the fissionable material in spent nuclear fuel during the life of a nuclear reactor, the amount of spent nuclear fuel is reduced (up to 5 times), natural uranium used for fuel manufacturing is saved, and thus the self-sufficiency of the nuclear fuel cycle is ensured. The present invention makes it possible to use REMIX-fuel to solve all the problems that may arise in a closed nuclear fuel cycle, while taking into account the number of reactors, the availability of natural uranium, and the accumulated amount of spent nuclear fuel.

A method for separating hydrogenated kerosene and TBP in a natural uranium extractant includes the following steps: First, at room temperature, take 20 mL of the uranium-containing mixed organic solvent to be treated and mix it thoroughly with 11–14.5 mol / L analytical grade phosphoric acid at a volume ratio of 1:1–1:2 for 5–10 min, with 1–5 separation stages, and allow the reaction to stand at 20–30°C. After standing, take the lower liquid phase, which is an H3PO4·nTBP solution, and the upper liquid phase is hydrogenated kerosene. At this point, the hydrogenated kerosene content in the upper liquid after separation can reach over 97%. Second, add 2–3 mol / L nitric acid aqueous solution to the obtained H3PO4·nTBP solution, with a two-phase flow ratio of 1:1–1:2 and 2–3 separation stages, allowing the reaction to stand at 20–30°C. Take the supernatant, which is the TBP product liquid, thus achieving separation. Third, prepare an extractant using the separated TBP and hydrogenated kerosene, and conduct a comparative experiment with fresh extractant.

The application discloses a kind of natural uranium supply to the evaluation method and equipment of long-term guarantee degree in nuclear power, belong to mineral resources guarantee technical field.The method takes primary uranium source and secondary uranium source joint supply as core analysis dimension, while giving consideration to quantity and quality, establishes evaluation index system, realizes the comprehensive quantitative analysis and prediction of the guarantee degree of natural uranium resources needed for nuclear power development by standardization evaluation process;The standardization evaluation process includes two evaluation processes of medium-term evaluation and long-term evaluation;The medium-term evaluation priority evaluation is the guarantee capacity of producing mine, and the long-term evaluation is based on the results of the medium-term evaluation Comprehensive evaluation is carried out by combining planned mine and potential mine.The present application can realize the quantitative evaluation of natural uranium supply guarantee for nuclear power, with high accuracy and strong operability.

The present invention belongs to the technical field of uranium purification and conversion, and specifically relates to a modeling method for a large-scale industrial-grade sieve plate uranyl nitrate stripping column. Input the parameters of the pulse sieve plate stripping column, which are divided into process operation parameters and structural parameters; establish a thermodynamic model of the uranyl nitrate stripping process, establish a pulse sieve plate stripping column hydraulic model, combine the thermodynamic model of the uranyl nitrate stripping process with the pulse sieve plate stripping column hydraulic model, and solve it using the Jung Kutta method; under the premise of the process operation parameters and structural parameters of the pulse sieve plate stripping column, calculate the uranyl nitrate concentration results at the outlet of the aqueous phase and the organic phase of the pulse sieve plate stripping column; verify the calculation results, obtain the final calculation results for the output that meets the requirements, and return to calculate again for those that do not meet the requirements. The present invention is suitable for simulating the natural uranium stripping process of the pulse sieve plate stripping column. The method has high accuracy, and the simulated data are all within the error range of 8% of the actual data.

The application provides a regeneration method of natural uranium extractant. In the regeneration method of the natural uranium extractant, the natural uranium extractant comprises tributyl phosphate and hydrogenated kerosene, and the regeneration method comprises the following steps which are sequentially performed: S1: washing the natural uranium extractant to be regenerated by using a sodium hydroxide solution, and then acidizing by using a nitric acid solution; S2: washing the natural uranium extractant after the washing and acidizing in step S1 by using a sodium carbonate solution, and then acidizing by using a nitric acid solution to obtain the regenerated natural uranium extractant. The regenerated natural uranium extractant obtained by the regeneration method has good selectivity and stability, and the reuse of the natural uranium extractant is realized.

The present invention belongs to the technical field of extraction and purification of natural uranium in the nuclear fuel cycle, and specifically relates to a simulation modeling method for a natural uranium extraction and purification system. The parameter types of the extraction and purification system are determined and divided into process operation parameters and pulse column structural parameters; the process operation parameters are used as input operating variables, and the pulse column structural parameters are used as fixed quantities; the mass transfer models of the extraction column, washing column, and stripping column in the extraction and purification system are respectively established using the unit differential method; the mass transfer models are dimensionless; the dimensionless mass transfer models are solved, and a thermodynamic model of the uranyl nitrate extraction and purification process and a hydraulic model of the pulse column are established. The thermodynamic model and the hydraulic model are combined, that is, the extraction reaction process and the structural characteristics of the pulse column used in the extraction reaction process are combined. This method can realistically simulate the operating results of the natural uranium extraction and purification process, and simulate and calculate the operating results under different two-phase flow ratios, concentrations, acidities, and temperatures.