Part of the waste residue generated during the development and utilization of rare earth resources belongs to the associated radioactive solid waste. The safe and effective disposal of this type of waste residue is an urgent problem that needs to be solved in the current development of the rare earth industry. By the method of investigation and analysis, based on the types and sources of rare earths, statistics were conducted on the types, yields and radioactive nuclide activity levels of waste generated during the mining and selection process. Combined with the development plan of the rare earth industry, the stock and increment of rare earth waste in typical provinces(autonomous regions) were preliminarily estimated. And the current status and existing problems of the treatment and disposal of rare earth associated radioactive waste residue were sorted out. On this basis, a strategy for regional landfill disposal is proposed: it is recommended to implement a 7+x model nationwide, and to build rare earth waste residue warehouses in major rare earth provinces(autonomous regions), with reference to the model of Baotou in Inner Mongolia, to collect and dispose of rare earth associated radioactive waste residues in the provinces(autonomous regions). Based on the estimated amount and increment of waste residues, suggestions for the scale of rare earth waste residue disposal in each province(autonomous region) are provided.

Radioactive decontamination is an important technical means to ensure the sustainable development of nuclear industry. Radioactive decontamination is not only related to the comprehensive cost of operating and managing facilities such as nuclear power plants, and the development of radioactive mineral resources, but also related to personnel safety and social environmental safety, and should be given sufficient attention. On the basis of summarizing various radioactive decontamination technologies commonly used in the process of decommissioning and maintenance of domestic nuclear facilities, the application conditions, advantages and disadvantages of physical decontamination, chemical decontamination, electro oxidation decontamination, microbial decontamination and smelting decontamination technologies are analyzed, and the technical pain points and development direction of decontamination technology is proposed.

In addressing the adsorption issue of low-concentration uranium in nitric acid systems, a chloromethylated styrene-divinylbenzene copolymer was employed as the framework, and phosphorylation was achieved using phosphorus trichloride as the functionalizing reagent. Through Friedel-Crafts alkylation and quenching-hydrolysis/alcoholysis reactions, long-chain hydroxyl and alkyl groups were grafted onto the resin, resulting in uranium adsorbents featuring phosphoric acid and phosphoric ester functional groups, respectively. The resin structural characterization was conducted using infrared spectroscopy, elemental analysis, and thermogravimetric analysis. During the resin preparation, the impact of different process parameters on the phosphorus content and uranium adsorption performance was investigated, leading to the determination of optimal synthesis conditions. Static experiments were performed to assess the influence of pH, equilibrium uranium concentration, and adsorption time on the uranium adsorption properties of the resin. Additionally, a selection of desorption agents and verification of resin reusability were carried out. The results indicate that the prepared phosphoric ester-based uranium adsorbent exhibits excellent adsorption performance for low-concentration uranium (<20 mg/L) in a simulated solution (1 mol/L HNO₃+1 mol/L NaNO₃). The resin saturation adsorption capacity for uranium is 21.9 mg/g dry resin, and the residual uranium concentration in the leachate after adsorption is <0.05 mg/L. Using 0.4 mol/L NaHCO₃ and 0.1 mol/L Na₂CO₃ as composite desorption agents, the desorption efficiency for uranium reaches 98.3%. The synthesized phosphoric ester-based uranium adsorbent proves effective for the adsorption and separation of low-concentration uranium in nitric acid systems.

The ore grade of the Rossing Uranium Mine in Namibia is low and the processing capacity is large. The mined ore is mixed with some waste rocks, and the grinding and leaching costs are high. To solve this problem, the distribution patterns of ore particle size and uranium grade were studied, the radioactivity visibility of representative ore samples was calculated, the radioactive selectivity curve was drawn, and the theoretical sorting index based on the cut-off grade was determined. The theoretical sorting indicators are: when the cut-off grade is 0.01%, the raw ore uranium grade is 0.032%, the concentrate uranium grade is 0.047%, the tailings yield is 33.95%, the tailings uranium grade is 0.002 8%, and the total recovery rate is 96.37%. The results show that radioactive beneficiation has a certain effect and the ore selectivity is high. It is mainly suitable for tailing of coarse-grained and extremely low-grade ores. The radioactivity visibility can be used as the theoretical basis for radioactive beneficiation of Rossing Uranium Mine.

Fengcheng paigeite deposit is a large scale multi-metal deposit containing boron, iron and uranium, which is developed by open-pit mining, following by beneficiation (gravity separation, magnetic separation, and flotation) and hydrometallurgical treatment to obtain iron concentrate, sodium borate, and diuranate as products. In this process, several kinds of solid waste are produced such as mining waste rock, beneficiation tailing, and leached uranium tailing. Through detailed investigation of the radioactive characteristics of product and solid waste in the full process, it is indicated that iron concentrate and sodium borate meet their radioactivity quality standard. Mining waste rocks, beneficiation tailing, gravel and coarse sand produced by crushing of ore, and boron mud can be treated and disposed as ordinary solid waste other than radioactive waste. Gravel and coarse sand can be used as building materials. Boron mud is used to produce sub-nanomater silica stone without any limitation related to radioactivity, in case of the boron mud addition not exceeding 50%. Leached uranium tailing should be disposed as extremely low level radioactive waste.

The high rates of submersible pump damage due to pump shaft fracture and pump body corrosion have been studied. By conducting theoretical calculations and ANSYS numerical simulations, the mechanical properties such as strength and stiffness of hexagonal and cylindrical shaft structures were compared. Field comparison tests on the corrosion resistance of 304, 316L, and 904 stainless steel materials were also carried out. The results indicate that under the same load and equivalent diameter conditions, the shear stress on the cross-section of the cylindrical axis is 64.95% of the hexagonal axis, and the torsion angle is only 56.25% of the hexagonal axis torsion angle; the simulation results show that the maximum circumferential deformation of the cylindrical shaft coupling is 68.4% of the maximum circumferential deformation of the hexagonal prism shaft, the cylindrical shaft structure exhibits better torsional performance. While 904 stainless steel has the best corrosion resistance, both 304 and 316L stainless steels demonstrate similar corrosion resistance to acidic media. Considering corrosion resistance margins and manufacturing costs, it is recommended to use a cylindrical pump shaft structure and continue using 316L stainless steel as the main material in the development of submersible pumps for uranium mining.

This paper summarized the sedimentary facies types and characteristics of the Upper Cretaceous Yaojia Formation in Baiquan area, Songliao Basin. It is considered that the Yaojia Formation in Baiquan area can be divided into upper and lower members. The upper member of Yaojia Formation has meander river facies and delta facies, while the lower member has braided river facies and delta facies, and further be divided into 6 subfacies and 10 sedimentary microfacies. The braided river facies sand body of the lower member of Yaojia Formation has large thickness, good uranium anomaly has been found, which has good uranium metallogenic potential, and is a favorable area for uranium prospecting in the future.

A certain deposit encountered a certain degree of water inflow during the mining process. In order to solve the water inflow problem and provide a basis for water prevention and control plan, the deposit was taken as the research object, the hydrogeological conditions of the deposit were generalized by analyzing the hydrogeological conditions, types and characteristics of aquifers, groundwater recharge and discharge conditions, geological structural characteristics, hydrogeological parameters, hydrogeological test data, and mining design data. The hydrogeological units of the study area were delineated, and a three-dimensional groundwater flow numerical model was established using GMS software, the predicted water inflow of the mining pit in the middle section below -200 m was obtained.

A method for determining uranium content in natural uranium products (U₃O₈) by wavelength dispersive X-ray fluorescence spectrometry was established using solution sample preparation and strontium carbonate as the internal standard. The method determines that the weight of the sample is 1.00 g, and the weight of the internal standard strontium carbonate is 0.600 g. The sample is digested with 15 mL of phosphoric acid and 2 mL of nitric acid to a constant volume of 200 mL. After stirring with magnetic force, the volume of the solution is controlled using a disposable plastic pipette and an electronic scale. Instrument measurement conditions selection feature X-ray line: U-L_α1,Sr-K_α1, channel mask 34 mm, primary collimator 150 μm. The linear correlation coefficient of the working curve of the method is 0.999 8, and the relative standard deviation (RSD) is between 0.031% and 0.050%, indicating good precision; The relative error between the measurement results and the recommended value of the reference material is not less than 0.034%, with good accuracy. Compared with the potentiometric titration method, the absolute deviation of this method is between 0.010% and 0.126%, and the results are accurate and reliable, meeting the requirements for rapid batch analysis of natural uranium products.

The electromagnetic radiation environment of 750 kV single cycle parallel transmission line was calculated and predicted by adopting the calculation model recommended by Appendix C and D of Technical Guidelines for Environmental Impact Assessment of Electric power Transmission and Distribution (HJ 24—2020). The results show that when the minimum height to ground of the conductor passing through farmland, garden land, pasture land, livestock and poultry breeding land, roads and other places is 15.5 m, the maximum value of the power frequency electric field intensity under the single cycle parallel line is more than 10 kV/m, the minimum height to ground of the conductor needs to be elevated to 16.5 m to satisfy the limit requirement of 4 kV/m. The power frequency magnetic field generated by the 750 kV single cycle parallel transmission line is less than the public exposure control limit(100 μT), which generally will not be an environmental constraint for the construction of the line, however, the power frequency electric field generated by the line is the main factor of the electromagnetic environmental impact, and the control limit of the power frequency electric field strength(4 kV/m) is an environmental constraint for the construction of the line, and it is also a key control factor for the electromagnetic environment of the transmission and transformation power. The field measurement results and the theoretical prediction results are in good conformity, indicating that the prediction model used has good applicability, and the results of the study can provide technical support for the construction and environmental supervision of 750 kV single cycle parallel transmission lines.