The special material handling system of the uranium enrichment factory was systematicly analyzed, the characteristics of special materials were analyzed in detail, the handling lines and logistics conditions were defined, the influencing factors and practical handling methods were distinguished, and a viable overall scheme of the special material handling was obtained. The economic and intangible factors of the handling scheme were analyzed and evaluated. The SHA provides theoretical supports for improving the special material handling, and provides a logical handling scheme for the rebuilding and expanding plan. It improves the handling efficiency and reduces the labor intensity. It also provides a certain reference for reducing the production cost.

In view of the problems such as imperfect waste water treatment process, low automation level and unstable process parameter commissioning in a uranium mine, Siemens 1500 series PLC is used as the control system, the control process includes automatic alkali dispensing, acid dispensing, lime over alkali neutralization, PID automatic pH adjustment, automatic wastewater discharge and other functions. The pH callback adopts the segmented gain method, which makes the waste water callback process is faster and more anti-interference. WinCC 7.4 is used as the upper system for remote monitoring and control. The control system, relying on advanced network technology and automation technology, realizes the functions of automatic data collection, online monitoring alarm, automatic parameter adjustment, automatic control of the actuator, etc., realizes unattended wastewater treatment process, and ensures continuous, safe and stable operation of uranium mine waste water treatment process.

In order to continuously improve the scientific research and management level, promote the standardization level of the in-situ leaching uranium industry, and more scientifically and effectively develop and build in-situ leaching uranium mines, the application status and the problems in the application of the relevant standards and technical regulations for in-situ leaching uranium mining in China are emphatically sorted out, analyzed, summarized, and the technical standard system table for in-situ leaching uranium mining is compiled.

The fluoride removal performance of GW-F90 resin was studied through static and dynamic tests, and the effects of adsorption time, initial fluoride concentration, pH and impurity ions on the fluoride removal performance of the resin were investigated. The influence of different desorbers on the desorption performance of the resin was investigated, and the mechanism of fluoride removal of the resin was determined. The research shows that the dynamic adsorption capacity of GW-F90 resin is 75.3 mg/g, the fluoride removal rate of the resin single adsorption can reach 92.7%, and the desorption rate is 98.7% when 10% sodium hydroxide solution is used to desorb the resin. GW-F90 resin has good selectivity and fluoride removal performance, and can effectively remove fluoride from fluoride-containing water.

Aiming at the problems of high turbidity and organic phase content in the uranium-molybdenum raffinate, which affect the return utilization, the experimental study on the removal of organic phase in the raffinate by flocculation pretreatment was carried out. The results show that the turbidity and organic phase contents in the raffinate can be reduced from 1 500 NTU and 294 mg/L to 0 NTU and 44.8 mg/L respectively under the conditions that the dosage of C6140 is 2.0 g/m³ raffinate, stirring speed is 60 r/min, stirring time is 10 s, and static time is 40 min after stirring. The process parameters obtained from the study have strong adaptability to the change of turbidity of raffinate, and the flocculation pretreatment process parameters can be used in production.

In order to optimize the radiation shielding of natural uranium repository, taking the design limit of the external dose rate of the shielding of natural uranium repository as the reference control objective, and on the basis of analyzing the accuracy of existing shielding calculation methods, Microshield software is used to optimize the radiation shielding calculation method of natural uranium repository, especially the source term model. This method is based on the single storage barrel source model, the influence of uranium daughter and the superposition of several storage barrels is mainly considered. The calculation results are close to the actual monitoring results, and the calculation method is reliable, which can provide effective support for the radiation shielding design scheme of natural uranium repository.

According to the requirements of safety monitoring in the decommissioning of uranium tailings pond, the first dam of a uranium tailings pond is taken as a pilot project. By deploying Beidou displacement monitoring terminals and various sensors at key points such as the surface of uranium tailings dam and the reservoir area, the real-time monitoring of the tailings pond and the prediction and early warning of the trend of surface deformation, the settlement trend of the dam and the variation trend of water level in the reservoir are realized, so as to predict the stability of the dam in advance and master the safety of the dam. Under the guidance of the intelligent monitoring and prevention system, a comprehensive monitoring platform is developed to provide advanced technical means for the decommissioning and management of the uranium tailings pond in the uranium industry, thus transforming passive “supervision” into active “monitoring”. The research results can provide reference for safety monitoring and intelligent prevention of other uranium tailings ponds.

Long-term monitoring and maintenance of decommissioned uranium mining and metallurgy facilities is an important insurance for regional environment and public health. Taking the decommissioned facilities during and before 12th Five-Year Plan which under long-term monitoring and maintenance as study subjects, the method, process, guarantee condition of monitoring and maintenance, as well as the radiation safety situation of the facilities were investigated. Based on the study and investigation, the problems in long-term monitoring and maintenance were analyzed, and rationalized suggestions for process improvement were proposed.

It is difficult to treat radioactive wastewater by increasing the area of evaporation pool alone when using natural evaporation process. Taking the concentrated water of electrodialysis and the wastewater of evaporation pond in a neutral in-situ leaching uranium mine as the research object, MVR evaporation process was used to investigate the quality of condensate water and evaporation effect under different pressures and temperatures. The results show that the condensate water can meet discharge or reuse standards, the volume reduction rate reaches 95%, and the MVR has the best evaporation effect at 0.07 MPa and 90 ℃.

The special acceptance is based on the archive, the archive acceptance of uranium mining and metallurgy research project is an important link in the project acceptance. In view of the problems existing in the archive acceptance of research project, the existing problems and their causes from the perspectives of integrity, accuracy, systematization, standardization and security were analyzed, and some reasonable suggestions to solve the related problems were put forward.