In conjunction with the increasing demand for material cutting, such as the decommissioning and dismantling of nuclear facilities, advanced cutting technologies need be developed to increase precision and cost-effectiveness. As compared with other cutting technologies, laser cutting offers advantages of greater cutting precision, accuracy, and customization. In this work, we investigated the constitution, classification, and current status of this technology. Pollutant emission during laser cutting, corresponding pollution control methods and apparatus were proposed as well. Laser cutting equipment mainly comprises an automated system integrating a fiber laser, industrial computer, servo motor control, electrical control, and detection technology. It mainly consists of mechanical and electrical control parts. Laser cutting equipment is distinguished by light source, power, and cutting dimensions. Known variants of laser cutting technology involve vaporization, fusion, reactive fusion, and controlled fracture cutting. During the cutting process, dust, smoke, and aerosols can be released, which is an environmental concern and poses a threat to public health. The selection of the dedusting method and design of apparatus should take into account the dust removal rate, initial capital cost, maintenance cost, etc. Multi-stage filtration such as bag filtration combined with activated carbon filtration or electrostatic filtration is accepted.

The average share of nuclear energy in electricity production is expected to increase under the background of the global pursuit towards carbon neutrality. Conjugating with its rapid development, the wave of decommissioning and dismantling (D&D) of nuclear facilities is coming. The surface decontamination is a prerequisite to D&D, which will make it easier and reduce the volume of radioactive wastes. However, there are no comprehensive studies on the decontamination methods, which is not helpful for the sustainable development of nuclear energy and environment protection. Therefore, in this work, the current status and future trends of global energy and nuclear energy are first analyzed. Then, various decontamination approaches are comparatively studied, including cleaning mechanisms, application subjects, and intrinsic advantages and disadvantages. Finally, the criteria and factors for selecting a decontamination process, the challenges, and future studies are directed. Among the mechanical methods, laser-based cleaning is high-speed, having automation ability, and thus is promising, although it creates a dust and airborne contaminant hazard. In further studies, factors such as selecting a proper laser facility, optimizing operating parameters, and designing a high-efficiency dust collection system could be studied. Regarding the chemical method, chemical gels are good for decontaminating complex shapes and vertical and overhead surfaces. In addition, they can enhance other decon agents’ efficiency by improving contact time. However, the formulation of colloidal gels is complex and no gel type is useful for all contaminants. Therefore, novel and versatile gels need be developed to enlarge their application field. Combining various decontamination methods will often have better results and thus a reasonable and effective combination of these decontamination methods has become the main direction.

Background: To investigate the MicroRNA-146a targeting regulation of IL-6/STAT3 signaling pathway activity and influence the proliferation and apoptosis behavior-related mechanisms of OA chondrocytes. Material and Methods: 10 C57 mice were isolated and cultured with membrane protease and type II collagenase. The experiment was divided into blank group, MicroRNA-146a overexpression group and low expression group. The chondrocytes were transfected with plasmid vector. After 48 hours of culture, the proliferation rate of chondrocytes was detected by MTT method. The levels of type ii collagen, MMP-9, IL-1, IL-6, and TNF-α in culture medium were detected by ELISA. Luciferase reported experimental analysis of MircoRNA-146a targeting regulation of IL-6 genes. Results: Compared with the blank group, the proliferation rate of chondrocytes in the overexpression group was significantly decreased, the apoptosis rate was increased, the levels of IL-6 and p-STAT3 protein, type II collagen, MMP-9, IL-1, IL-6 and TNF-α were increased, while the low expression group was correlated (P < 0.05). Luciferase reporter experiments confirmed that MicroRNA-146a had a better binding effect with the IL-6 gene. Conclusion: MicroRNA-146a overexpression may mediate activation of IL-6/STAT3 signaling pathway and participate in decreased proliferation activity and increased apoptosis activity in OA chondrocytes. IL-6 gene may have targeted regulatory sites for MicroRNA-146a.

During the operation of a nuclear power plant, many main systems will generate variety of radioactive spent filter elements. These filter elements are main solid waste which need to be replaced regularly to keep safety of these systems. Because these filter elements have a certain level of radioactivity, the replacement operation has a higher risk. Therefore, according to the national and nuclear power plant radioactive waste regulations, it is necessary to ensure the safe and reliable operation of the radiation protection, make sure that operator and facilities are protected from radiation exposure or minimized. Based on the analysis of the filter element replacement process and equipment of domestic nuclear power units in service, combined with the requirements of newel construction of intelligent nuclear power plants, it is necessary to propose a radioactive spent filter element intelligent replacement ROBOT program. This paper discusses the design scheme of a new intelligent replacement robot for radioactive spent filter elements, and key issues involving fully automatic replacement technology for radioactive filter elements, such as filter layout and filter element replacement process optimization, robot grabbing actuator design, robot positioning mechanism design and accuracy guarantee, etc. have been systematically studied. A set of robot systems with intelligent replacement of radioactive irrationality have been developed. The test has been verified and the technical conditions for implementation in NPP have been met.

Based on the safety analysis, the risk of high temperature and radiation are found in the local operation during the automatic welding and vacuum drying of typical spent fuel dry storage system. To enhance the operational safety, a high temperature and radiation protection equipment has been developed through the structural design and numerical analysis and has been applied in demonstration project in China. It is proved by the local monitoring data that in the case of loading spent fuels with a total heat rate of 26kW, with the help of the protection equipment, the highest temperature of the operational area is 60% lower than the case without the equipment in the same environmental conditions. The dose rate in the area can also be 60% lower. The equipment is proved to be of significant help to ensure the safety of operators in high temperature and radiation environments, during both normal operation and equipment failure conditions.