This article briefly discusses the pivotal role of the basic standards for radiological protection in promoting the development of radiological protection related disciplines. Radiological protection system outlined in the recommendations published by the International Commission on Radiological Protection (ICRP), which provide basis for developing radiological protection standards, has undergone four generations of evolution; And the International Basic Safety Standards(IBSS), jointly developed by the International Atomic Energy Agency(IAEA) and multiple international organizations, has completed three generations of evolution. This paper focuses on the main characteristics of the four generations of evolution of basic standards for radiological protection in China, including 1960, 1974, 1980s and 2002. Based on the more than 8 years experience in joint development of the fourth generation basic standard GB 18871—2002, valuable lessons need to be sorted out; It will be beneficial to continuously update the basic standards of radiological protection and develop the discipline of radiological protection. As a participant in the development of China’s third and fourth generation basic standards, I would like to put forward six suggestions for updating the standards and promoting the fifth generation basic standards to meet the urgent needs of related development in China. Obviously, it is imperative to develop new basic standards that are scientifically sound, easy to implement, and able to solve practical problems in a targeted manner, based on national conditions and international standards.

Controlling of effluent discharge is a major aspect of environmental radiation protection in nuclear power plants (NPP). The national standard GB 6249—2011 set the discharge limits for a single unit with thermal power 3 000 MWt and clarified that the discharge control values for other power reactors should be appropriately adjusted. Currently, various types of reactors, technologies, standards, and multiple countries import coexist in China, resulting in a significant difference in the thermal power of nuclear power units. How to determine their discharge limits has become a focus for the environmental radiation protection management of NPPs. This paper collects data on the design and approval of effluent discharge in domestic nuclear power plants, as well as domestic and foreign data on effluent discharge, design power, and electricity generation, and conducts the correlation analysis. This paper proposes methods and suggestions for adjusting the discharge control values according to unit power, providing a reference for the standardized management of effluent discharge for NPPs.

Traditional solid detectors such as scintillators and semiconductors are difficult to meet the future requirements for flexible radiation detection applications. Therefore, in this paper, a new technology route is proposed based on novel perovskite materials. The perovskite solution is filled into the flexible matrix of porous nylon film, and the flexible detection materials are prepared through recrystallization. Scanning electron microscopy imaging, X-ray diffraction, ultraviolet absorption spectroscopy, and tests such as μτ value, dose rate linearity, and detection sensitivity under X-ray irradiation are conducted on six prepared materials. The six materials are optimized and further X-ray and γ-ray tests are carried out. The results show that the μτ value of [NH₃(CH₂)₄NH₃]BiI₅ flexible film material is 1.30×10^-3 cm²·V^-1; the optical band gap is 2.02 eV: and the detection sensitivity is (3 190±50)μC·Gy_air^-1·cm^-2, which is superior to existing semiconductor detectors and retains the inherent excellent detection characteristics of perovskite crystal materials. This paper lays an important foundation for the subsequent research and development of flexible radiation detectors and detection systems.

In coded aperture imaging systems, the field of view (FOV) is conventionally determined by the geometric relationship between the coded aperture mask and the position-sensitive detector. However, the influence mechanism of critical physical parameters—including the thickness and material properties of both the mask and detector, as well as the radiation energy—on the fully coded field of view (FCFOV) has not been systematically investigated. This study employs a controlled-variable approach to systematically elucidate the relationship among these parameters (mask thickness/material, detector thickness/material, and energy) and the FCFOV. By introducing the concept of equivalent thickness to revise the conventional geometric model (which relies solely on mask-detector distance), we propose an empirical parameterized formula for FCFOV calculation, representing the first such model of its kind internationally. Both simulations and experimental results validate the effectiveness of the formula, demonstrating its superior accuracy in defining the FCFOV boundaries compared to traditional methods. These research findings provide a important reference for future FOV calibration and system design in coded aperture imaging applications.

I-129 is a typical emission nuclide in the gaseous effluent of spent fuel reprocessing, which will produce certain radiation hazards to the environment and human body. Therefore I-129 needs to be monitored. Until now online monitoring of I-129 in the gaseous effluent of spent fuel reprocessing plant is still vacant in China. Based on the existing aerosol online monitoring system, this paper designs an aerosol conversion device to solve the sampling problem of the aerosol online monitoring system, and provides a pre-sampling device and method for the online monitoring of gaseous I-129 in the gaseous effluent of the reprocessing plant by the subsequent linkage aerosol online monitoring technology. The aerosol conversion experiment was carried out by stable iodine instead of I-129, and the conversion efficiency of the device was measured under different conditions. Combined with the performance parameters of ICP-MS, the conversion efficiency of the aerosol conversion device and the loss rate of aerosol during the online monitoring process, the low detection limit range of the aerosol conversion device for the online monitoring of I-129 in gaseous effluent was preliminarily derived, which was compared with that of the international continuous monitoring low detection limit requirements. The preliminary low detection limit range of the aerosol conversion device for online monitoring of I-129 in gaseous effluent was compared with the international continuous monitoring low detection limit requirements, which verified the feasibility of the method and the better prospect and research value in the field of online monitoring of I-129 in reprocessed gaseous effluent.

In view of the existing problems between personal dose management system and supporting equipment in nuclear power plant, such as system isolation, data unable to interact, transformation difficulties and technical support lag, the communication interface between personal dose management system and dosimeter reader was studied. Based on the developed domestic personal dose management system software and dosimeter supporting readers as well as dosimeters, the communication interface between the system and supporting equipment is studied by using WebService communication technology, so as to complete the interaction of dosimeter reader information, dosimeter information, personnel information, radiation work permit (RWP) information and access control area records, and to realize the personnel dose management and access control in nuclear power plant. The performance test results show that the average time of system interface call is 348.8 ms, which ensures the efficiency of personnel entering the control area and further improves the intelligent management of power plant.

Tobacco leaves contain various natural radioactive nuclides, smoking may increase internal radiation dose to the human body. This paper analyzed the ²¹⁰Po levels in 36 domestic cigarette brands and 4 foreign cigarette brands. The analysis results showed that the ²¹⁰Po content in domestic cigarettes ranged from 22.3 to 48.6 mBq/g (or 13.1 to 29.9 mBq per cigarette), with an average of 32.9 mBq/g (or 20.2 mBq per cigarette); while in foreign cigarettes, ²¹⁰Po content ranged from 18.5 to 24.3 mBq/g (or 11.1 to 12.7 mBq per cigarette), with an average of 21.2 mBq/g (or 12.1 mBq per cigarette). Overall, the ²¹⁰Po content in domestic cigarettes was slightly higher than that in foreign cigarettes. Based on the ²¹⁰Po content in tobacco shreds, it was estimated that the amount of ²¹⁰Po inhaled by Chinese smokers from cigarettes was approximately from 24.85 to 150.29 mBq per day, and the internal radiation equivalent dose to the lung tissue was from 27.48 to 166.22 μSv per year.

The beam quality of Boron Neutron Capture Therapy (BNCT) is a crucial factor affecting its therapeutic efficacy. In recent years, multi-imaging plate systems have attracted increasing attention for measuring BNCT beam parameters. In such systems, the thickness of the conversion layers plays a key role in determining measurement accuracy. This study applies a particle swarm optimization algorithm to optimize the conversion layer thicknesses. A Monte Carlo simulation is used to calculate the system’s response matrix at each step of iteration. The condition number of the response matrix is chosen as the optimization objective. Through iterative computations, the optimal thickness values are obtained. Based on these results, a physical interpretation is further provided, focusing on the range of secondary charged particles and the enhancement effects of the conversion layers on each imaging plate. The research findings offer important reference data for the development of multi-imaging plate detectors for BNCT beam characterization.

When nuclear power plants experience severe accidents triggered by external event or catastrophic natural disasters beyond design basis accident, there is a need for off-site emergency response forces to provide support. The mutual support among nuclear power groups serves as an important backup force. Based on the analysis of the emergency response capabilities layout among domestic nuclear power groups and drawing from the practices of international support for nuclear accident emergency in other countries, this paper identifies current issues in inter-group emergency support for nuclear accident. This paper also explores comprehensive considerations necessary for implementing mutual support among groups, coordination and cooperation with national-level nuclear emergency support forces, and requirements for routine maintenance of the support mechanism. Relevant suggestions are proposed.

Although domestic nuclear power plants (NPPs) have established on Duty Emergency Response Organization (DERO) in accordance with relevant standards and guidelines, the guidelines usually have not specified the requirements for the minimum-DERO in detail, resulting many differences in the configuration and scale of the minimum-DERO among different NPPs. Through investigating of the current situation of DEROs in NPPs, based on the results of classification analysis and evaluation of typical accidents, the dynamic understanding of the minimum DERO at different stages has been deepened. The requirements for the minimum DERO personnel are determined according to three categories of personnel, namely “on-duty” “time-limited” and “others”. The duty arrangements, examination and verification, logistics support and optimization methods of the minimum DERO have been analyzed. A general formulation method and process for the minimum DERO have been established. The setting principles, positions and personnel composition of the minimum DERO for dual-unit plant sites have been proposed. The quantitative criteria for the general minimum DERO and suggestions for the minimum DERO for dual-unit plant sites have been provided, which has provided a technical reference for NPPs to formulate nuclear emergency plans.

This article analyzes the current status, hotspots and trends of research on nuclear and radiological events among nursing staff. By retrieving the literature related to the research of nursing staff in the field of nuclear and radiation in the core set of the Web of Science database, the Citespace software is used to conduct a visual representation analysis of the literature. The results show that a total of 262 documents were obtained, and the number of published papers is on the rise. Country with the highest number of published papers is Japan (66), and country with the highest centrality is the United States (0.27). Institution with the highest number of published articles is Fukushima Prefectural Medical University (26 articles), while institution with the highest centrality is Harvard University (0.11). Keyword analysis shows that the research hotspots of nursing staff in nuclear and radiological events mainly focus on public health after radiation exposure, the prevention and emergency preparedness status of nursing staff for nuclear and radiation disasters, and radiation protection. Emergency preparedness and management for disaster prevention is the research trend for future nursing staff in the fields of nuclear and radiation. Future research should enhance academic exchange and cooperation among scholars and research institutions at home and abroad, focusing on solving existing problems and developing new radiation care technologies, with the aim to further promote the development of nursing personnel in the fields of nuclear and radiation and to provide reference for later research.

Radiation pneumonia, as a common and severe complication as well as a dose-limiting factor in radiotherapy for thoracic tumors, has an incidence rate ranging from 10% to 30%. Once RP occurs, it can cause irreversible changes in lung function, resulting in the interruption or cessation of radiotherapy and serious clinical consequences. Currently, there is a lack of effective prevention and treatment methods. A vast number of microbial communities coexist in the human body. Due to the anatomical connection between the oral cavity, lungs, and intestines, and the interconnection between the mucosal immune systems of the intestinal and pulmonary tracts, the oral and intestinal microbiota not only affect the oral cavity and intestines themselves, but also can indirectly affect the course of lung diseases through their own or metabolic products via the bloodstream or directly through body cavity transplantation. Based on the interaction and influence of the oral and intestinal microbiota on lung diseases, this paper proposes the crucial role of the “oral—intestinal—pulmonary axis” in the occurrence and development of RP. By regulating the balance of the oral and intestinal microbiota, this paper offers a new strategy for the clinical prevention and treatment of RP, and simultaneously provides evidence-based medical evidence for strengthening the popularization of scientific knowledge to enhance patients′ awareness of maintaining good oral and intestinal microbiota health.