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Design optimization and effect analysis for radiation protection in Haiyang nuclear power plant GOU Quanlu, WANG Caixia, ZHANG Jiannian, WAN Dengwei, YU Xiaodong, WANG Yilin RADIATION PROTECTION    2023, 43 (6): 620-627.   Abstract （120）      PDF（pc） （2026KB）（42）       Knowledge map    Save Both units of Haiyang Nuclear Power Plant(NPP)Phase I have been equipped with AP1000 technology designed by Westinghouse of the United States. The radiation protection design was based on the priority of using advanced and mature technology. In order to reduce the radiation level of reactor unit and the occupational exposure dose to the staff, a lot of optimization design technology have been used: such as adopting the passive safety system to reduce the amount of equipment; integrated top head design of reactor pressure vessel; the maintenance-free main shield pump; steam generator primary circuit water chamber which adopted electrolytic polishing technology; spent fuel transport channel using of blocking water sac to improve equipment reliability; in order to reduce the maintenance workload. The main optimization measures adopted in the radiation protection design and the protection effect obtained by these measures were introduced, through comparison and analysis with typical data of domestic operating nuclear power plants. These measures can be used for reference for the optimization of radiation protection design in subsequent Phases of Haiyang NPP project, as well as for other peers. Reference | Related Articles | Metrics

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Expert consensus on occupational health surveillance of radiation workers Nuclear Emergency Medicine Branch of the Chinese Nuclear Society; Chinese Society of Radiological Medicine and Protection, Chinese Medical Association; Radiological Health Professional Committee of Chinese Preventive Medicine Association; Nuclear and Radiation Emergency Response Branch of the Chinese Society of Radiation Protection RADIATION PROTECTION    2024, 44 (2): 101-109.   Abstract （100）      PDF（pc） （979KB）（138）       Knowledge map    Save This paper describes the expert consensus on occupational health surveillance of radiation workers from various perspectives, including the changes in the understanding of health surveillance by international organizations, the establishment of relevant regulations and technical standards for occupational health surveillance of radiation workers in China, the establishment of examination items and period, the indications of inability to engage in radiological work, the definition of suspected radiological injuries, as well as the understanding of the standardization of medical examination methods, assessment of suitability, handling of special cases, and the management of health surveillance files. The Chinese Expert Consensus on Occupational Health Surveillance of Radiation Workers and the future outlook of the program are presented, aiming to provide guidance for the practice of radiation workers’ health surveillance in China. Reference | Related Articles | Metrics

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Study on air kerma measurement and conversion coefficient from air kerma to dose equivalent for 250-500 kV X-ray narrow spectrum QU Bingbing, ZHAO Rui, WU Jinjie, LU Pingzhou, LI Mengyu, LI Ting, MA Yingjie RADIATION PROTECTION    2024, 44 (1): 19-26.   Abstract （99）      PDF（pc） （2555KB）（101）       Knowledge map    Save Accurate measurement of radiation dosimeter is an important guarantee for conducting radiation protection. According to the operational quantities in ICRU report, it is necessary to verify or calibrate it in the reference radiation field. Referring to the ISO 4037-1:2019, the narrow spectrum X-ray reference radiation quality in (250-500) kV was established, and the uniformity of the radiation field and the spectrum were studied. The spectrum and half value layer parameters of radiation quality were obtained by Monte Carlo simulation and experimental measurement, and were compared with the ISO recommended values. These results meet the requirements of the relevant specification, indicating that the new radiation quality is accurate and reliable. The A5 ionization chamber is used to measure the air kerma in the new radiation field. According to the conversion coefficient of the air kerma to dose equivalent calculated by the X-ray energy spectrum, the conversion of the air kerma to the ambient dose equivalent and the individual dose equivalent is realized, which provides the measurement conditions for the energy response evaluation of various radiation dose meters in the high-energy region, and ensures the accuracy and reliability of the measurement value. Reference | Related Articles | Metrics

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Calculation of internal exposure dose coefficients for Chinese adult reference phantom YAN Shuchang, QIU Rui, WU Zhen, LUO Xiyu, ZHANG Hui, LI Junli RADIATION PROTECTION    2024, 44 (4): 323-335.   Abstract （96）      PDF（pc） （11091KB）（126）       Knowledge map    Save In the fields of nuclear science and technology, nuclear energy and nuclear medicine, accurate assessment of internal exposure dose received by relevant public, professionals, and patients is an important guarantee for personnel health and safety during work, nuclear accidents, and radiation therapy. Referencing the ICRP biokinetic model and radionuclide information, the internal dose coefficient is obtained by calculating the Specific Absorbed Fraction (SAF). The correctness of the calculation method is verified using the ICRP reference human phantom. Finally, based on Chinese adult reference human phantom, a database of internal radiation dose coefficients for Chinese adult reference human is calculated. The database obtained includes the Specific Absorbed Fraction (SAF) of α, β, and γ rays for Chinese adult reference human, the committed equivalent dose coefficients for sensitive organs (tissues) of Chinese adult reference human, and the committed effective dose coefficients for Chinese adult reference human. The calculated results were compared and analyzed with the internal dose conversion coefficients provided by GB 18871—2002. It was found that using the internal radiation dose conversion coefficient database of Chinese adult reference human can more accurately assess the internal dose caused by the intake of radioactive nuclides by Chinese adults. Reference | Related Articles | Metrics

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Research progress on radon migration and coverage control ZHAO Yong, ZHANG Guifeng RADIATION PROTECTION    2024, 44 (1): 1-9.   Abstract （91）      PDF（pc） （962KB）（112）       Knowledge map    Save With the development of nuclear power, the demand for natural uranium has increased. It has become evident that large volume accumulation of tailing on the ground may cause radon pollution. Therefore it is of great significance on how to effectively reduce the amount of radon exhalation from uranium tailing. Generally, the covering method after ground accumulation is used to reduce the ground environmental hazards caused by uranium tailing. The process of radon migration mainly undergoes two stages of migration in the covered material and the covering material. As a result, studying radon migration law has become a key component in solving the problem. In this paper, foreign and domestic scholars' studies on the factors influencing radon exhalation, radon migration theory, coverage control method and effect, and coverage parameters are summarized and reviewed. The following results are obtained: At present, the exhalation mechanism and influencing factors of radon are presented as comprehensive analysis. But there is a need for further research on the multi-factor coupling mechanism and action process during radon exhalation. Natural and artificially synthesized materials are selected as covering materials, the Natural materials are currently commonly used, in which the addition of bentonite in red soil, sandy sub-clay, and red soil are the good material for radon reduction. However, more research is needed to find covering materials that are effective in controlling radon and have minimal impact on the ecological environment. This paper provides ideas for more effectively eliminating radon pollution from uranium tailing in the future. Reference | Related Articles | Metrics

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Expert consensus on radiation biodosimetry by semi-automatic analysis of dicentric chromosome Nuclear Emergency Medicine Branch of Chinese Nuclear Society, Chinese Society of Radiological Medicine and Protection of Chinese Medical Association, Radiological Health Professional Committee of Chinese Preventive Medicine Association, Nuclear and Radiation Emergency Response Branch of China Society of Radiation Protection RADIATION PROTECTION    2024, 44 (3): 199-209.   Abstract （88）      PDF（pc） （2111KB）（55）       Knowledge map    Save Over the past ten years, semi-automatic analysis of dicentric chromosome (dic) has been widely used for estimating radiation biological dose internationally due to its technical maturity. However, there are still no relevant technical specifications and standards in China, although both technical reports published by the IAEA and technical standards published by the International Organization for Standardization have recommended this method for dose estimation. The present technical consensus of biological dose estimation was established from the aspects of the dic semi-automatic analysis principle, main technical content, factor analysis, and application examples, based on more than 30 years of practical experience for dic manual and semi-automatic analysis at home and abroad. Compared with the existing national standard GB/T 28236, it could significantly improve the efficiency of biological dose estimation, and could also reduce the requirements for technical proficiency of professionals, thus could be better promoted and applied. Similar to manual analysis, dic semi-automatic analysis could be used to estimate and reconstruct the exposed dose under different radiation exposure scenarios including acute uniform, local, extensional irradiation, and delayed sampling. Considering the inefficiency of current domestic dose estimation which cannot meet the needs of clinical classification and diagnosis for large-scale nuclear and radiation accidents that have a large number of exposed people, the promotion and application of dic semi-automatic analysis might solve these bottleneck problems and provide technical support for further development of relevant national standard. Reference | Related Articles | Metrics

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Study on radiation field measurement technique by utilizing total station positioning ZHAO Yuan, LIU Liye, LI Hua, LIU Xuegang, CHENG Jinfeng, WANG Xiaolong, LONG Zeyu, LI Hui, CHEN Ling RADIATION PROTECTION    2024, 44 (4): 336-342.   Abstract （88）      PDF（pc） （8453KB）（71）       Knowledge map    Save During the maintenance or decommisioning of nuclear facilities, it is often necessary to measure the radiation dose rate field on site. Traditional dose rate meters do not support spatial coordinate measurement and require additional coordinate measurement tools. Additionally, dose rate measurement and coordinate measurement are not synchronized, which limits measurement efficiency. A measurement method based on total station positioning was proposed, which can simultaneously measure dose rates and corresponding spatial coordinates with a positioning accuracy of mm level. A prototype measurement system was developed. The prototype was used to conduct testing experiments on a cement solidified radioactive waste container, and the outcomes were compared against Monte Carlo calculations. The discrepancy between the measured and simulated values conforms to a normal distribution, with an average deviation of 12.8% and a standard deviation of 9.37%. The relative deviation of approximately 96% of the measurement points is within the range of [-30%, 5%], reflecting high measurement accuracy. Radiation field assessments were also conducted in two other intricate settings within a nuclear facility structure. The interpolation of radiation fields at discrete measurement points was performed using the logarithmic transformation ordinary Kriging method. When measurement points were appropriately chosen, the average relative deviation in the three-dimensional radiation field reconstruction results could be maintained at approximately 50%. The results indicate that the radiation field measurement system based on total station can reconstruct the 3D radiation field on site, and the accuracy can meet the application requirements. Reference | Related Articles | Metrics

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Preliminary analysis on area ambient electromagnetic fields in part of Beijing by vehicle survey XU Hui, TONG Jing, LI Fei, WANG Guan, LI Miao, KANG Xiaohan RADIATION PROTECTION    2024, 44 (4): 356-366.   Abstract （88）      PDF（pc） （16458KB）（72）       Knowledge map    Save The electromagnetic fields ranging from 0.1 MHz to 6 GHz were measured by vehicle survey within the area of 800 km2 in Beijing, in order to promote the monitoring and evaluation of area ambient electromagnetic quality. The vehicle survey gathered 900,000 values including global electric fields of total frequency bands, Radio Frequency and long, medium, and short waves, as well as selective electric fields of total base stations and 5G base stations. Mass data were analyzed by SPSS and ArcGIS to understand general ambient electromagnetic quality level, spatial and temporal distribution pattern, electromagnetic fields characteristics of various functional regions, electromagnetic source contribution and trace to the Electromagnetic sources for hot points. The analysis reveals that the electric field of total frequency band of this area is(1.08±0.59) V/m,84.00% of all points values are less than 1.5 V/m, and the total value of RF and the long-medium-short waves accounted for 68.2% and 31.8% of the total value of the total frequency band respectively, while the electric field of the base station is 0.63 V/m, accounting for 76.70% of the total radio frequency value, which means the most contributed source of electromagnetic radiation in the region is base stations. The spatial distribution of the total value of the full frequency band and radio frequency band basically have the same trend, which is significantly positively correlated with the population density and the distribution of base stations, while the electric field strength of long-medium-short waves in the ambient is mainly influenced by the relative radiated facilities within small ranges. The intensity of the full-day electric field strength of the base stations in residential area is generally above industrial zone which shows that the distribution of the base stations of the residential area is relatively dense. From 7: 00—18: 00 working hours, the electric field strength of 5G base stations in industrial area is greater than that of residential area. And during the rest time period, the electric field strength of 5G base stations in residential area is greater than that of industrial zones. Analysis of hot-spot map can position concentrated areas of electromagnetic radiation facilities such as mobile base stations of multiple operators, and trace back to the long-medium-short wave electromagnetic radiation sources and surrounding affected areas through spectrum analysis. Reference | Related Articles | Metrics

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Analysis of key technical points and difficulties in the process of emergency response to radiation accidents ZHANG Yan, QIAO Qingdang, YANG Duanjie RADIATION PROTECTION    2024, 44 (4): 423-429.   Abstract （85）      PDF（pc） （2664KB）（101）       Knowledge map    Save The response process to radiation accidents includes several important action steps. This article analyzes the technical key points of each main step in the process of radiation accident emergency response, combines with practical experience, and provides countermeasures and suggestions for the existing difficulties. This analysis could provide reference for further improvement of radiation accident emergency response in the future. Reference | Related Articles | Metrics

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A performance study of a new personal neutron dosimeter based on SSNTD JIAO Yan, CAO Qinjian, WEI Xiaofeng, XU Yuan, ZHAO Yuan, LIU Liye RADIATION PROTECTION    2024, 44 (1): 33-41.   Abstract （82）      PDF（pc） （3552KB）（50）       Knowledge map    Save As a passive personal neutron dosimeter, CR-39 solid state nuclear track detector is convenient, cheap, insensitive to gamma and beta rays and has strong anti-interference ability, and better response to fast neutrons. A new personal neutron dosimeter has been developed combining with two measurement methods of CR-39 and albedo thermoluminescence dosimeter. Performance experiments are carried out on the CR-39 detector according to the international standard ISO 21909-1. The results show that the CR-39 solid state nuclear track detector has good repeatability, batch homogeneity, dose linearity, stability, response of reference radiation field and no photon-sensitivity. The detection threshold and uncertainty of dose measurement are presented in this paper. It provides an experimental data reference for the introduction of international standard. Reference | Related Articles | Metrics

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Research on regional environmental electromagnetic radiation monitoring technology WANG Guan, MIAO Erkang, XU Hui, GAO Peng RADIATION PROTECTION    2024, 44 (3): 224-232.   Abstract （80）      PDF（pc） （10710KB）（82）       Knowledge map    Save With the continuous improvement of information technology in society, complex and changeable electromagnetic wave signals fill the whole space. How to obtain electromagnetic environment monitoring data accurately and effectively has become the key to scientific assessment of regional environmental electromagnetic radiation level. Based on the characteristics of environmental electromagnetic radiation and the existing standards and monitoring practices as well as the work of the international organization, regional environmental electromagnetic radiation monitoring by means of vehicle-borne survey and grid monitoring are discussed. This study not only provides guidance for further improving the existing work of electromagnetic environment monitoring, but also provides a technical reference for improving the regulation efficiency of Chinese electromagnetic environment. Reference | Related Articles | Metrics

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RADIATION PROTECTION    2024, 44 (1): 0-0.   Abstract （76）      PDF（pc） （190KB）（82）       Knowledge map    Save Related Articles | Metrics

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International status of the development of transportable small modular nuclear reactors and transportation safety SUN Hongchao, LI Guoqiang, WANG Pengyi, MENG Dongyuan, WANG Changwu, WANG Zhipeng, ZHUANG Dajie, SUN Shutang, ZHANG Jiangang RADIATION PROTECTION    2024, 44 (3): 210-216.   Abstract （76）      PDF（pc） （3021KB）（66）       Knowledge map    Save The transportable nuclear power reactors (TNPPs), as a kind of small modular reactors (SMR, generally below 30 MW), can produce electricity for remote and small local communities. TNPPs can be transported by land or other means of transportation, and can operate on the transport vehicle or after unload from the transport vehicle. Thanks to meeting diverse energy needs, TNPPs have been attracting the attention of all countries. In this paper, the development status of TNPPs was introduced, and the features of different types of TNPPs, the problems and challenges to TNPPs development were summarized. The problems arising in the transport safety of TNPPs and countermeasures were mainly discussed. Reference | Related Articles | Metrics

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Review and analysis of radiation accidents in China from 2016 to 2020 GONG Yu, DANG Lei, LI Xiaoding, BAI Gang, QU Yunhuan, QI Yuan RADIATION PROTECTION    2023, 43 (6): 665-670.   Abstract （75）      PDF（pc） （1485KB）（92）       Knowledge map    Save In order to draw lessons from the radiation accidents and to improve radiation safety level, the author summarizes and sorts out the radiation accidents that occurred in China from 2016 to 2020. The author also analyzes the types, levels and consequences of the accidents on the basis of the final evaluation of the 13th Five Year Plan for Nuclear Safety and Radioactive Pollution Prevention and Control and the 2025 Long-term Goals carried out by the Ministry of Ecology and Environment. The issues caused by radiation accidents are discussed. Suggestions are put forward, such as optimizing radiation safety supervision, cultivating nuclear safety culture, establishing radiation safety evaluation indicators, and improving the compensation mechanism for radiation accident damage. Reference | Related Articles | Metrics

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Investigation on radon concentration in Chengdu metro XU Lipeng, CHEN Li, WANG Xianliang, LI Jie, PENG Yi, LIU Min, LI Chunyang, YANG Qiang, GU Yi, LI Jianying RADIATION PROTECTION    2024, 44 (4): 367-373.   Abstract （75）      PDF（pc） （1299KB）（62）       Knowledge map    Save To understand the radon concentration levels in the Chengdu metro environment, instantaneous methods and cumulative methods were used to conduct an investigation to the radon concentration levels at 31 subway stations. The results showed that the radon concentration of 279 measuring points in Chengdu metro as measured instantaneously ranged from 9.1 to 39.0 Bq/m3, with an average of (19.7±7.8) Bq/m3. The radon concentration of 124 measuring points at the subway stations as measured cumulatively twice ranged from 9.7 to 32.5 Bq/m3, with an average of (18.4±4.3) Bq/m3. The radon concentration level was significantly lower than the standard reference value. It was found that the radon concentrations inside the subway cars were lower than that at the subway stations on the corresponding line, with a positive correlation reaching 0.84 (P<0.05), and the radon concentrations at the upper security inspection points were lower than that at the lower platforms of the corresponding line, with a positive correlation reaching 0.81 (P<0.05). The radon concentrations in the open ticket halls were lower than that in the control rooms in the enclosed area on the same floor of the corresponding line. Analysis revealed that ventilation is effective in reducing the level of radon concentration in the subway. The annual effective dose of radon and its progeny in the ambient air of the Chengdu metro to the subway staff and passengers is estimated to be 0.15 mSv and 0.05 mSv respectively. Reference | Related Articles | Metrics

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Study on standard system for containment enclosures LIU Fugui, LIU Lipo, DONG Fangfang, JIN Liqiang, PAN Jianjun, LI Xiaozhen, GUO Jianxin RADIATION PROTECTION    2024, 44 (1): 85-92.   Abstract （74）      PDF（pc） （2044KB）（52）       Knowledge map    Save Containment enclosures are specialized facilities that meet specific requirements of seal and radiation protection. This paper comprehensively sorts out the current status of containment enclosure standards in China. This paper also analyzes the standard requirements of containment enclosures in terms of design, manufacture, installation & commissioning, operation & maintenance as well as decommissioning. Finally this paper establishes the structure diagram and gives standard specifications for containment enclosures, which lays a foundation for guiding the application and implementation of containment enclosures standards and the standards research and development work urgently needed in the next step. Reference | Related Articles | Metrics

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Study on the residual radioactivity level in the open site of soil for exploitation and utilization of associated radioactive ore ZHENG Guofeng, XIE Shujun, LIAO Yunxuan, ZHANG Ailing, SHANG Zhaorong, GAO Siyi RADIATION PROTECTION    2024, 44 (2): 151-159.   Abstract （73）      PDF（pc） （1116KB）（73）       Knowledge map    Save During the exploitation and utilization of associated radioactive ore, the associated natural radionuclides may migrate to soil and cause soil pollution. This paper analyzes soil pollution risk control regulations in China and internationally. By using RESRAD software program, the screening value of residual soil radioactivity at the open site of associated radioactive ore utilization according to different land use purposes were calculated and deduced. The calculated screening values were compared with those recommended by the U.S. regulatory agency. Therefore, the screening values of soil residual radioactivity of 6 typical radionuclides were determined, which can help improve our country’s soil radioactive pollution risk control regulations. Reference | Related Articles | Metrics

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Development of a prototype instrument for α-surface contamination measurement based on air Radioluminescence JIN Chenghe, ZHAO Yuan, WANG Yu, CAO Qinjian, XIONG Wanchun, HUANG Mingxiao, LIU Liye, LI Yan, DONG Jiajie, XIA Sanqiang RADIATION PROTECTION    2023, 43 (6): 549-555.   Abstract （72）      PDF（pc） （4466KB）（48）       Knowledge map    Save Optical detection method of α surface contamination based on air Radioluminescence was one of the active area of research since its first demonstration at the beginning of this century. Compared to other kinds of α surface contamination measurement methods, the optical detection method of α surface contamination has the following advantages: it can realize non-contact α surface contamination measurement, it can effectively measure non-flat surface α contamination, and finally it can effectively reduce the risk of surface contamination. But on the other hand, affected by low emission yield of air Radioluminescence from α particle energy deposition, the detection limit of optical detection method of α surface contamination is too high compared with other kinds of α surface contamination methods. In this paper we presented a prototype instrument for measurement of α surface contamination. The instrument is based on optical detection of air Radioluminescence from α radiation, and work in telescope scanning mode. Primary performance testing results show that, the sensitivity of the prototype instrument is 2.63 s-1/kBq, and the MDA is 1.0 kBq at 1 m distance from object lens and 10 s measurement time. Field experiment shows that the prototype instrument can also accurately measure space distribution of α surface contamination. Reference | Related Articles | Metrics

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Research on accounting boundary and method of greenhouse gas emission of nuclear power plants life cycle WU Feifei, KANG Jing, WANG Yan, LIAN Bing, YANG Jie, YUE Qi RADIATION PROTECTION    2024, 44 (1): 10-18.   Abstract （72）      PDF（pc） （2653KB）（70）       Knowledge map    Save Nuclear energy is an important source of low-carbon electricity, which is conducive to achieving the “dual carbon” goal. At the national level, a unified and standardized accounting method for greenhouse gas emissions by nuclear power industry has not been established. Relevant research on the accounting boundary and method are essential. Based on critical issues of greenhouse gas emissions accounting, we systematically analyzed the accounting boundary and methods of greenhouse gas emissions from nuclear power life cycle at home and abroad. In addition, we compared the greenhouse gas accounting standards and guidelines for enterprises in key industries. The accounting research framework was proposed for greenhouse gas emissions during the nuclear power life cycle. The future research prospects are proposed from three aspects, which include the establishment of a greenhouse gas emission accounting system, research on emission influencing factors and case studies at the decommissioning stage. The proposed research can provide a reference for establishing a unified and standardized statistical accounting system for greenhouse gas in the nuclear power industry in China. Reference | Related Articles | Metrics

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Research on the effects of fast neutron irradiation on silicon photomultiplier tubes and CLYC detectors CHEN Zhaoxi, SUN Shifeng, ZHANG Xiangming, ZHANG Ao RADIATION PROTECTION    2024, 44 (1): 62-70.   Abstract （71）      PDF（pc） （7277KB）（55）       Knowledge map    Save In this experiment, the SiPM device and Cs2LiYCl6 (CLYC) scintillator detector were exposed to a 14 MeV fast neutron field, and the maximum cumulative irradiation fluence reached 1.53×1011 cm-2. The effects of neutron irradiation on the SiPM device parameters and effects on CLYC detector performance were studied. The focus was on the gain, dark count rate, dark current, breakdown voltage, quenching resistance and other parameters of SiPM before and after irradiation with different fluences, as well as the changes and causes for the detection performance of the CLYC detector. Among them, the dark count rate increased the highest with 3 orders of magnitude, the dark current increased by up to 2 orders of magnitude, and the energy resolution of the CLYC detector decreased by 1.4% after removing the background. After the irradiation experiment, the SiPM and CLYC detectors were annealed at room temperature to study the SiPM device parameters and detector performance recovery. The performance of SiPM and CLYC detectors gradually deteriorates as the neutron fluence increases. For SiPM, the main performance is the increase in dark count rate and dark current. For the CLYC detector, the main manifestation is the reduction of energy resolution. The annealing process helps mitigate the effects of neutron irradiation and restores some performance of SiPM and CLYC detectors. Reference | Related Articles | Metrics

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Status and enlightenment of eye lens dose monitoring for radioactive workers in foreign nuclear facilities XUE Xiangming, WU Xiaoyan, YANG Xue, Gu Xiaona, ZHAN Jingming RADIATION PROTECTION    2024, 44 (3): 217-223.   Abstract （71）      PDF（pc） （1089KB）（77）       Knowledge map    Save International community has revised the eye lens dose limit for more than 10 years, during which several countries have integrated the new eye lens dose limit into their national law. Data from abroad show that the eye lens dose of some job in nuclear facilities may be high. Some countries have put forward specific monitoring programs, but relevant domestic information is lacking. On the basis of sorting out the dose levels of eye lens among occupational populations in foreign nuclear facilities, this article reviews the monitoring objects, requirements for monitoring dose levels, and monitoring methods proposed by foreign institutions, in order to provide reference for the revision of eye lens dose limits and related work in China’s nuclear facilities. Reference | Related Articles | Metrics

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Discussion on key technologies of portable on-line monitoring equipment for low-level radioactive waste water in NPPs ZHOU Jianwang, YOU Chengmao, MEI Xiangjie, ZHOU Kebo, ZHANG Sujie, YIN Wangming RADIATION PROTECTION    2024, 44 (4): 349-355.   Abstract （71）      PDF（pc） （2713KB）（97）       Knowledge map    Save Based on the situation and demand of a NPP, the features of LLRW are summarized. The technical requirements for portable online radioactive monitoring equipment are specified. The most important requirement is to meet the low detection limit (minimum detectable activity concentration, MDAC≤8 Bq/L) and portability of the equipment (total weight of the equipment should be≤50 kg). Key technologies such as measurement mode, detector selection and calibration method are then discussed. The measurement mode is generally sampling mode. The detector is generally large volume NaI crystal. The calibration methods are usually standard liquid source method and representative point method. Finally, the current online monitoring equipment for LLRW is investigated. It is found that the weights of all the existing equipment are more than 200 kg, which is far from the requirement of NPPs. Therefore, it is necessary to develop new on-line monitoring equipment with low MDAC and excellent portability. Three research directions are suggested, which are the application of new detector types, the development of new detector structure, and the development of new measurement methods. In order to improve the detection efficiency, a new detector structure based on annular NaI crystal is proposed. The weight of the new equipment and the MDAC is discussed preliminarily. It is expected to meet the requirements of NPPs. Reference | Related Articles | Metrics

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Numerical simulation and analysis on intermittent discharge of liquid effluent from a coastal nuclear power plant ZHANG Haiwen, JI Ping, ZHAO Yijun, CHEN Xiaoli, ZENG Li RADIATION PROTECTION    2024, 44 (1): 71-79.   Abstract （68）      PDF（pc） （9650KB）（62）       Knowledge map    Save A numerical model for discharge of liquid effluent from a coastal nuclear power plant is established by using MIKE 21 Hydrodynamic model with transport module in an unstructured grid. Numerical simulations of transport and diffusion of liquid effluent with non-decaying nuclide are carried out with different scenarios of the intermittent discharge starting at the four typical tidal moments respectively, in addition to a comparison with continuous discharge under the condition of equal discharge concentration. The mean concentration distribution, impact areas of liquid effluent in the sea water and characteristic values of intake concentration in different scenarios are given. The comparative analysis indicate that the transport and diffusion process of liquid effluent from the coastal nuclear power plant is mainly affected by tidal current. The intermittent discharge starting at the moment of ebb strength has significant advantages in respect of environmental impact and intake concentration. The calculated results can provide technical support for the optimization of liquid effluent discharge mode and marine environmental impact assessment. Reference | Related Articles | Metrics

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Calculation of RBE weighted absorbed dose coefficients for an accidental inhalation of 241Am CHEN Qianlan, CHEN Baowei, XIA Yihua, LUO Zhiping , LIU Senlin RADIATION PROTECTION    2024, 44 (1): 27-32.   Abstract （68）      PDF（pc） （910KB）（45）       Knowledge map    Save When an acute high intake of radionuclide has occurred or is going to occur in the dose range close to deterministic effect (or tissue reaction), it is needed for a technical platform or tool used to quickly estimate the short-term absorbed dose in interested organs or tissues, in order to make decision for nuclear and radiation response actions and other response actions suggested by IAEA Safety Guide No.GSG-2, which can minimize large radiation dose to the people exposed and then protect the health of the people actually. Therefore this paper focuses on the followings: studying the designing principle and models’ parameters foundation of the International Commission on Radiological Protection (ICRP) Human Respiratory Tract Model (HRTM), Systemic Model, Human Alimentary Tract Model (HATM) and Wound Model; compiling the retention and excretion fraction m(t) calculation codes, after its verification, to calculate the target organ’s RBE weighted absorbed dose AD(30)T for an urgent inhalation of 241Am, and the correctness of the results are ensured by comparison of two persons’ results. Reference | Related Articles | Metrics

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Analysis on tritium discharged at Tianwan Nuclear Power Station VVER reactor GUO Yinglai, WANG Hu, CHEN Yunfeng, HUI Miaomiao, LIU Hanhan, WU Chunyuan RADIATION PROTECTION    2024, 44 (3): 240-243.   Abstract （68）      PDF（pc） （2846KB）（74）       Knowledge map    Save This article analyzes gaseous tritium discharge and liquid tritium discharge since the operation of TNPS Unit 1&2 (VVER). It was found that the tritium discharge and normalized discharge meet the standard's requirements. After the 18-month fuel cycle, the annual emission of gaseous tritium did not change significantly, but the annual discharge of liquid tritium increased. Liquid tritium discharge is the main way at TNPS Unit 1&2, and the proportion of liquid tritium discharge is greater than 90% of total tritium discharge. In each fuel cycle, the monthly discharge of liquid tritium changes periodically, while the monthly emission of gaseous tritium does not change significantly. Reference | Related Articles | Metrics

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The correlation analysis on tritium in the air and rainwater around Tianwan Nuclear Power Plant GUO Yinglai, WANG Hu,CHEN Yunfeng, LIU Hanhan,WU Chunyuan, HUI Miaomiao RADIATION PROTECTION    2024, 44 (3): 244-247.   Abstract （68）      PDF（pc） （6280KB）（72）       Knowledge map    Save Based on the environmental monitoring data of tritium in air and rainwater around Tianwan nuclear power station (TNPS) over the years, the correlation is analyzed with the distance, season and gaseous tritium emission from the sampling station. It is found that the activity concentration of tritium in air and rainwater around the nuclear power station is negatively correlated with the distance from the nuclear power station, and is positively correlated with gaseous tritium emission. The monitoring statistical results in the third quarter are the lowest. Reference | Related Articles | Metrics

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Development of a dosimeter for Hp(0.07) monitoring WEI Yingjing, WU Zhifang, FANG Dengfu, LIU Liye, FENG Mei, WEI Shiliang RADIATION PROTECTION    2024, 44 (1): 42-49.   Abstract （67）      PDF（pc） （3318KB）（74）       Knowledge map    Save In view of the poor performance of dosimeters for low energy β rays monitoring in China, a ZF-P7 Hp(0.07) dosimeter was developed, based on LiF:Mg,Cu,P thermoluminescence detector and combined with simulation calculation, in order to solve the problem of accurate measurement of Hp(0.07) dose in β and γ mixed fields. The performance test results of ZF-P7 Hp(0.07) dosimeter are as follows: For the maximum energy of 225 keV-2.274 MeV of β rays, the energy response ranges is 0.67-0.95; For energies between 16 keV to 1 250 keV of X or γ rays, the energy response ranges is 0.66-1.45; Within the range of 100 μSv-1.2 Sv, the dose linearity is 0.91-1.10; Under the X radiation of 65 keV and angle range of 0° to ±60 °, the angle response of -60° to 60° is 0.99-1.09; Under the β radiation of 85Kr, the angle response of -60° to 60° is 0.94-1.11. According to the measurement results, the performance of ZF-P7 dosimeter meets the requirements of EJ/T 1178—2005 and JJG 37—2014. Because the ZF-P7 dosimeter has excellent performance, especially the radiation response is good at X,γ,β mixed radiation filed, which can solve the problem of operators’ Hp (0.07) dose monitoring in the mixed radiation fields. It can be widely used in the Hp(0.07) dose monitoring for workers in the mixed radiation fields. Reference | Related Articles | Metrics

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Comparison and analysis of electromagnetic radiation monitoring instruments in anechoic chamber NING Jian, LI Zhanyou, ZHOU Feng, YUAN Xiuhua RADIATION PROTECTION    2024, 44 (1): 57-61.   Abstract （67）      PDF（pc） （4011KB）（32）       Knowledge map    Save In order to improve the comparability of the comparison results of monitoring instruments, it is necessary to select a place where the field strength is stable and is not affected by the external electromagnetic environment for comparison. This article analyzes and summarizes the experience and practices of conducting frequency-selective radio frequency electromagnetic radiation monitoring instrument comparison-measurement in a standard anechoic chamber, and finds out some problems that are difficult to detect in daily work.This paper also proposes suggestions for monitoring instrument verification during the monitoring period.Conducting comparisons in a stable and standard electromagnetic field environment could provide a new practice for electromagnetic environment monitoring instrument comparison. Reference | Related Articles | Metrics

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Investigation and risk assessment of soil radioactivity levels at a rare earth refining factory and surrending area ZHU Xiaojiao, XIAO Bifu, GU Hong, LV Yingfu, LIU Pei, ZHOU Wei, LI Yuandong, TANG Hui RADIATION PROTECTION    2024, 44 (3): 233-239.   Abstract （67）      PDF（pc） （2105KB）（52）       Knowledge map    Save In order to find out the range and harm of radioactive contamination in soil of a rare earth refining factory and its surrounding soil, the mass activity concentrations of 238U, 232Th and 226Ra in soil of a rare earth refining factory and its surrounding soil were investigated. The radionuclide contamination of soil in the study area was evaluated by geological accumulation index method, single factor pollution index method and Nemerow comprehensive pollution index method. The health risk assessment model of US EPA was used for risk calculation. The results showed that the mass activity concentration ranges of 238U, 232Th and 226Ra were 20.9-92.6 Bq/kg, 25.1-565.5 Bq/kg, 17.3-83.1 Bq/kg, respectively. The geological accumulation index method showed that the two sampling points downstream of the outlet and west side of the plant were mono-nuclide pollution. The single factor pollution index method and Nemerow comprehensive pollution index method showed that the comprehensive pollution of soil at each site reached mild pollution. Health risk assessment showed that the maximum risk values caused by 238U, 232Th and 226Ra were all less than 10-6, and all were within the acceptable range. The main exposure routes were ingestion routes, and the greatest risk came from 232Th. The investigation shows that the health risk of 238U, 232Th and 226Ra in a rare earth refining factory and its surrounding soil is within the acceptable range. Reference | Related Articles | Metrics

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Study on the dominant ventilation method for radon reduction in uranium mine LI Xianjie, ZHANG Zhe, HU Penghua, CHENG Gang, REN Jianjun, LIU Xiaochen RADIATION PROTECTION    2024, 44 (1): 80-84.   Abstract （65）      PDF（pc） （910KB）（32）       Knowledge map    Save Based on the radon exudation rule in the inlet and the using sections of the mine ventilation network, the calculation formula of air demand for radon reduction in uranium mines under different ventilation modes is derived from the basic equation of radon reduction ventilation in uranium mines. The evaluation indicators of dominant ventilation mode are derived from the effective air supply capacity of the inlet section. And the discrimination method of radon reduction ventilation mode in uranium mines is suggested. Reference | Related Articles | Metrics

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A proposal to strengthen the application of nasal swab analysis in routine monitoring programme for internal contamination WANG Yadong, WANG Lusheng, MA Yan, DAI Xiongxin RADIATION PROTECTION    2023, 43 (6): 687-692.   Abstract （65）      PDF（pc） （1131KB）（21）       Knowledge map    Save In order to timely detect the occurrence of accidental internal radionuclide contamination of workers and accurately identify the contaminated individuals for medical treatment, it was proposed to strengthen the application of nasal swab analysis in the routine monitoring programme. The reliability of nasal swab analysis for internal contamination monitoring was validated by the human respiratory tract aerosol deposition model and the real data of nasal swab analysis from nuclear facilities in the United States and Japan. All the available methods of nasal swab analysis were listed and assessed in the aspects of speed and accuracy, and the prospect of imposing a daily nasal swab analysis for internal contamination monitoring was described. To make the proposal more practicable, several specific suggestions for further research were also put forward. Reference | Related Articles | Metrics

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Concentration study of 14C in marine organisms caused by NPP effluents and application to public dose evaluation XU Liping RADIATION PROTECTION    2024, 44 (2): 174-181.   Abstract （65）      PDF（pc） （1364KB）（47）       Knowledge map    Save Considering the exposure to the surrounding public caused by coastal nuclear power plant radioactive effluents, the largest contribution is caused by 14C. During dose evaluation of the key route feeding from marine organisms, the 14C concentration will directly affected the rationality. In this study, the specific activity equilibrium model was adopted, as well as consideration of the actual carbon content of sea water and marine organisms in Fuqing NPP. Calculating 14C concentration factors of different species of marine organisms, which were verified by comparing with measured values and IAEA rec-ommended values of some marine organisms on sites. As conclusions, 14C concentration factors suitable for the Fuqing NPP area were obtained. It is recommended to take 6 800 for fish, 5 300 for algae, 5 000 for crustaceans and 4 500 for mollusks. They can be applied to public dose evaluation by dividing different age groups and calculate the public personal effective dose caused by 14C intake from marine organisms. These recommended values can be applied to the assessment of the public radiation dose caused by the effluents from the coastal NPP. Reference | Related Articles | Metrics

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The investigation and analysis of the associated radioactivity in a stone coal vanadium extraction enterprise in Gansu Province WANG Fujun, WANG Haishan, HAO Jianguo, FANG Peng, MA Hongda, WEI Jinxiang, LIANG Xiaoye, DING Jingjie, LIU Zuoye RADIATION PROTECTION    2023, 43 (6): 586-594.   Abstract （64）      PDF（pc） （1327KB）（48）       Knowledge map    Save In this paper, the geographical distribution of stone coal associated radioactive mineral resources in Gansu Province was introduced, and the natural radionuclides of stone coal associated minerals and radiation problem was studied in the process of development and utilization. Investigations found that the radioactivity of stone coal associated ore mainly comes from uranium series radionuclides 238U and 226Ra, and the average activity concentration of 238U and 226Ra in some mining areas exceeds 1 Bq/g. Taking a stone coal vanadium extraction enterprise in Gansu Province as an example, the radiation dose rate recieved by the staff and the public is evaluated, and the possibility of radioactive pollution transferring to the environment in the form of waste water, waste gas and radioactive solid waste is analyzed. In view of the existing radioactive pollution problems of stone coal associated radioactive mines, the corresponding suggestions are put forward. Reference | Related Articles | Metrics

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Retention calculation and comparison between new and old model based on the ICRP new iodine biokinetic model DAI Wei, WANG Ming, DONG Lang, ZHANG Qingxian, GU Yi, ZENG Guoqiang, LI Sangang RADIATION PROTECTION    2024, 44 (2): 110-119.   Abstract （64）      PDF（pc） （12261KB）（45）       Knowledge map    Save One new detailed biokinetic model for systemic iodine has been published in the International Commission on Radiological Protection (ICRP) Publication No. 137, which will lead to the calculation results of retention and excretion based on the new model that differs from the old iodine model. This paper aims to quantitatively analyze the difference in the calculation results of the old and new iodine system models, to provide a reference for the accurate assessment of radioactive iodine-induced internal exposure in China. In this paper, the matrix algorithm was used to build a calculation model of radioactive iodine based on ICRP publications, and the retention of radioactive iodine (including I-125, I-129, I-131) in thyroid and daily urine after intake through different ways (inhalation, ingestion and intravenous injection) was systematically analyzed. In addition, considering that the new model divides the liver and kidney parts that were not in the old model, the retention of radioactive iodine in these organs is also calculated and analyzed in this paper. The results showed that there were significant differences in the calculation results of radioactive iodine in the thyroid gland and daily urination calculated by the old and new models. But compared with ingestion and injection, the inhalation method could cause the largest difference in the calculation results.In the new model, the calculation results of retention in liver and kidney were different, but the variation tendency was similar. Reference | Related Articles | Metrics

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Development of fission ionization chamber detector for reactor neutron flux measurement QIU Shunli, XIAO Wei, DONG Jincheng, GE Mengtuan, ZHAI Chunrong, TANG Zhongming, ZHOU Yulin, ZENG Le, LIU Haifeng, SUN Guangzhi, CHENG Hui, SHI Xianwu, LIU Wenzhen RADIATION PROTECTION    2024, 44 (2): 134-140.   Abstract （64）      PDF（pc） （5120KB）（33）       Knowledge map    Save In order to establish a monitoring device for reactor neutron flux measurement to meet the measurement requirements of ex-core nuclear measurement system, a fission ionization chamber detector with long sensitive region, wide range, high sensitivity and strong γ-suppression ability has been developed. At the same time, the thermal neutron sensitivity, high voltage plateau characteristic, screening threshold plateau characteristic and γ sensitivity of the fission ionization chamber detector are tested and verified. The test results show that the comprehensive performance of the fission ionization chamber can meet the application requirements of the intermediate range measurement channel for ex-core nuclear measurement system of the AP1000 series nuclear power plant. Reference | Related Articles | Metrics

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Study on the diamond dose measurement device for X-rays generated from ultrashort and ultra-intense laser facility SONG Honghu, WU Zhen, QIU Rui, WEI Shuoyang, GONG Hui, ZHANG Hui, LI Junli RADIATION PROTECTION    2023, 43 (6): 542-548.   Abstract （63）      PDF（pc） （5323KB）（44）       Knowledge map    Save An active dose measurement device based on a diamond detector was developed by our research group, and its performance was further studied. Monte Carlo software FLUKA was used to model the device. Energy and angular response simulations were performed based on the model. The device was calibrated in China National Institute of Metrology. Energy response and dose rate response calibration of the device was conducted by using 137Cs and 60Co. 137Cs is used for the angular response calibration of the device. The results showed that the output current of the device was linear with the dose rate, and no obvious saturation phenomenon was observed. The device has a good angular response to 137Cs, with the maximum variation less than 18%. Related verification experiments were carried out based on 3 MV and 6 MV electron pulse accelerator and “XG-III” laser facility. The results given by the device were consistent with Unidos dosimeter and TLD detectors, with maximum deviation less than 7% and 35%, respectively. Based on the above simulation and experiments, the feasibility of applying this device to real-time dose measurement of pulsed radiation field induced by ultra-short and ultra-intense laser facility is further verified, which provides an alternative for dosimetric method of such pulsed radiation field. Reference | Related Articles | Metrics

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Organic iodine formation, filtration emission, and steam environment simulation under core melt accident GAO Linfeng, LIANG Junqin, YAO Yanyan, ZHAO Gaoxin, CHEN Xin, CHANG Sen, LI Xin RADIATION PROTECTION    2023, 43 (6): 576-585.   Abstract （61）      PDF（pc） （6365KB）（36）       Knowledge map    Save When nuclear power plant coolant loss accident leads to core melting, radioactive iodine in nuclear fuel will be released into the containment with coolant and will form high temperature and high pressure steam environment. Under natural action and artificial intervention (spraying, etc.), the physical and chemical forms of iodine gradually change, forming a gaseous iodine environment dominated by organic iodine in the long-term stage. In this paper, the formation and filtration process of organic iodine in accident condition of nuclear power plant are described and the simulation of organic iodine vapor environment is carried out. By quantitative vaporization and multiple control, a wide-range of accurate simulation of organic iodine vapor environment represented by typical accident operating parameters (130 ℃, 399 kPa, 95%RH) was achieved. The simulation of iodine-containing steam environment can be used for the detection of organic iodine filtration performance of in-service adsorbents and the development of new adsorbents, which is of great significance in organic iodine filtration and controlled discharge under accident conditions at nuclear power plant. Reference | Related Articles | Metrics

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Research on optimal management of very low level radioactive waste from nuclear power plants in China ZHANG Li, LIU Jianqin, QIN Xiang, GAO Kai, YANG Song, HAN Xu, GUO Xiliang RADIATION PROTECTION    2024, 44 (2): 167-173.   Abstract （61）      PDF（pc） （5033KB）（64）       Knowledge map    Save With the promulgation and implementation of domestic radioactive waste classification standard, operators of nuclear power plants began to pay attention to classified management of radioactive waste. Among them, very low level radioactive waste generated during the operation of NPPs have the properties of low radioactivity and large quantities. If they are managed as low-level waste, it will not only increase the operation cost, but also occupy the resources of the disposal site, which is not conducive to the minimization management of radioactive waste. Based on the current situation of domestic VLLW management, combined with the technology and good practices of international treatment and disposal of VLLW, this paper proposes an optimized management route for VLLW in China. Reference | Related Articles | Metrics

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RADIATION PROTECTION    2024, 44 (3): 264-264.   Abstract （61）      PDF（pc） （581KB）（4）       Knowledge map    Save Related Articles | Metrics

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Preliminary study on the method for estimating 18F activity through multi-time span spectral detection FENG Jiangping, ZHANG Jinfan, GUO Jianfeng RADIATION PROTECTION    2023, 43 (6): 595-597.   Abstract （60）      PDF（pc） （1079KB）（29）       Knowledge map    Save In order to solve the measurement difficulty of 18F activity, a new method (attenuation method) for measuring 18F activity with energy spectrum is put forward based on the decay law and binding energy spectrum multi-time span detection. Based on empirical calculations, the relative uncertainty of attenuation method is 3.1%. It is preliminarily believed that this method is correct and feasible, and can solve the technical difficulties in energy spectrum measurement of 18F. Reference | Related Articles | Metrics

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A new generation of human radiation dose calculation technology based on deformable mesh-type phantom ZHAO Ri, LIU Zhaoxing, LIU Na, WANG Xianxiang, ZHANG Jing, LIANG Runcheng, LIU Xin, LINGHU Renjing, DAI Yuling RADIATION PROTECTION    2023, 43 (6): 533-541.   Abstract （60）      PDF（pc） （9536KB）（46）       Knowledge map    Save In order to improve the accuracy of dose calculation and meet the requirement of precise radiation protection, a complete method of dose calculation based on deformable mesh-type phantom was established, including the deformation algorithm of human mesh-type phantom and the high-speed Monte Carlo calculation method of this phantom. Algorithms of rigid rotation matrix, Laplacian volume map and As-rigid-as-possible transformance were used to deform the bone, soft tissue and internal organs respectively. The high speed Monte Carlo calculation of the phantom is based on Delaunay tetrahedralization technology. Based on this, a comparative test of dose calculation between the deformable mesh-type phantom and the non-deformable voxel phantom was carried out. The results show that, for squatting posture and bottom-up irradiating condition, the effective dose obtained by the mesh-type phantom is 51.2% higher and the organ dose is up to 98.6% higher than that obtained by the voxel phantom; for kneeling posture and antero-posterior irradiating condition, the effective dose obtained by the mesh-type phantom is 58.7% higher and the organ dose is up to 98.0% higher than that obtained by the voxel phantom. This paper focuses on breaking through the key techniques of the new generation of dose calculation technology, including the mesh-type phantom deforming algorithm and high speed Monte Carlo simulation method, which provides important support for the further development of high-precision dose calculation in China. In the future, it is expected to achieve accurate evaluation of personnel dose in precise radiation protection applications. Reference | Related Articles | Metrics

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Influence and correction of sample mass thickness variation for total alpha radioactivity measurement in water DU Yunwu, DENG Xiaoqin, BI Chaowen, ZHU Jie, WANG Liang, ZENG Yi, GUO Xuying, WANG Yan, WANG Qian RADIATION PROTECTION    2023, 43 (6): 566-575.   Abstract （59）      PDF（pc） （10255KB）（82）       Knowledge map    Save The detection efficiency of 241Am and natural alpha radionuclide with different mass thickness was analyzed through experiments and Monte Carlo simulation. The relationship between mass thickness and detection efficiency, count rate, detection efficiency correction factor, as well as reciprocal detection efficiency were analyzed. And the relationship between detection efficiency, effective saturation thickness and energy were also analyzed. The results show that the detection efficiency of alpha radionuclide in water needs to be corrected by the detection efficiency correction factor, branch ratio and component ratio. When the mass thickness is 7 mg/cm2, the equilibrium uranium detection efficiency correction factor is 0.96; With a mass thickness of 2 mg/cm2, the equilibrium thorium detection efficiency correction factor is 1.01, and the equilibrium 226Ra-222Rn detection efficiency correction factor is 1.05. When the mass thickness is greater than 4 mg/cm2, the detection efficiency correction factors of natural uranium, 4% enriched uranium and 97% enriched uranium are basically constant, which are 0.39, 039 and 0.47, respectively. When the mass thickness is less than 0.510 mg/cm2, the detection efficiency correction factor of single alpha radionuclide radiation source is greater than 0.70. When the mass thickness is greater than the effective saturation thickness, the reciprocal of the detection efficiency is linear with the mass thickness. The effective saturation thickness is linearly related to the alpha ray energy. Reference | Related Articles | Metrics

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Uncertainty analysis of calibration factor of radon monitor TIAN Xingyu, ZHANG Xiongjie, PANG Liuqing, LI Yunyang, SU Jianwen RADIATION PROTECTION    2024, 44 (2): 141-146.   Abstract （59）      PDF（pc） （1450KB）（38）       Knowledge map    Save The uncertainty of the calibration factor is an important parameter to evaluate the calibration results and is an important basis for the evaluation of the measurement results of radon monitor. In this paper, the uncertainty source of calibration radon monitor is analyzed by using radon chamber. The relative standard uncertainty of the calibration factor was measured. The results show that the main influencing factors of the uncertainty of the calibration factor include: the repeatability of the standard instrument and the measured instrument; standard instrument calibration factor and its annual stability; inhomogeneity of test area of radon chamber device. Finally, the relative standard uncertainties of the calibration factors at each measurement point are 4.1 %, 3.6 %, and 3.3 %, respectively. Reference | Related Articles | Metrics

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Radiation protection design of nuclear air-cleaning units GUO Chuangcheng, TANG Hui, QIU Jinmeng, WANG Chong, YANG Li, ZHANG Xin RADIATION PROTECTION    2023, 43 (6): 628-633.   Abstract （58）      PDF（pc） （1104KB）（47）       Knowledge map    Save Based on the requirements of relevant standards at home and abroad and practical work experience, radiation protection factors to be considered in the design of nuclear air-cleaning units were synthesized, screened, and summarized. A design process control table that can be used by designer to enhance radiation protection considerations was developed. The table covers various aspects such as component selection, material selection, system configuration and location, maintainability, testability, operability, adsorbent cooling and fire protection, pressure and boundary leakage. Reference | Related Articles | Metrics

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Electromagnetic radiation environmental monitoring of Hubei Province 5G communication base station LUO Qiong, YANG Shaobo RADIATION PROTECTION    2024, 44 (2): 147-150.   Abstract （58）      PDF（pc） （1624KB）（31）       Knowledge map    Save The electromagnetic radiation environment quality of 5G mobile communication base stations which were built and put into operation in Hubei Province from 2021 to 2022 was investigated. The power density of the sampled 266 5G base stations ranges from 0.01 to 295 μW/cm2. Through statistical analysis of monitoring data from aspects such as monitoring distance, functional area, base station type, etc., it was found that the electromagnetic radiation environment of 5G communication base stations in Hubei Province is generally good. The rooftop type base stations in densely populated urban areas such as residential areas are prone to high power density values, but all base stations beyond a horizontal monitoring distance of 50 m meet the standards for multiple application modes, which has guiding implications for the radiation environment management of 5G communication base stations in Hubei Province. Reference | Related Articles | Metrics

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Application of an adaptive Wiener filter in noise reduction for gamma energy spectrum ZHANG Jiawei, NIE Yajie, QI Zijian, ZHAO Yanhui RADIATION PROTECTION    2024, 44 (1): 50-56.   Abstract （57）      PDF（pc） （3417KB）（38）       Knowledge map    Save A noise reduction algorithm based on the adaptive Wiener filter for portable gamma spectrum detectors was developed. Compared with traditional gamma spectrum noise reduction algorithm represented by the five-point third-order filtering and the centerofgravity method,the estimated variance value is used as a measure of local details to implement adaptive adjustment of the noise reduction algorithm. Verified by simulated signals and measured data, the noise reduction algorithm based on the adaptive Wiener filter has faster running speed and better noise reduction effect than the five-point third-order filtering and the center-of-gravity method while retaining the gamma energy spectrum characteristic information. With the advantage of no distortion, it has certain application potential in the energy spectrum noise reduction processing of portable gamma energy spectrum detectors. Reference | Related Articles | Metrics

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Study on the formation mechanism and preparation of 110mAg colloid in the primary circuit of PWR nuclear power plant SUN Yun, XIAO Yan, LI Fuhai, LIN Genxian, LIU Canshuai, SONG Lijun RADIATION PROTECTION    2024, 44 (3): 248-256.   Abstract （56）      PDF（pc） （10677KB）（80）       Knowledge map    Save Under the condition of the simulating water quality of the primary circuit of PWR, colloidal silver nanoparticles were prepared by using lithium borate solution as the medium and hydrazine to reduce silver nitrate. The effects of reducing agent, boric acid, concentration of Ag+, temperature and irradiation conditions on the properties of colloidal silver were investigated. The results showed that boric acid and reducing agent hydrazine can effectively stabilize the colloidal particles. When the molar ratio of hydrazine to silver is 1.0-2.0, the reduction rate of Ag+ is the highest and the colloid is the most stable. The higher the concentration of silver ions, the more negative charges on the surface of colloidal particles, therefore there will be less particle aggregation, and the colloidal stability will be enhanced. Under high temperature and high pressure water environment, it is easier to form colloidal particles with larger particle size. While the irradiation dose ranges from 0.9 kGy to 7.2 kGy, colloidal silver can be formed with or without hydrazine. Reference | Related Articles | Metrics

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RADIATION PROTECTION    2023, 43 (6): 0-0.   Abstract （55）      PDF（pc） （239KB）（58）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2024, 44 (4): 0-0.   Abstract （55）      PDF（pc） （16764KB）（86）       Knowledge map    Save Related Articles | Metrics

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Consideration and suggestions on improving China’s nuclear emergency training and exercise in the new era LIU Yulong, WANG Youyou, HOU Yuhan, BIAN Huahui, LIU Chang RADIATION PROTECTION    2024, 44 (4): 416-422.   Abstract （55）      PDF（pc） （1032KB）（48）       Knowledge map    Save The Chinese government attaches great importance to nuclear emergency training and exercises. As an important component of nuclear emergency management system, this article takes nuclear emergency training and exercises as the starting point, useing the national “Shendun” series of nuclear emergency joint exercises as case analysis, Based on the key points of nuclear emergency core capacity building, this article proposes ideas and suggestions on improving China’s nuclear emergency training and exercise in the new era. Reference | Related Articles | Metrics