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Study on statistical method of effluent emissions from nuclear power plant DANG Yuqin, WANG Wenhai, ZHENG Guofeng, ZHU Kun RADIATION PROTECTION    2023, 43 (4): 300-310.   Abstract （130）      PDF（pc） （5576KB）（78）       Knowledge map    Save The statistics of radioactive effluent emissions from operating nuclear power plants is an important work. However, it is found in practice that the activity concentrations of many radionuclides in the effluents from nuclear power plants are not high, and the analysis results are often lower than the detection limit in the effluent emissions statistics. In this context, it is a challenge to make deep research on how the monitoring data can be processed to bring emissions statistics closer to actual emissions. In this paper, the monitoring data of effluents from Qinshan nuclear power base in recent years are collected; their numerical distribution characteristics are analyzed and studied; the statistical method and strategy of effluent emissions based on radionuclide detection rate are put forward; and the recommended value of the value coefficient of the detection limit of effluent is given. By comparing with the statistical results of traditional methods and by analyzing the differences, it is considered that the statistical method and strategy based on radionuclide detection rate is realistic and feasible, and the statistical results are closer to the actual emission situation, which is worthy of further research. Reference | Related Articles | Metrics

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Research on temperature drift correction method of seawater radioactivity sensor SHI Yan, ZHANG Yingying, WU Bingwei, FENG Xiandong, WANG Yifei, BI Haijie RADIATION PROTECTION    2023, 43 (3): 225-234.   Abstract （101）      PDF（pc） （9407KB）（33）       Knowledge map    Save The seawater radioactivity sensor developed based on NaI(Tl) scintillation crystal detection method is the main technological means to carry out in situ automatic monitoring of marine radionuclides at home and abroad. Nevertheless, when the seawater radioactivity sensor is continuously operating at sea for a long time, the measured seawater gamma spectrum data will drift due to the influence of ambient temperature. In this paper, the seawater radioactivity sensor measurement experiment is carried out under the condition of environmental temperature gradient change, and the drift law of the gamma spectrum data calculated by the seawater radioactivity sensor which occurs with the environmental temperature change is analyzed. When the ambient temperature is lower than 15 ℃, channel address corresponding to the characteristic energy peak increases with the increase of temperature; on the contrary, when the ambient temperature is higher than 15 ℃, the channel address corresponding to the characteristic energy peak decreases with the increase of temperature. The gamma spectrum peak channel address shift can be expressed as a quadratic function of temperature, and further a correction method of gamma spectrum shift based on ambient temperature change is proposed. It is verified by laboratory experiments on air and water environment that the peak channel address drift of characteristic peak after air environment correction is not more than ±2 channels, and the peak channel address drift after water environment correction is not more than ±3 channels, which meets the requirements of temperature drift correction for continuous measurement of gamma spectrum by the sensor. Reference | Related Articles | Metrics

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Research on neutron shielding performance and the secondary γ dose simulation of tungsten boride material CHI Xiaomiao, HAN Yi, LIU Liye, CHEN Faguo, LI Guodong, SHEN Huaya, YANG Mingming, SUN Yansong RADIATION PROTECTION    2023, 43 (4): 343-352.   Abstract （101）      PDF（pc） （15558KB）（54）       Knowledge map    Save In order to neutron absorption and secondary γ ray shielding performance. In this paper, the Geant4 program is used to simulate and analyze the incident neutrons with material thickness from 0 to 2 cm and energy from thermal neutron to 20 MeV. The results show that: (1) W-B series compounds mainly act on the absorption and shielding of neutron energy from thermal neutrons to 10-2 MeV; When the thickness is constant, the neutron absorption performance of W2B5 is the best; When the mass is constant, WB4 has the best neutron absorption performance. (2) From the neutron macroscopic cross section and material density of different materials, compared with traditional neutron absorbing materials, W-B series compounds have more significant advantages in low-energy neutron absorption. Taking thermal neutrons as an example, the neutron macroscopic l cross section of W2B5 material is about 8.67 times that of B203 material and 40.59 times that of PB202 shielding material.(3) the contribution of the secondary γ dose to the total dose decrease with the increase of the incident neutron energyand the contribution of the secondary γ dose to the total dose increase with the increase of the thickness of the shielding material. study provides a reference for the realization of the optimal design of neutron shielding devices for clarifying the application advantages and application scenarios of W-B series compounds, and has practical engineering guidance value. Reference | Related Articles | Metrics

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RADIATION PROTECTION    2023, 43 (4): 0-0.   Abstract （89）      PDF（pc） （184KB）（89）       Knowledge map    Save Related Articles | Metrics

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Evaluation of 137Cs radioactivity level and the induced resident external exposure dose in soils surrounding a nuclear facility LI Lifan, WEN Fuping, HU Xiang, LI Huiping RADIATION PROTECTION    2023, 43 (4): 318-324.   Abstract （86）      PDF（pc） （2969KB）（47）       Knowledge map    Save 137Cs is an artificial radionuclide that has been paid special attention in environmental monitoring of nuclear facilities. In this paper, the 137Cs radioactivity level in soils around a nuclear facility was statistically analyzed, and was compared with similar nuclear facilities from 2012 to 2021. The background deduction method was established for the external radiation dose caused by 137Cs in soils, and the resident external radiation dose caused by 137Cs in soils around the nuclear facility was estimated. The results showed that the activity concentration of 137Cs in soil samples around the nuclear facility decreased first and then increased from 2012 to 2021, and the average activity concentration of 1.81 Bq/kg in recent ten years was slightly higher than that of similar nuclear facilities. From the point of view of monitoring locations, four of the six locations with the highest average 137Cs activity concentration are distributed within a 2 km radius of the nuclear facility. The annual effective dose caused by 137Cs from soil samples around the nuclear facility was 1.24 μSv, which was only 0.5% of the target annual dose for the public specified for the nuclear facility. Reference | Related Articles | Metrics

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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 （84）      PDF（pc） （2026KB）（26）       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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Monte Carlo simulations of radiation dose of astronauts caused by space radiation particles SHEN Jiangyan, YAN Congchong RADIATION PROTECTION    2023, 43 (S1): 8-13.   Abstract （83）      PDF（pc） （3533KB）（47）       Knowledge map    Save Space radiation is one of the main risks for astronauts during space station missions. Because of the complex composition of space radiation particles and the wide range of energy, the study of space radiation particle spectrum can better assist the effect study of space radiation particle on astronauts. Also, the astronaut safety protection mechanism will be further improved. The spatial radiation particle spectrum simulated by Shandong Institute of Advanced Technology and the voxel model of ICRP adult male were used, and an equal-scale model of the “Tianhe” core module was constructed based on the Monte Carto program Geant4.The space radiation dose to astronauts during long-term space station mission in Low Earth Orbit(LEO) was estimated based on the particle flux data. The results show that the skin dose rate reaches 2.22 mGy·d-1 after 163 days in the core module of the space station, and the high energy heavy ions, although only 0.5% in the space radiation particle spectrum, contribute 14.6% of the space radiation dose. This study has some reference significance for astronaut risk assessment and biological effects of high energy heavy ion radiation. Reference | Related Articles | Metrics

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Expert consensus on clinical diagnosis and treatment techniques for local radiation injuries caused by external Iridium-192 source irradiation Nuclear and Radiation Emergency Medicine Branch of the Chinese Nuclear Society, Nuclear and Radiation Emergency Branch of China Society of Radiation Protection Safety, Radiological Health Professional Committee of Chinese Preventive Medicine Association, Environmental Protection and Waste Management Committee of Science and Technology Commission of China National Nuclear Corporation RADIATION PROTECTION    2023, 43 (5): 393-411.   Abstract （83）      PDF（pc） （1345KB）（55）       Knowledge map    Save Focusing on the international frontier of advanced radiation diagnosis and treatment research, and combining the practical experience of more than 30 years of basic research and clinical treatment of radiation injuries in China and especially in the General Hospital of Nuclear Industry, we established a precise assessment technology system for local radiation injuries caused by external Iridium-192 source irradiation from multiple dimensions. The treatment strategy and optimal treatment and efficacy evaluation plan for local radiation injuries were established and validated in the whole process of treatment of local radiation injuries. In this way, the precise assessment, standardized treatment, prognosis, rehabilitation management and long-term medical follow-up of nuclear and radiation injuries can be realized. The cure rate of local radiation injuries can be improved, and the disability rate can be reduced. Theoretical guidance and technical support can be provided for the treatment of local radiation injuries. Reference | Related Articles | Metrics

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Design and testing of source range detector for nuclear measurement system outside reactor core XIAO Wei, HU Chan, QIU Shunli, ZHAI Chunrong, DONG Jincheng, GE Mengtuan, ZHOU Yulin, ZENG Le RADIATION PROTECTION    2023, 43 (3): 218-224.   Abstract （80）      PDF（pc） （3718KB）（42）       Knowledge map    Save A boron lined proportional counter is used to design the source range measurement channel of the ex-core nuclear measurement system. A high sensitivity detector is developed and a set of source rang detection device is designed. The thermal neutron sensitivity on pile test methods are given. The sensitivity, discrimination threshold characteristics, high-voltage plateau characteristics, count rate linearity and measurement range of the detection device are tested and verified. The test results show that the detector has excellent radiation performance. The thermal neutron sensitivity can reach 22 s-1/(cm-2·s-1), and the high-voltage plateau characteristic plateau length is 150 V, with plateau slope 28.3%/100 V. The pulse counting rate of the detector has a significant linear coincidence with the neutron fluence rate, and the upper limit of the neutron fluence measurement can reach 1×105 cm-2·s-1, which meets the use requirements of the source range channel of the external nuclear measurement system. The source range detector can be widely used in nuclear power plant and marine external nuclear measurement and monitoring systems. Reference | Related Articles | Metrics

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Research progress of testing methods for X-ray shielding performance of low-lead/lead-free materials ZHANG Xuan, LI Dehong, ZHANG Xiaole, HAO Guanghui, CAO Lei, ZHANG Jian, HUANG Jianwei, GUO Bin, ZHAO Rui, LI Mengfei RADIATION PROTECTION    2023, 43 (5): 412-421.   Abstract （79）      PDF（pc） （4444KB）（52）       Knowledge map    Save To scientifically and rationally evaluate the protective effect of low-lead/lead-free materials, the shielding performance of such materials needs to be accurately tested. Through literature research, combined with the current relevant standards, this paper introduces shielding performance testing of protective materials from three aspects of X-ray radiation quality, testing equipment and testing methods. According to the different test geometry, there are five detection methods as follows: under the condition of narrow beam, the detector is far away from the material to be tested, so it can not detect the secondary radiation generated by the material to be tested, so it is not suitable for the detection of low-lead/lead-free materials. Under the condition of broad beam, the solid angle of the radiation beam increases and the detector is close to the tested material, which is conducive to the detection of low-lead/lead-free materials, but there are certain requirements for the area of the tested material and the selection of the detector. The inverse broad beam condition is detected by narrow beam and flat ionization chamber, but there is a small field problem. The improved inverse broad beam condition uses IB-AT and IB-AP configurations to reduce the difference of energy spectrum, but the implementation is cumbersome. The improved broad beam can reduce the influence of the small field problem, but there is still the influence of the energy spectrum difference on the results. In practice, the appropriate test method can be selected according to conditions and specific protection needs. Reference | Related Articles | Metrics

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RADIATION PROTECTION    2023, 43 (3): 279-279.   Abstract （78）      PDF（pc） （532KB）（89）       Knowledge map    Save Related Articles | Metrics

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Rapid determination of strontium-89 and strontium-90 in liquid effluent of nuclear power plant by liquid scintillation counting method FANG Chunming, YANG Fan, GUO Xiaocui RADIATION PROTECTION    2023, 43 (3): 243-248.   Abstract （77）      PDF（pc） （3317KB）（44）       Knowledge map    Save This paper described analysis and measurement method for strontium-89 and strontium-90 in liquid effluent of nuclear power plant. Strontium-89 and strontium-90 in liquid effluent are enriched by cation exchange resin, separated by strontium resin, and measured by low background scintillation spectrometer. The relevant measurement conditions are analyzed and studied. This method simplifies the treatment process of liquid effluent of nuclear power plant. The established method can detect multiple nuclides at the same time, and can fully meet the analysis requirements of strontium-89 and strontium-90 in liquid effluent of nuclear power plant. Reference | Related Articles | Metrics

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Study on the status of I-129 monitoring technology for gaseous effluent in reprocessing plant LIN Yibo, LUO Zhiping, PANG Hongchao, WANG Chuangao, CHEN Ran RADIATION PROTECTION    2023, 43 (5): 422-430.   Abstract （75）      PDF（pc） （1832KB）（66）       Knowledge map    Save A large amount of radioactive gas is generated during the reprocessing process in spent fuel reprocessing plants. The main forms of I-129 in the gaseous effluent of the reprocessing plants were investigated, and the current monitoring methods for radioactive iodine were summarized. By comparing their advantages and disadvantages, the online monitoring methods suitable for I-129 in the gaseous effluent of reprocessing plants were analyzed. And it is feasible to establish online monitoring technology for I-129 in the gaseous effluent in reprocessing plants. An ICP-MS based online monitoring technology for I-129 in the gaseous effluent in reprocessing plants could be established for experiemnt purpose, with the aim to monitoring the gaseous iodine molecules in the gaseous effluent in reprocessing plants, thereby achieving real-time monitoring of I-129 in the gaseous effluent in reprocessing plants. Reference | Related Articles | Metrics

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Research on the module structure design of simulation workplace neutron spectrum device based on DT neutron source LI Hui, LI Deyuan, YAN Xuewen, ZHANG Pengpeng, CHEN Faguo, LI Hua RADIATION PROTECTION    2023, 43 (3): 209-217.   Abstract （74）      PDF（pc） （7577KB）（43）       Knowledge map    Save Neutron dose is highly dependent on its energy. However, the energy spectrum of the calibration field is different from workplace, which could lead to a large deviation in the measurement of neutron dose at workplace. Using simulation workplace neutron spectrum for equipment calibration will improve the accuracy of neutron dose measurements. In this paper, the modular construction method of the simulated workplace neutron spectrum and the structural design method of the device were studied based on the DT neutron source, the simulated spectrum with the characteristics of workplace neutron spectrum at pressurized water reactors (PWR), and its fuel cycle. By analyzing the T(d, n)4He reaction emission neutron’s energy spectrum and angular distribution law, a point source with an average energy of 14.1 MeV Gaussian distribution and isotropic emission was used to approximate the DT neutron source. 14 alternative materials were selected according to the interaction cross-section of neutron and matter, the relative neutron fluence ratio and average neutron energy were analyzed. And the materials for constructing the simulation workplace neutron spectrum device were selected from the perspectives of neutron multiplication, energy attenuation, energy spectrum adjustment, and practicality. Two workplace neutron spectrum of the pump room and reactor hall were selected as target spectrum. Main moderation assembly, modulating layers and reflector assembly were designed. The simulated neutron spectrum and device structure for the two workplace target spectrum were constructed. The results show that the construction method of the simulated workplace neutron spectrum described in this paper is effective, and the modular design is highly expandable, which can be adapted to a variety of workplace target spectrum to construct the simulated spectrum. Reference | Related Articles | Metrics

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Electromagnetic exposure safety assessment of electrostatic discharge through numerical simulation SONG Yanxia RADIATION PROTECTION    2023, 43 (4): 289-299.   Abstract （73）      PDF（pc） （9240KB）（38）       Knowledge map    Save Based on the numerical calculation method on electromagnetic dosimetry and according to the typical electrostatic discharge (ESD) current waveform specified by IEC (International Electro technical Commission), the first harmonic component with the strongest energy and the full harmonic components in the frequency domain after Fourier transform were used as electromagnetic radiation sources, the electromagnetic effect of human biological tissue when the human body is located at different positions of the exposure source is simulated and analyzed, and the numerical simulation results were compared with those recommended by the International Commission on Non-Ionizing Radiation Protection (ICNIRP). The results showed that the electric field intensity (E), magnetic field intensity (H) and specific absorptivity (SAR) decreased with the distance from the exposure source, and the distribution of electric field lines became more uniform with the increasing distance; The electric field intensity attenuates rapidly after entering the head, and the brain has a certain shielding effect on the space electromagnetic field; The SAR peak values and distributions in coronal and sagittal planes are almost the same at different positions in the human head, and the SAR peak values in sagittal and coronal planes are 15.7 times of those in axial planes; The peak of head SAR at different positions appeared at the skull, and the SAR in the brain was the smallest and distributed symmetrically with respect to x and y; Under the condition of multi frequency exposure, the whole-body SAR value of the exposure source located at 1m (position A) on the right side of the human body exceeded the basic limit of ICNIRP, while the whole-body SAR value of the exposure source located at 5 m (position B) on the right side of the human body and beyond did not exceeded the basic limit of ICNIRP. The human body should be located 5 m away from the exposure source to reduce the exposure risk. The research results can provide a numerical reference for human ESD electromagnetic exposure protection, and can provide a theoretical basis for the formulation of ESD electromagnetic exposure related standards. Reference | Related Articles | Metrics

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Progress of research on electromagnetic radiation safety of implantable medical devices HE Diwei, CHEN Zhiying, TANG Danfeng, ZHANG Ying RADIATION PROTECTION    2023, 43 (3): 193-208.   Abstract （72）      PDF（pc） （15515KB）（49）       Knowledge map    Save Long-term or excessive exposure of the human body to electromagnetic radiation may cause some health effect. When medical devices are implanted into human body, the level of electromagnetic radiation exposed to human body will be increased. With the widespread application of implantable medical devices, the safety of electromagnetic radiation containing such devices cannot be ignored. Implantable medical devices often communicate with the outside world or have power supply wirelessly. On the one hand, its existence will change the electromagnetic field distribution of external radiation sources in hu-man tissues, which may increase the level of electromagnetic radiation; on the other hand, it is a radiation source itself and will generate electromagnetic radiation in human tissues. Many countries and international organizations use the specific absorption rate to measure the impact of electromagnetic radiation on the human body, and use it to formulate safety limits for electromag-netic radiation. This paper reviews domestic and foreign research on electromagnetic radiation safety in the communication and charging scenarios of implantable medical devices, and focuses on the electromagnetic field metrology methods, related models and influencing factors of electromagnetic radiation specific absorption rate research. Finally, the numerical calculation and ex-perimental measurement methods are discussed and compared, and the important factors affecting the specific absorption rate are analyzed, which will provide reference to the engineering design of parameters such as optimal operating frequency and power limit. Reference | Related Articles | Metrics

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An evaluation method of indoor radon exposure dose matrix caused by building materials XU Pengcheng, ZENG Zhi, MA Hao, SUN Bowen, LI Junli RADIATION PROTECTION    2023, 43 (3): 249-256.   Abstract （72）      PDF（pc） （926KB）（61）       Knowledge map    Save In order to make the evaluation of indoor radon exposure dose more systematic and universally applicable, an evaluation method of indoor radon exposure dose caused by building materials was established by using matrix. Based on indoor radon concentration model, personnel exposure dose estimation model and standards, four factors including radon exhalation rate of building materials, building structure size, indoor air exchange rate and personnel exposure time were combined in this method. The complex calculation under different conditions is converted into the matrices. Using this method, the radon exposure dose levels of indoor personnel under different air exchange rates and different exposure duration can be obtained. Taking a room with known size and known radon exhalation rate of building materials as an example, this method was used to analyze and evaluate the indoor radon exposure dose. The indoor radon exposure dose levels under different ventilation rates and exposure duration were quickly and simply obtained from reference table. Reference | Related Articles | Metrics

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RADIATION PROTECTION    2023, 43 (4): 390-392.   Abstract （71）      PDF（pc） （565KB）（53）       Knowledge map    Save Related Articles | Metrics

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Research on the influence of 56Fe evaluation cross section of different databases on shielding calculation CHI Xiaomiao, HAN Yi, CHEN Faguo, MA Xiangyu, SHEN Huaya RADIATION PROTECTION    2023, 43 (S1): 1-7.   Abstract （70）      PDF（pc） （5811KB）（32）       Knowledge map    Save 56Fe evaluation cross sections are still being updated at home and abroad. In order to evaluate the applicability and accuracy of 56Fe cross sections in various evaluation libraries and different versions of the same evaluation library in shielding calculation, this paper selects the FE DIA100 R150 benchmark with the evaluation the cross-section data quality of 56Fe in different evaluation libraries. And based on the CENDL-3.2 evaluation library, the sensitivity analysis of 56Fe stable isotopes was carried out, and the influence of key reaction channel sections of 56Fe on shielding calculation was studied. Some main conclusions are drawn as follows. 1) Due to the lack of accuracy of the elastic scattering cross section and inelastic scattering cross section of 56Fe, there are large differences between the calculated values of various evaluation libraries and the experimental measurements in the energy regions of 1.20-1.70 MeV and 10.00-17.00 MeV. 2) The (n, n) and (n, n′)d reaction cross-sections in 56Fe are the most sensitive factors to the influence of shielding calculations. 3) In CENDL-3.2, the cross section value of 56Fe(n, n) is higher than the real value in the energy region of 0.01-0.10 MeV. Reference | Related Articles | Metrics

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Study on monitoring method of automatic continuous sampling and analysis system for ultra-large flow aerosol CAO Longsheng, LIAO Yuhang, LV Anbiao, ZHOU Ying, ZHOU Feng RADIATION PROTECTION    2023, 43 (3): 235-242.   Abstract （67）      PDF（pc） （8502KB）（39）       Knowledge map    Save Due to different Placement decay time of aerosol samples, the detection limit of automatic continuous sampling and analysis system for ultra-large flow aerosol will be greatly affected. High detection limit may cause the fact that very low content of artificial radioactive substances in the air can not be detected. In order to develop an optimized and perfect monitoring method, this experiment studies natural radionuclides that mainly affect the background and their changes with the placement time, and further analyzes the changes of the detection limit of artificial radionuclides around nuclear facilities with sample placement time, by measuring the samples in different weather conditions for different placement time. The results show that for routine environmental monitoring, the samples on sunny day need to be placed for 2 days after collection; On rainy days, the collected samples shall be placed for 1 day before measurement; For emergency monitoring , direct measurement after sampling is required, the detection limit of sunny day samples are about 4-5 times of the minimum value and rainy day samples are about 2 times. It can be considered to measure the samples directly first and then conduct verification measurement after sufficient decay time. 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 （67）      PDF（pc） （2555KB）（75）       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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Evaluation of the application value of chromosome aberration and micro-nucleus analysis in occupational health surveillance of radiation workers HAN Lin, ZHAO Fengling, LIU Yulong, LYU Yumin RADIATION PROTECTION    2023, 43 (4): 366-371.   Abstract （66）      PDF（pc） （1229KB）（44）       Knowledge map    Save Application of chromosome aberration and micro-nucleus in peripheral blood lymphocyte as radio-sensitive biological indicators to biodosimetry was widely recognized by the international academia. Nevertheless some problems on the application value of the indicators are still worth discussing in occupational health surveillance of radiation workers. In this paper, based on the formation mechanism of chromosome aberration and micro-nucleus, the signification and practical value of the two indicators were explored in occupational medical examination of radiation workers, in order to provide discussion and a reference for the counterparts. Reference | Related Articles | Metrics

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Application of vehicle-mounted frequency-selection measurement in urban electromagnetic environment monitoring TANG Hui, GAO Peng, SU Kunpu, TANG Yanbo, XU Bin, GU Hong, LI Yuandong, MIAO Erkang RADIATION PROTECTION    2023, 43 (4): 311-317.   Abstract （66）      PDF（pc） （13840KB）（27）       Knowledge map    Save Objective: To measure the level of urban electromagnetic environment more efficiently and accurately and master the composition of electromagnetic environment. Methods: The DZER100 vehicle-mounted fast frequency selection measurement system was developed jointly with Chengdu Dot Matrix Technology Co., LTD. The full-band scanning time of the system was 300 ms under the condition of 30 MHz-6 GHz frequency band and 100 kHz resolution. With a driving speed of 60 km/h and a distance of 5 m between measuring points, the total field intensity, spectrum and electromagnetic environment of specific frequency band of each measuring point can be effectively obtained. Results: 14 393 effective point data were obtained for 5.3 km2 area. Through automatic analysis of system data, the average electric field intensity of the whole area was about 1.23 V/m, and the ratio of 0 V/m-2 V/m reached 87.411%. The average value of standard ratio was 1.41%, and only 0.24% of the sites accounted for more than 20%. Through the spectrum visualization analysis function, the spectrum composition of the focus point and the contribution of the focus frequency band can be quickly grasped. Conclusion: The vehicle-mounted frequency selection measurement (30 MHz-6 GHz) can realize the simultaneous measurement of the total field intensity and spectrum of each point, which effectively solves the remaining pain points caused by the use of non-frequency monitoring instruments. The obtained data amount is far more than that of the traditional grid measurement method, and the data are more representative, which can reflect the electromagnetic environment in the region more comprehensively. The vehicle-mounted frequency selection measurement can meet various requirements such as the measurement and evaluation of the overall level of regional electromagnetic environment and the analysis of the composition of the electromagnetic environment source terms, and provide more detailed and accurate basic data for the management of electromagnetic environment through visualized data. Reference | Related Articles | Metrics

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RADIATION PROTECTION    2023, 43 (S1): 0-0.   Abstract （65）      PDF（pc） （201KB）（54）       Knowledge map    Save Related Articles | Metrics

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Design of nuclear emergency assessment and decision support system for spent fuel reprocessing plant YANG Yapeng, ZHANG Jiangang, FENG Zongyang, JIA Linsheng, LIANG Boning, WANG Ning, XU Xiaoxiao RADIATION PROTECTION    2023, 43 (4): 353-359.   Abstract （64）      PDF（pc） （7484KB）（42）       Knowledge map    Save A nuclear emergency assessment system should be established to deal with the potential accidents such as criticality, radioactive material leakage, fire and explosion which could occur in spent fuel reprocessing plant. This paper introduces the design of a real-time three-dimensional visualization system for nuclear emergency assessment and decision support for five typical accidents in spent fuel reprocessing plant. The system is capable of diagnosising emergency conditions on real-time based on dynamic process monitoring data, calculating the source terms released into the plant and environment, carrying out emergency response process management based on emergency plan, and implementing protection action analysis for protecting staff and the public. The system can realize the dynamic display of emergency evaluation results and response process based on three-dimensional visualization technology. The system was developed for the emergency assessment and decision support of the spent fuel reprocessing plant, and will improve the emergency preparedness and response capacity. Reference | Related Articles | Metrics

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Practice and consideration on clearance of very low level radioactive contaminated material XU Kan, XIONG Kouhong, YAN Xiaojun, GUO Xiliang, XU Chunyan, GAO Chao RADIATION PROTECTION    2023, 43 (4): 360-365.   Abstract （64）      PDF（pc） （1021KB）（66）       Knowledge map    Save Based on the analysis of clearance practice of very low level radioactive contaminated material in recent years and the analysis of the latest description of IAEA on the applicability of clearance concept, some considerations on the clearance management of radioactive contaminated material arising from domestic NPPs are put forward. Reference | Related Articles | Metrics

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An ignored radiation exposure source term in nuclear power plants GU Jingzhi RADIATION PROTECTION    2023, 43 (5): 438-442.   Abstract （64）      PDF（pc） （967KB）（50）       Knowledge map    Save Noble gas is a kind of radioactive material produced in nuclear fission processes of a nuclear power unit. Nevertheless such radiation source term and its exposure risk to workers of nuclear power plants during specific conditions has been neglected, due to its physical form and charachteristics as well as the difficulties of exposure dose measurement technology. This paper calls for attention to the professional radiation staffs of nuclear power plants to make further efforts to identify those specific radiation risks existed inside the nuclear power plant and then to control and reduce the source terms and their exposure risks. Reference | Related Articles | Metrics

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Investigation on KAP of radiation protection among medical staff in nuclear medicine department and analysis of influencing factors WANG Mengting, YANG Suyun, SHI Bingzi RADIATION PROTECTION    2023, 43 (5): 501-509.   Abstract （64）      PDF（pc） （1082KB）（33）       Knowledge map    Save Objective: To investigate knowledge, attitude and practice of radiation protection among medical staff in nuclear medicine department and to analyze the influencing factors, so as to provide the basis for standardizing the radiation protcetion behavior of medical staff and enriching the training content of radiation protection. Methods: A self-designed questionnaire on KAP of radiation protection was used to investigate the medical staff in nuclear medicine department, and multiple linear regression was used to analyze the factors affecting KAP of radiation protection. Results: A total of 123 valid questionnaires were collected, and the effective recovery rate was 94.62%. The total score of the radiation protection KAP questionnaire for medical staff in nuclear medicine department is 76.92; the knowledge score is 57.69; the attitude score is 95.24; and the behavior score is 83.33. The results of multiple linear regression analysis showed that if medical staff had children and whether they regularly attended radiation protection training were the influencing factors of radiation protection KAP score (P<0.05). Conclusions: Medical staff in nuclear medicine department have a good level of KAP about radiation protection, and their attitude and behavior are positive, but their knowledge of radiation protection is insufficient. Relevant organizations and agencies should regularly organize radiation protection training and education, in order to improve medical staff's knowledge level of radiation protection, and form positive attitudes and behaviors. Reference | Related Articles | Metrics

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Suggestions on standardizing collective dose data management of nuclear power plants in China WANG Liang, HUANG Qianqian, YE Yuanlv, LIU Zhiyuan, CHEN Lu, LIU Fudong RADIATION PROTECTION    2023, 43 (S1): 39-43.   Abstract （62）      PDF（pc） （1031KB）（52）       Knowledge map    Save At present, the in-service nuclear power plants in China are relatively insufficient in dose data collection, statistics, standardized classification management, information publicity and so on. There is a low degree of standardization and normalization of dose data between different reactors in the same nuclear power base or even between different refueling cycles of the same unit, which leads to poor data comparability and is not conducive to achieving the requirements of radiation safety optimization. Based on the practice of domestic and foreign nuclear power plant dose data management, the deficiencies and problems of collective dose data management in Chinese nuclear power plants have been analyzed, and a number of suggestions were put forward. 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 （59）      PDF（pc） （962KB）（50）       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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An investigation of the authorized release limits of radioactive effluent from nuclear power plant HUANG Yanjun, SHANGGUAN Zhihong, ZUO Weiwei RADIATION PROTECTION    2023, 43 (5): 431-437.   Abstract （58）      PDF（pc） （3557KB）（37）       Knowledge map    Save Emission control plays a key role in environmental radiation protection and effluent management for the operator of nuclear power plants (NPPs) and the authorities. In this paper, the effluent emission levels of pressurized water reactor (PWR) NPPs at home and abroad, the contain rate of the emission control value stipulated in GB 6249—2011 were investigated for the reported release amount, and the regulated values were compared with that in France. It was shown that, except for 3H and 14C in the effluent, the existing regulatedemission limits could basically contain the statistical emissions of foreign nuclear power plants with a much large controllable margin. Under the current effluent emission management level, a suitable, and much controllable margin could be used for optimization for the limits except for 3H and 14C. Reference | Related Articles | Metrics

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A study of 7Be, 210Pb and 210Po in the atmosphere of Tianjin and the committed effective dose from 2018 to 2020 CUI Ming, YU Chuan, GAO Jianzheng RADIATION PROTECTION    2023, 43 (5): 495-500.   Abstract （58）      PDF（pc） （1156KB）（28）       Knowledge map    Save In order to study the activity concentration and to estimate the committed effective dose through inhalation of 7Be, 210Pb and 210Po in the atmospheric aerosols of Tianjin, TSP samples from 2018 to 2020 were analyzed. Activity concentrations of 7Be,210Pb and 210Po in TSP were in the range of 0.74-15.0 mBq/m3, 0.21-2.5 μBq/m3 and 0.17-0.74 μBq/m3, respectively. The activity concentrations of three radionuclides were at highest in winter. This is the combined effect of the airflow from high latitudes and the increased pollution emission in winter season in Tianjin. The total committed effective dose caused by 7Be, 210Pb and 210Po was in the range of 6.28-40.1 μSv/a, which was far lower than the dose limits for public exposure and not enough to threaten human health. Reference | Related Articles | Metrics

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Carcinogenic effect of tritium water on mice or rats: A systematic review and Meta analysis XU Kai, LI Mei, WANG Chunping, LU Haili, SHAN Wenping, QIN Xiujun RADIATION PROTECTION    2023, 43 (4): 372-383.   Abstract （56）      PDF（pc） （2409KB）（27）       Knowledge map    Save A systematic review and meta-analysis were used to explore the relationship between exposure to tritium water (HTO) and carcinogenic effect in rats or mice. Database such as PubMed, Embase, The Cochrane Library, Web of Science, CNKI, China Biomedical Literature Database, Wanfang, and VIP were searched with computer. Literature regarding carcinogenicity of rats exposed to tritium water was searched for experimental studies that met the inclusion criteria, with time frame from the establishment of the aformentioned databases to February 15th 2021. Literature was managed by using Endnote 9.2. Toxicological data reliability evaluation tool ToxRTool was used to evaluate the quality of the literature. A total of 10 experimental studies were included. Among them, 4 articles reported the malignant transformation experiment in vitro and 7 articles reported the experiment in vivo. For the in Vitro cases, the cell Surviving Fraction decreased exponentially with the increase of radiation dose. The equation was lnSF = 0.047-0.270 D (P<0.001), R2=0.850. Taking the radiation dose of cells as the independent variable and the malignant transformation fraction (foci/dishes) as the dependent variable, the fitting equation was y=0.205+0.195x (P<0.001), R2=0.853; Meta-analysis of dose-response relationship showed that the risk of malignant transformation of cells increased rapidly at first and then increased slowly with the increase of radiation dose. For the in Vivo cases, the increase of the activity of intraperitoneal injection resulted in a decrease of median or average survival time. Tritium water (HTO) has a definite carcinogenic effect on both cells and animals and leads to the decline of life quality. However, the carcinogenic effect of very low dose tritium water exposure needs further study. Reference | Related Articles | Metrics

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Monitoring and research of long pulse radiation in EAST fusion device LI Chengxun, HUO Zhipeng, ZHONG Guoqiang, HU Liqun RADIATION PROTECTION    2023, 43 (5): 451-459.   Abstract （56）      PDF（pc） （4608KB）（39）       Knowledge map    Save EAST(Experimental Advanced Superconducting Tokamak) conducts plasma fusion by deuterium and deuterium, which releases large amounts of neutrons and secondary gamma rays. In order to accurately understand the spatial distribution of radiation products in the EAST fusion device under the condition of high parameter long pulse plasma discharge, the radiation on-line monitoring system is used to realize the effective monitoring of neutron and γ rays. According to protection requirements, 13 key monitoring areas are arranged inside and outside the EAST installation hall. In terms of monitoring system hardware, radiation neutrons and γ rays are detected by ionization chamber based on BF3 proportional counter tube and argon respectively, and monitoring data are transmitted to acquisition machine through twisted pair and Ethernet hybrid networking mode. The monitoring system software adopts the control acquisition software based on LabVIEW to collect and store the real-time dose rate and cumulative dose of neutron and gamma rays. The monitoring results show that the maximum radiation dose rate in the hall of the EAST fusion device rapidly increases by more than 3 orders of magnitude under the long pulse and high parameter plasma operation condition, and then drops to the radiation background level soon after the discharge. The radiation dose rate outside the hall is always kept close to the radiation background level due to the protective effect of the shielding wall. The online radiation monitoring system can not only effectively obtain radioactive data, but also provide data support for radiation safety protection management to ensure the safe development and utilization of fusion energy and personnel safety. Reference | Related Articles | Metrics

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RADIATION PROTECTION    2024, 44 (1): 0-0.   Abstract （56）      PDF（pc） （190KB）（59）       Knowledge map    Save Related Articles | Metrics

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Effects of ionizing radiation on the development of cerebellum and prefrontal cortex in mice during neonatal period WANG Yangyang, LIU Yuanduo, LIU Lian RADIATION PROTECTION    2023, 43 (3): 271-279.   Abstract （55）      PDF（pc） （14831KB）（16）       Knowledge map    Save To investigate the effects of X-ray on the development of cerebellum and prefrontal cortex in mice during neonatal period, the mice in irradiation group were irradiated with whole-body X-ray dose of 2 Gy (2 Gy/min) at the postanal day 3(PD 3). Irradiated mice were euthanized at 7, 21 and 90 days after irradiation (PD 3+7, PD 3+21, PD 3+90) and brain samples were collected for different experimental studies. Hematoxylin-eosin (HE) was utilized to detect the pathomorphological changes of brain tissue; Immunohisto-chemistry were used to detect the protein expression of IBa1 and GFAP; Western blotting were used to detect the protein expression of IL-1β and TNF-α. In the irradiation group, the inflammatory cell infiltration was observed in the cerebellum and prefrontal cortex, and the thickness of external granular layer (EGL) narrowed. Purkinje cells migrated to internal granular layer (IGL) and some cells were lost in the cerebellum. Compared with the control group, the number of IBa1 positive cells increased at 21 days after irradiation (p<0.05), while the number of GFAP positive cells decreased at 7 days after irradiation in cerebellum (p<0.05). The number of IBa1 positive cells continued to increase until adulthood (p<0.05, p<0.01), and the number of GFAP positive cells continued to decrease until adulthood in prefrontal cortex (p<0.01). The protein expression of IL-1β increased at 90 days after radiation in cerebellum and prefrontal cortex (p<0.05), while the expression of TNF-α did not change. Neonatal exposure to 2 Gy X-ray caused continuous pathological changes in the granulosa cell layer, molecular layer and Purkinje cell layer of cerebellum, and inflammatory cell aggregation in the prefrontal cortex. Neonatal exposure to 2 Gy X-ray increased the number of microglia in the prefrontal cortex and cerebellum, decreased the number of astrocytes. IL-1β is mainly the inflammatory factor. Reference | Related Articles | Metrics

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Review of radiation epidemiology, dosimetry and radiobiology in areas with high natural background radiation areas of the world XUE Huiyuan, GAO Jin, TU Yu RADIATION PROTECTION    2023, 43 (S1): 129-138.   Abstract （55）      PDF（pc） （1168KB）（22）       Knowledge map    Save Radiation levels therefore vary from one region of the world to another. Naturally occurred high background radiation areas, due to the uniqueness of their radiation doses and the populations that inhabit, has always been attracting the attention of researchers from different countries. Early epidemiological studies did not show an increasing trend in cancer incidence in high natural background radiation areas, raising some controversy about the validity of the linear non-threshold hypothesis. This paper presents and discusses the main results of radioactivity level measurements, radiobiological and radiation epidemiological studies conducted in some of the major areas with high natural background radiation areas of the world, such as China, Brazil, India and Iran. It is hoped that research interest will be aroused in the topical issues of dosimetry, epidemiology and radiobiology related to the high natural background radiation areas of the world. Recommendations to address the problems faced at this stage, in order to achieve better research related to high natural background radiation areas. At the same time, the inhabitants of high natural background radiation areas are protected from possible radiation exposure. Reference | Related Articles | Metrics

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Inter-comparison results of 137Cs and 90Sr in seawater among analytical laboratories LIN Jing, HUANG Dekun, NI Jialin, JI Jianda, ZHONG Qiangqiang, ZHANG Jinzhao, YU Tao RADIATION PROTECTION    2023, 43 (5): 485-489.   Abstract （55）      PDF（pc） （1803KB）（16）       Knowledge map    Save Inter-comparison results among analytical laboratories for the measurements of 137Cs and 90Sr in seawater in 2020 is described in this paper. The spiked seawater samples were distributed to 13 participating laboratories, and their analytical results were compared to the reference values. The relative deviation of 137Cs between measured values and reference value was -2.99% to 5.97%. The results had passed all criteria and were assigned “Accepted” status as a final score. In the case of 90Sr, one measured result did not pass the accuracy test and correctness test, so it was considered as “Not Accepted”. All other results were accepted. The analytical laboratories participating in this inter-comparison have good overall comparison results. Reference | Related Articles | Metrics

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Radiation risk control of radiograph flaw detection by using multiple radioactive source of in the reactor building during the overhaul of the HPR1000 unit XU Zhuoqun, JIANG Zhiyuan, TIAN Qiuxin RADIATION PROTECTION    2023, 43 (S1): 44-51.   Abstract （54）      PDF（pc） （14025KB）（23）       Knowledge map    Save Radiograph flaw detection is one of the non-destructive testing methods widely used in nuclear power plants. Due to the high activity of the radioactive source to be used, if the inspection operation or management is improper, it may lead to radiation incidents or radiation accidents. This paper, based on HPR1000 unit design layout and first overhaul practice, upholds the reactor building multiple radioactive source of radiograph flaw detection risk control idea, innovatively designed a “three-step” code, combined with the judgment logic of independent research and development, in order to ensure the safe and efficient implementation of multiple radioactive source of radiograph flaw detection in the reactor building during the overhaul of HPR1000 unit. The results could provide support to improve the domestic and foreign control system in the field of radiation protection, and provide experience feedback for the same type of units at home and abroad. Reference | Related Articles | Metrics

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Calculation and regulation of radon and radon progeny concentration in uranium mine ventilation network YE Yongjun, ZHANG Yingpeng, CHEN Daijia, ZHANG Xiaoyu RADIATION PROTECTION    2023, 43 (3): 257-264.   Abstract （54）      PDF（pc） （3069KB）（30）       Knowledge map    Save The radiation dose received by workers in uranium mines mainly comes from radon and radon progeny. In order to reduce the radiation dose caused by radon in uranium mine, it is necessary to provide sufficient and reliable radon reduction air volume to the underground on the basis of ensuring the air quality. Therefore, according to the ventilation network calculation theory, radionuclide decay theory and turbulent mass transfer theory, the calculation model of radon and radon progeny concentration in ventilation network is established. Using MATLAB software, according to the proposed model, the radon and radon progeny concentration distribution in the specific branch of a hard rock uranium mine is calculated and analyzed. The results show that: 1) the solution model can analyze the radon and radon progeny concentration of single branch, multi branch and ventilation network with local radon source; 2) According to the protection requirements against radon and radon progeny, the branch with the concentration of radon and radon progeny exceeding the limit can be judged, and the optimal air volume of radon and radon progeny reduction as well as the wind pressure of fan operation can be calculated by air volume adjustment method when the corrected air volume is small. Reference | Related Articles | Metrics

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Preliminary study on combustion release behavior of tributyl-phosphate/kerosene in nuclear fuel cycle LIAN Yiren, SUN Hongchao, YANG Hao, SONG Xiaopeng, ZHUANG Dajie, SUN Shutang, WANG Changwu, CHEN Lei, YANG Xinjing, SUN Qian, XU Xiaoxiao, WANG Pengyi, LI Guoqiang, ZHANG Jiangang RADIATION PROTECTION    2023, 43 (4): 336-342.   Abstract （53）      PDF（pc） （8040KB）（19）       Knowledge map    Save The combustion of tributyl-phosphate/kerosene is a typical fire accident in nuclear fuel cycle facilities, and it is an important research content of nuclear fuel cycle safety that cannot be ignored. In this paper, a preliminary study on the solvent fire accidents (combustion area 77.9-2 921.0 mm2) was carried out. The combustion rate of the solvent, the release components of gases, the release of aerosols and their particle size distribution were analyzed by basic experiments. And the differences between experimental results with the published foreign data were analyzed. Reference | Related Articles | Metrics

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Study on the application of uncertainty analysis technology in safety assessment of an environmental protection supporting project LIU Xingwei, WANG Xuhong, LV Tao, LI Xingyu, LI Chang, KANG Baowei, WANG Xin, XIA Jiaguo RADIATION PROTECTION    2023, 43 (4): 325-335.   Abstract （53）      PDF（pc） （11236KB）（31）       Knowledge map    Save In order to solve the uncertainty problem (caused by cognitive level and long time scale) of safety assessment results for radioactive waste disposal, this study, based on an environmental protection supporting project, first carried out deterministic model safety assessment, and then generated 1 000 samples based on probability theory method and Latin hypercube sampling technology to carry out uncertainty analysis and sensitivity analysis. The results show that the calculation results of near-field release rate of deterministic model are high, that of geosphere is fit, and that of Mo-93 and Ni-59 is good, and that of I-129 is low in biosphere. The results of sensitivity analysis show that the parameters related to concrete materials (such as effective diffusion coefficient of concrete, distribution coefficient of nuclide in concrete, thickness of concrete barrier), leaching rate of waste, initial activity and distribution coefficient of nuclide in geosphere are the main influencing parameters of model release rate peak value, which can be treated as the key parameters for subsequent engineering design and field investigation. Reference | Related Articles | Metrics

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RADIATION PROTECTION    2023, 43 (4): 317-317.   Abstract （53）      PDF（pc） （564KB）（35）       Knowledge map    Save Related Articles | Metrics

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Development of directional dose equivalent rate meter for emergency radiation protection WEI Yingjing, WU Zhifang, LIU Liye, LI Yin, WEI Shiliang, YAN Jun RADIATION PROTECTION    2023, 43 (5): 467-472.   Abstract （53）      PDF（pc） （3843KB）（29）       Knowledge map    Save In order to accurately measure the H'·(0.07) under emergency conditions, a directional dose equivalent rate meter for emergency radiation protection is developed. The detector conta: 2 layers 3 μm alumini polyester film, a diameter of 35 mm Plastic scintillators with thickness of 50 μm, plexiglass with a thickness of 5 mm, and SiPM. They were used as the front window, scintillator, photoconductive and photoelectric converter of the detector in turn. According to GB/T 4835.2—2013, the radiation characteristics of the developed directional dose equivalent rate meter for emergency radiation protection are as follows: the relative intrinsic error is -14% to +20% in the dose rate range of 70 μSv/h-1.7 Sv/h; With the incident angle from 0 to ±60°, and the β ray average energy of 60 keV-800 keV, the variation of radiation energy and incident angle is in the range of -16% to +48%; in the radiation field of 0.23 mSv/h, the statistical fluctuation of the measurement results is 8.4%. The test results show that the radiation characteristics of the directional dose equivalent rate meter for emergency radiation protection meet the requirements of GB/T 4835.2—2013, and can be used for directional dose equivalent rate monitoring in places with high weak penetrating radiation and emergency conditions. Reference | Related Articles | Metrics

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2019-2020 radon concentration measurement and dose estimation in some non-uranium mines in China WU Yunyun, SONG Yanchao, ZHANG Qingzhao, CUI Hongxing, HOU Changsong RADIATION PROTECTION    2023, 43 (S1): 61-66.   Abstract （52）      PDF（pc） （1259KB）（38）       Knowledge map    Save In 2019-2020,75 non-uranium mines in 11 provinces (autonomous regions) were selected and investigated. Solid State Nuclear Track Detector was used to measure the radon concentration in mines. The arithmetic mean (AM) of radon concentration in metal mines was (1 334 ±3 301)Bq/m3, the geometric mean (GM) of them was (317± 4.6) Bq/m3, ranging from 22 to 28 314 Bq/m3(N = 416). The AM and GM in non-metal mines was (162±151) Bq/m3 and (125±2) Bq/m3, respectively, with range of 22-971 Bq/m3 (N=113). There was 31.8% of the 529 underground measuring points with radon concentration exceeding 300 Bq/m3, 19.8% of measuring points exceeding 1 000 Bq/m3 and 9.3% exceeding 2 700 Bq/m3. There were 21 metal mines with radon concentration exceeding 1 000 Bq/m3, accounting for 28% of the total surveyed mines. The average annual effective dose of metal miners was 8.38 mSv, and that of non-metal miners was 1.01 mSv. It can be seen that the problem of high radon concentration in metal mines is very prominent. It is suggested that the protection of ventilation engineering should be strengthened in metal mines, and the monitoring of radon in the workplace and individual dose of radon in miners should be implemented. Non-uranium mines should be managed by classification of radon. Reference | Related Articles | Metrics

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Analysis on the interference of carbon-14 on tritium monitoring in gaseous effluent BAO Li, YANG Youkun, LIAN Bing, GUO Chen, MA Xuyuan, YANG Hailan RADIATION PROTECTION    2023, 43 (S1): 52-55.   Abstract （51）      PDF（pc） （2581KB）（25）       Knowledge map    Save Tritium is an important radionuclide in gaseous emissions from nuclear facilities. As a low-energy pure β radionuclide, tritium is mostly monitored by cumulative sampling and laboratory analysis. After tritium is sampled in airborne effluent and measured without purification, there may be interference from other radionuclides. The interference of carbon-14 in airborne effluent on tritium measurement is quantitatively analyzed, which provides reference for accurate and quantitative monitoring of tritium in airborne effluent. According to the sampling characteristics of tritium and carbon-14, the interference in the sampling stage is determined, and the mono-nuclear and tritium-carbon double-labeled samples are prepared and measured to determine the interference effect of carbon-14 on tritium measurement stage. In the sampling stage, the influence of carbon-14 on tritium varies with the temperature, and the solubility of CO2 in tritium capture solution is 0.70 g at 10 ℃. In the measurement stage, the influence of carbon-14 on tritium will vary according to the design and working principle of liquid scintillation spectrometer. For example, if Quantulus1220 ultra-low level liquid scintillation spectrometer is used, the counting contribution of carbon-14 can not be ignored in tritium measurement mode; If LSA2000A liquid scintillation spectrometer is used, the counting contribution of carbon-14 can be ignored in tritium measurement mode. 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 （51）      PDF（pc） （3552KB）（30）       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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The weakly penetrating radiation dose measurement of surface of uranium fuel element surface and operator CHEN Bin, WEI Yingjing, AN Shifeng, WANG Yuqing RADIATION PROTECTION    2023, 43 (5): 473-477.   Abstract （50）      PDF（pc） （1273KB）（30）       Knowledge map    Save Along with β radiation of 238U and 235U dacay in uranium fuel. Existing, weakly penetrating radiation risk ofto operator of uranium fuel element exists. TIn this article,measuring the β spectrum was measured with β spectrometer and measuring the β dose rate was measured with directional dose equivalent meter,T, while the maximum energy of beta ray emitted from uranium fuel element is 2.3 MeV. The measurement results show that the $\dot{H}$'(0.07) is 1.38 mSv/h, and the $\dot{H}$'(0.07)/$\dot{H}$*(10) is 36. The experimental results show that the protective clothing worn by the uranium fuel element operators has almost no protective effect on high-energy β rays, and the Hp(0.07)/Hp(10) is 130. AccordingBased on the measurement results of uranium fuel element and operator, it is suggested monitoring Hp(0.07) and Hp(3) for the operator of uranium fuel element. At the same time,, the weakly penetrating radiation protectiveon methods were provided. Reference | Related Articles | Metrics

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RADIATION PROTECTION    2023, 43 (3): 0-0.   Abstract （49）      PDF（pc） （175KB）（33）       Knowledge map    Save Related Articles | Metrics

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Investigation and analysis of natural radionuclides content in coal used for power generation in China WANG Shaolin, CHEN Ling, BAI Xiangfei, TUO Fei, CHEN Faguo, CAO Zhonggang RADIATION PROTECTION    2023, 43 (5): 478-484.   Abstract （49）      PDF（pc） （1041KB）（34）       Knowledge map    Save Based on the analysis of the data obtained from coal mines and related literature, it is found that in 2013, the natural radionuclide content of 238U, 226Ra, 232Th, 40K, 210Po, and 210Pb for coal samples is 29.2±2.9 Bq/kg, 25.2±2.1 Bq/kg, 26.9±0.1 Bq/kg, 64.0±0.6 Bq/kg, 20.7±0.2 Bq/kg and 24.6±0.3 Bq/kg respectively based on weighted average of annual production; while the natural radionuclides content for coal samples is 33.9±9.7 Bq/kg, 30.9±7.9 Bq/kg, 28.5±4.2 Bq/kg, 79.7±20.4 Bq/kg, 26.8±4.3 Bq/kg and 33.9±7.7 Bq/kg respectively based on the weighted average of coal mine scale. The results of this survey can provide basic data for a comprehensive evaluation of the radioactive impact of Chinese coal power industry chain on the natural radioactive level of coal power generation. Reference | Related Articles | Metrics