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Table of Content

    15 August 2023 Volume 43 Issue S1
      
    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 (5811KB) ( 32 )  
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    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.
    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 (3533KB) ( 47 )  
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    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.
    The decay heat calculation and key factors study on spent fuel storage and transportation system of third generation nuclear power plant
    WANG Mengqi, PENG Chao, LI Hui, ZHEN Zheng, MEI Qiliang
    RADIATION PROTECTION. 2023, 43(S1):  14-19. 
    Abstract ( 43 )   PDF (2617KB) ( 20 )  
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    In this paper, based on the spent fuel assembly from the third generation passive nuclear power plant, a comparative study on the decay heat calculation based on ANS 5.1—2005 and ORIGEN-S was carried out. The variation of decay heat of fission products and actinide nuclides under different cooling times is analyzed in detail. The results show that the contribution of actinide nuclides to the total decay heat of spent fuel with cooling time of more than 5 years is close to 20% or even higher, and the main contributions of actinide nuclides are from Cm-244, Pu-238 and Am-241. ANS 5.1—2005 only considers U-239 and Np-239 for actinide nuclides. For the spent fuel storage system with long cooling time, the calculation of decay heat by ANS 5.1—2005 is not conservative. It is suggested that special programs such as ORIGEN-S should be used to calculate the decay heat for the third generation passive NPP spent fuel storage and transportation system.
    Benchmark analysis of shutdown dose rate calculation program based on R2S method
    ZHANG Xian, LIU Shichang, LU Peng, ZHANG Xiaokang, QUAN Guoping, CHEN Yixue
    RADIATION PROTECTION. 2023, 43(S1):  20-24. 
    Abstract ( 39 )   PDF (2938KB) ( 7 )  
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    Based on the lattice counting function of the Monte Carlo program cosRMC, this paper developed a shutdown dose rate calculation program with a strict two-step method as the core. Through coupling particle transport calculation and activation analysis calculation, the shutdown dose field was accurately obtained. The ALARA program was used to carry out activation analysis and calculation. In this paper, the program is applied to the calculation benchmark of ITER diagnostic window, and a full calculation analysis is carried out, which is in good agreement with the shutdown dose rate results calculated by other programs. In order to improve the efficiency of particle transport calculation, the parallel calculation method and the global weight window variance reduction algorithm are applied in the program calculation. In addition, due to the fusion device geometry is complex, the lattice structure is difficult to accurately describe the geometric structure, a lattice often contains more than one cell, at this time of the lattice flux average to shut down the accuracy of dose rate will bring bad effect, rather than the lattice structure has a good adaptability, geometry, therefore, this work is based on unstructured lattice made further development program for shutdown dose rate, The reliability of the program for calculating shutdown dose rate based on unstructured lattice was verified.
    Numerical simulation of complex thermoluminescence glow curve analysis by step annealing
    JI Yunlong, LI Dawei, ZHANG Yuxin, WANG Xiaoning, NING Jing
    RADIATION PROTECTION. 2023, 43(S1):  25-32. 
    Abstract ( 38 )   PDF (8207KB) ( 11 )  
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    In the dynamic analysis of thermoluminescence, it is common to encounter the glow curve with multiple peaks overlapped to some extent. Step annealing method uses pre-heating to gradually remove the influence of low temperature peak components, and to achieve the separation of multiple peaks to a certain extent, which plays an important role in the analysis of complex glow curve. In this paper, MatLab program is used to simulate the glow curves under various conditions according to the first-order dynamic model, and the step-annealing method is used to simulate the glow curves during the secondary heating after the process of pre-heating and rapid cooling. The initial rising slope of the glow curve of secondary heating is analyzed, and the activation energy (trap depth) is obtained. The calculated results are in good agreement with the pre-set dynamic parameters.
    Effects of abnormal environmental factors on thermoluminescence dosimeter
    HUANG Ming, ZHANG Hui, KANG Ning, HU Yuxin, HOU Lina, WANG Bing, ZHU Guoping, DENG Yanli
    RADIATION PROTECTION. 2023, 43(S1):  33-38. 
    Abstract ( 40 )   PDF (1074KB) ( 18 )  
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    In order to ensure the accuracy of personal dose measurement, study on the change of relative response of TLD2000C LiF(Mg,Cu,P) thermoluminescence dosimeter (TLD) under the influence of abnormal environmental factors was conducted. Performance experiment in the conditions of normal and abnormal environmental factors, such as high temperature and high humidity, water immersion and high electromagnetic radiation, and the difference of relative responses of TLD between different environmental factors were analyzed. The change of relative response of TLD is about -7% under high temperature and high humidity conditions, and The effect of short time immersion and high electromagnetic radiation environment on the relative response of TLD is very little. High temperature and high humidity environment will produce minus change to the relative response of TLD, therefore attention should be paid in the process of use, storage and transportation. Short time immersion or rain fall has little effect on the relative response of TLD. The experimental results have good reference value. TLD can be read and used normally when placed in high electromagnetic radiation environment.
    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 (1031KB) ( 52 )  
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    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.
    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 (14025KB) ( 23 )  
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    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.
    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 (2581KB) ( 25 )  
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    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.
    Study on measuring radon exhalation rate of building materials by activated carbon box method
    LIU Shubo, MEI Aihua
    RADIATION PROTECTION. 2023, 43(S1):  56-60. 
    Abstract ( 37 )   PDF (3612KB) ( 15 )  
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    In this paper, the surface radon exhalation rate of autoclaved aerated blocks and concrete blocks was measured with activated carbon box method. The influence of sampling time and sample sealing method on the measurement results was studied. The experimental results show that different sealing materials have some influence on the experimental results, but there is no significant difference. The density of concrete blocks is high, the specific activity of radionuclides is much higher than that of autoclaved aerated blocks, and the radon excrete rate is relatively high. In practice, the results of surface precipitation of autoclaved blocks vary greatly with sampling time, while the results of concrete blocks are relatively stable. In summary, the activated carbon box method has the advantage of low cost, convenient operation and easy to use in large quantities, and has strong practicability for engineering testing.
    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 (1259KB) ( 38 )  
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    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.
    Discussion on the designated value of proficiency testing sample based on the agreed value of participants
    WANG Ruijun, BAO Li, LI Pengxiang, SONG Qinnan, MA Xuyuan, YANG Youkun, LI Zhou, GAO Zequan
    RADIATION PROTECTION. 2023, 43(S1):  67-70. 
    Abstract ( 41 )   PDF (1402KB) ( 9 )  
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    Proficiency testing is an important means of laboratory quality assurance. The determination of the specified value of proficiency testing samples could affects the accuracy of the evaluation of proficiency testing results directly. It is a common method to determine the specified value by using the agreed value of participants. The accuracy of this method is limited by the number of participants. When the number of participants is small, the uncertainty of the specified value determined by this method is large. If the number of participants is too small, it can not even determine the result of proficiency testing.
    Research on irradiation damage effect of radioluminescent materials in radioluminescent nuclear battery
    XU Zhiheng, LIANG Dongdong, WU Yishui, JIANG Tongxin, TANG Xiaobin
    RADIATION PROTECTION. 2023, 43(S1):  71-77. 
    Abstract ( 47 )   PDF (8138KB) ( 9 )  
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    Radioluminescent nuclear batteries have unique advantages such as compactness, miniaturization, and a wide range of transducer materials to choose from, and are regarded as a typical representative of radiation-particle-conversion nuclear batteries. Fluorescent material is the key link that affects the performance of the battery, and its irradiation stability is a prerequisite to ensure that the battery can serve efficiently for a long period of time. Based on this, ZnS:Cu, a typical material in radioluminescent nuclear batteries, was selected for the study. The changes in luminescence properties of ZnS:Cu radioluminescent materials after irradiation with different types and intensities of ray particles were emphasized. The changes of parameters such as irradiated fluorescence spectra, luminescence intensity, and the influence laws of fluorescent materials before and after irradiation on the electrical output performance of the corresponding nuclear batteries were compared. The irradiation resistance of the ZnS:Cu fluorescent layers was tested and investigated to be relatively good, and the peak light intensity of its emission spectrum was only attenuated by 15.23% and 13.94% compared with that of the unirradiated one after being irradiated by protons at 200 keV and 1.25×1014 ions/cm2 and electrons at 100 keV and 4.32×1016 e/cm2, respectively. It was also found that the irradiation damage effect causes radioluminescent intensity decay, which is intrinsic to the degradation of the electrical performance of the battery. And a certain intensity of gamma irradiation can promote the irradiation luminescence performance of ZnS:Cu fluorescent layer. Among them, the ZnS:Cu fluorescent layer based on acrylic thin film was subjected to gamma irradiation with an irradiation dose of 871.0 kGy, and the maximum output power of the corresponding nuclear battery was enhanced by 24.59%. This work has positively contributed to the research on irradiation stability assessment and performance optimization of fluorescent materials and related devices.
    Helium permeability in rubber rings during container leakage testing
    WANG Pengyi, ZHUANG Dajie, CHEN Lei, SUN Hongchao, LI Guoqiang
    RADIATION PROTECTION. 2023, 43(S1):  78-83. 
    Abstract ( 35 )   PDF (2720KB) ( 9 )  
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    The O-ring sealing rubber is usually used in container for radioactive material transport to achieve the containment of the contents and air-tightness requirements. Among the quantitative gas-leakage testing methods, the most commonly used one is gas filled envelope or evacuated envelope method by using helium as the tracer gas and helium mass spectrometer as the gas detector. During leakage testing, in addition to helium leakage caused by cracks or defects between the cap and the O-ring, helium will also permeate through the O-ring to the side with smaller pressure, thus interfering with the true leakage rate. The helium permeation process goes through three processes: dissolution, diffusion and desorption. The permeability of rubber is composed of dissolution and diffusion coefficient. Both of them can be affected by the type of gas, rubber and environmental temperature. Actually, the leakage rate caused by helium gas permeation is also affected by the pressure difference, exposed area, thickness, compression rate of rubber and the existence time of pressure difference, etc. This paper proposes a gas filled envelope method using helium mass spectrometer as gas detector, hoping to decrease the existence time of pressure difference, which can be used in quantitatively testing for sealed containers. Testing is divided into six steps: qualitative leakage detection of pipeline connection systems, background characterization before measurement, measuring instrument calibration before measurement, the actual leakage rate measurement, measuring instrument calibration after measurement and background characterization after measurement. Obvious helium permeation has been observed after helium is pumped into the envelope 8 minutes later during the delivery inspection of a container, and the leakage rate reaches 1.2×10-7 Pa·m3/s. After replacing the contaminated O-ring, this method is used to test the same container again. As a result, helium permeation is largely reduced and the leakage rate goes down to 7×10-10 Pa·m3/s.
    Study and practice on nuclear safety regulation of radioisotope heat source transportation in lunar exploration project
    ZHANG Liang, HAN Guosheng, LIU Caixia
    RADIATION PROTECTION. 2023, 43(S1):  84-88. 
    Abstract ( 33 )   PDF (1029KB) ( 9 )  
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    In the chang’e-4 project, China used domestic radioisotope heat sources to provide energy for aerospace projects for the first time. In order to ensure the safe implementation of the mission, it is necessary to carry out nuclear safety regulation on the whole process from development to launch, while the domestic mature safety regulation experience on such domestic radioisotope heat source products is insufficient. Starting with the analysis of the radioactive characteristics of heat source, this paper investigates the existing nuclear safety regulatory requirements at home and abroad, especially the regulatory data of the International Atomic Energy Agency, Russian Federation and the United States. This paper also disassembles the regulatory links of heat source transportation, selects and analyzes the specific requirements suitable for the safety regulation of isotopic heat source transportation in China.
    Research on shipment approval of radioactive materials
    BAO Jie, ZHAN Lechang, ZHANG Linan, WANG Yue
    RADIATION PROTECTION. 2023, 43(S1):  89-94. 
    Abstract ( 43 )   PDF (1647KB) ( 17 )  
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    This paper investigated the basic situation of radioactive material shipment approval, mainly Including the scope of approved shipment of radioactive material and the main content of approval, made by the International Atomic Energy Agency (IAEA), the United States, Great Britain, France, Germany and China’s shipment approval agencies. This paper also summarized and compared the similarities and differences of the scope of approval and the content of approval, combined with the actual situation of domestic radioactive material shipment regulation. Suggestions on the management of radioactive material shipment are given.
    Analysis on transport and use of radioactive sources for well logging in oil (gas) fields in China
    PAN Yuting, CAO Fangfang, LI Duohong, LIU Nian
    RADIATION PROTECTION. 2023, 43(S1):  95-98. 
    Abstract ( 37 )   PDF (2370KB) ( 9 )  
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    The data of the transportation and use of radioactive sources as well as their packages for well logging used in oil (gas) fields were collected. At present, there were more than 60 organizations in China that use well logging sources. There were approximately 3 340 well logging sources, in which 697 sources belong to Class II radioactive materials. And there were 126 types of packaging for those 697 sources. Investigation has found that 40% of the well logging sources have expired service. Only 22.5% of packaging had been registered. The surface doses of some packages approach 7 times of the limits specified by national standard. The well logging operations were also not quite standardized. Suggestions were put forward to these problems.
    Research on key issues of radiation protection design for low-level radioactive waste disposal sites
    WANG Yaxiao, LI Zhuoran, WANG Bingheng, WANG Xiaoxia, GAO Guiling
    RADIATION PROTECTION. 2023, 43(S1):  99-105. 
    Abstract ( 42 )   PDF (4886KB) ( 50 )  
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    The radiation protection design of low-level radioactive waste disposal sites generally involves waste disposal cells and waste receiving plant. The radiation shielding structure of waste disposal cell correlates highly with the acceptance criteria of the disposal site and the waste stacking and disposal plan. There are waste loading places, waste unpacking places and nondestructive examination places in the waste reception plant. This paper mainly introduces the formulation of radiation zoning criteria for low-level radioactive waste disposal sites, the consideration of radiation protection design principles, and the radiation protection design of waste disposal cells and waste receiving plants. The waste stratification and separation strategy in waste disposal cells, the limit of the surface dose rate of radioactive waste and limit layers allowed in different separation and stacking methods were studied. The direct irradiation of the side walls of the disposal unit and the sky scattering of the disposal unit, as well as radiation protection design considerations for cement mortar and capping were considered. Key issues about radiation protection design in the unpacking area of the waste receiving plant were studied, too. The problems and experience related to the radiation protection design of low-level radioactive waste near-surface disposal sites are introduced, which provides a reference for the radiation protection design of related facilities.
    Study on the influence of radioactive waste oil capacity on the performance of cement waste form
    LIU Yan, ZHAO Qinkai, YU Dawan, WAN Xiaogang, WANG Dongwen, ZHOU Chenhao
    RADIATION PROTECTION. 2023, 43(S1):  106-110. 
    Abstract ( 35 )   PDF (2948KB) ( 12 )  
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    The total amount of radioactive organic waste oil that is temporarily stored is small. And it's not easy to be solidified directly. In this paper, sulphur-aluminate cement and emulsion solidification method are used to solidify the simulated radioactive waste engine oil. Taking different oil capacity in the solidification matrix as the variable, the mechanical properties, leaching resistance and freeze-thaw properties of the solidification matrix are analyzed in accordance with the national standard GB 14569.1—2011. The results show that when the oil capacity is less than 25% (mass ratio), the properties of the solidification matrix meet the relevant requirements of national standard GB 14569.1—2011. On this basis, the thermal stability, porosity and phase composition of different oil solidification matrix were investigated by gradient temperature rise method, TG, XRD, SEM and static nitrogen adsorption instrument. The experimental results show that when the oil capacity is less than 16.67%, the thermal stability of the solidification matrix is excellent. When the oil capacity is 12.5%, the micro pores and pore diameter of the solidification matrix are the smallest, so the strength of the solidification matrix under this oil capacity is the highest. When the oil capacity is less than 25%, the addition of engine oil will not inhibit the hydration process of sulphur-aluminate cement and the differential curve of pore size distribution of cement solidification matrix.
    Construction and maintenance of urban radioactive waste repository and analysis of radiation environment monitoring in Yunnan
    LUO Jing, YU Yilin
    RADIATION PROTECTION. 2023, 43(S1):  111-122. 
    Abstract ( 44 )   PDF (4152KB) ( 22 )  
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    Yunnan radioactive waste repository is one of the first batch of urban radioactive waste repositories constructed by the central government. Over the past 34 years of operation, it has collected and stored a total of 3 650 radioactive sources and 12.2 tons of radioactive waste; The security construction of the warehouse area has been continuously upgraded to meet the nuclear safety guidelines “Requirements for the Safety Prevention System of Urban Radioactive Waste Storage”; The radiation environment quality in the warehouse area is good, and all radioactive monitoring indicators of environmental air, water, soil, and ecological environment belong to the regional environmental background level; The promotion activity of nuclear safety culture is rich and diverse, and the emergency prevention of radiation accidents is constantly prepared to continue to ensure the ecological and environmental safety of the province.
    Thoughts on regulation of occupational hazards during decommissioning of nuclear facilities
    ZHAN Jingming, XUE Xiangming, YANG Xue, JIANG Xia, WU Xiaoyan
    RADIATION PROTECTION. 2023, 43(S1):  123-128. 
    Abstract ( 46 )   PDF (1037KB) ( 16 )  
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    By investigating the publications, standards and documents related to the regulation of occupational disease hazards in the decommissioning of nuclear facilities, this paper analyzes the types, characteristics and regulatory status of occupational disease hazards in the process of decommissioning of nuclear facilities. It is considered that compared with the normal operation stage and building construction operations, the decommissioning of nuclear facilities has the characteristics of complex radiation source terms, strong radioactivity, uneven distribution of environmental radiation field, prominent dust hazard factors, etc, Its occupational disease hazard regulation measures are similar to construction operations, and it is difficult to regulate occupational disease hazards. Whether it is normal decommissioning or post-accident decommissioning, the health risks faced by workers participating in the decommissioning of nuclear facilities are still a key concern of all countries. In view of this, China should, on the basis of IAEA and domestic decommissioning related operating experience, combined with the characteristics of Nuclear Facility Decommissioning and the current situation of occupational hazard management, put forward prevention and management measures for occupational disease hazards at the decommissioning site of nuclear facilities in China, so as to provide occupational health regulation basis for the growing nuclear facility decommissioning project in China, and promote the healthy and stable development of Nuclear Facility Decommissioning in China.
    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 (1168KB) ( 22 )  
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    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.