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  • 28 August 2023 Volume 32 Issue 4
      

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  • ZHANG Zhen, WU Zhen, LIANG Jing
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    Objective To calculate the doses and their dose conversion coefficients for the personnel whose organs were under accidental exposure to three types of X-ray machines and two γ radiation sources, and to provide a simple method for rapid estimation of accidental doses. Methods The radiation source models of X-ray machines and two γ sources were established with the FLUKA simulation software and a Chinese reference voxel phantom was imported. The organ absorbed dose, dose conversion coefficient between organ absorbed dose and air Kerma, and conversion coefficient between organ absorbed dose and radiation source were calculated for a simulated scenario where the personnel were under antero-posterior exposure to radiation sources 1 meter away. Results For the lungs, heart, muscles, soft tissue, liver, skin, and brain, the conversion coefficient between organ absorbed dose and air Kerma was 0.30-1.19 (Gy/Gy). For X-ray machines, the conversion coefficient between organ absorbed dose and output for the six organs ranged from 6.12 × 10?3 to 2.90 × 10?2 Gy·m2/(mA·min). For γ radiation sources, the conversion coefficient between organ absorbed dose and activity for the six organs ranged from 1.12 × 10?8 to 7.01 × 10?8 Gy·m2/(GBq·s). Conclusion The conversion coefficient between organ absorbed dose and air Kerma and the conversion coefficient between organ absorbed dose and output or activity of a flaw detector can provide important dosimetric parameters for rapid assessment of similar radiation accidents.
  • WANG Xinran, YAN Chao, CHEN Ling, MIAO Shiguang, ZHANG Liang
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    Objective To construct a rapid prediction system to improve the accuracy and efficiency of evaluation of the consequences of nuclear accidents at a field scale. Methods Base on a diagnostic wind field model and Lagrangian particle diffusion, we established a rapid prediction method for wind field and pollutant dispersion around complex underlying surfaces within a field scale, in a way of visual discrimination of buildings and vegetation distribution. With data simulation and the use of a real urban field example, the simulated results were compared with wind tunnel test measurements and computational fluid dynamics results to study the influence of complex underlying surfaces on wind field and pollutant transport in the region. Results The rapid prediction system could clearly simulate the high-resolution wind field and pollutant concentration distribution of the region in about five minutes. It could interface with geographic information software and couple with a mesoscale weather prediction model. In terms of accuracy, the system performed well in wind field simulation, with the fractional deviations of wind speed and wind direction being 0.33 and −0.08, respectively. Concentration field simulation was greatly affected by the wind field, and the ratios of simulated concentrations to observed concentrations were between 0.05 and 3.4, except for a few low concentration points. Conclusion The rapid prediction system can effectively simulate the distribution characteristics of the flow field and improve calculation efficiency when ensuring calculation accuracy, which provides an important reference for emergency response to nuclear accidents.
  • XU Zhiqiang, GENG Jiwu, JIA Yuxin, ZHANG Zaoqin, XIA Bing, WANG Meixia
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    Objective To analyze the dose distribution of induced radiation in fixed proton beam therapy room and the influence of shielding materials, and to provide a basis for radiation protection and shielding material selection in proton therapy. Methods FLUKA was used to simulate the dose distribution of induced radiation in fixed proton beam therapy room, the dose over time, and the influence of different concrete materials. Results The dose of induced radiation was mainly concentrated around the target, and the dose rapidly decreased to 1/5-1/10 of the value at the time of stopping irradiation after cooling for 3-5 min. The induced radiation in concrete formed a slightly higher dose area at the end of the main beam near the inner side of the shield. The content of Fe, O, and H in concrete had significant effects on induced radiation (P < 0.01), and the dose was negatively correlated with the content of Fe. Conclusion The patients after proton therapy as well as the induced radiation in air and shielding materials are the main sources of external radiation dose for workers, and waiting for a period of time is the most effective way to protect the staff. Without considering the difficulty in construction and based on the analysis of shielding materials in protection against external irradiation and their influence on induced radiation, heavy concrete with a relatively high level of Fe is the best choice of the shielding material for proton therapy room.
  • XIONG Wenjun, YAN Qiang, WANG Ying, HUANG Jinfeng, ZHONG Huaqiang
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    Objective To develop a portable nuclear radiation detector with low-energy γ-nuclide recognition capability for rapid measurement of the dose levels in low-energy radiation fields and identification of nuclides. Methods A digital multi-channel circuit was developed for a detector based on the room temperature semiconductor cadmium zinc telluride, nuclide recognition was achieved using an intelligent nuclide recognition algorithm, and the energy response function G(E) was used to calculate the real-time ambient dose equivalent rate H*(10). Results The portable spectrometer had a minimum detectable energy of 20 keV, and the typical energy resolution for low-energy X-rays was > 4.10% at 59.5 keV and 20℃, enabling accurate identification of 241Am nuclide. Conclusion The device has a good measurement performance for low-energy γ/X rays, effectively addressing the limitations of existing devices for monitoring low-energy radiation fields, and provide reliable technical methods for monitoring and emergency response in spent fuel reprocessing plants or nuclear material production plants.
  • LOU Hailin, ZHENG Yifan, WEN Wen, CONG Rili, DONG Qian, SUN Xiaoyu, TU Xingming, WANG Shaolin
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    Objective To improve the analysis of 134Cs, 137Cs, and 60Co in aerosol samples by the national key radiation environment laboratories. Methods Intercomparison of analysis results of 134Cs, 137Cs, and 60Co in standard aerosol samples was performed among the national key radiation environment laboratories according to Gamma spectrometry method of analyzing radionuclides in biological samples (GB/T 16145-1995 ), and the intercomparison results were evaluated by the standard deviation. Results Six laboratories were involved in the intercomparison. For 134Cs, 50% of the laboratories showed a relative deviation less than 10%, and 50% showed a relative deviation of 10%-20%. For 137Cs, 33.3% of the laboratories showed a relative deviation less than 10%, and 76.7% showed a relative deviation of 10%-20%. For 60Cs, all laboratories showed a relative deviation less than 10%. The overall intercomparison results were acceptable. Conclusion The laboratories in this intercomparison show generally good results.
  • LI Chuanlong, GUO Jinsen, WANG Chuangao, PANG Hongchao, LIU Senlin
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    Objective To evaluate the migration of plutonium aerosol caused by α recoil. Methods In this paper, the recoil deposition and Brownian motion of plutonium-containing nanoaerosols were simulated by Monte Carlo method. The recoil angle and the vertical first landing time of Brownian motion in the process of settling were sampled, and then the lateral displacements of Brownian motion were sampled to determine the final settling position of aerosol. Results For aerosols with particle sizes of 10-50 nm, the maximum migration distance of a single recoil settling was 1.39 μm. Brownian motion increased the migration capacity. Although there was a high likelihood that aerosols settled within 100 μm, there remained a slight probability of long-term suspension in the air. Conclusion The α recoil is one of the mechanisms of plutonium aerosol migration. An important mechanism for long-distance migration of nanoaerosols is that Brownian motion after recoil may cause them to suspend for a long time.
  • LYU Xiaofan, LU Binghui, RAN Xinze, WANG Junping, WANG Tao
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    Radionuclide-contaminated wounds are common in medical response to nuclear emergencies, which have different manifestations in different types of accidents. Medical treatment is the key part of the response. Based on the drill experience gained from medical response to nuclear emergencies, the authors summarize the research advances in radionuclide-contaminated wounds in recent years, mainly involving the biokinetic characteristics, medical response, surgical debridement, and prevention and treatment of internal contamination of radionuclide-contaminated wounds; the authors summarize the key points of technical operations and provide suggestions on improvements in the drills. The authors believe that medical treatment of radionuclide-contaminated wounds requires highly compatible integration of the practical skills from clinical medicine and radiological knowledge; emergency response, surgical debridement, and prevention and treatment of internal contamination all together constitute an integrated rescue and treatment strategy with internal logic correlations. However, targeted improvements are needed to achieve desired effects in the drills.
  • WANG Xinyun, ZHANG Wei, XIA Chundong, LIU Yi, ZHANG Xianpeng
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    Objective To investigate the gross alpha and gross beta radioactivity levels in drinking water around Shidao Bay Nuclear Power Plant before its operation. Methods Ten sampling sites were set up within 30 km of Shidao Bay Nuclear Power Plant. From 2018 to 2021, samples were collected during the dry season and wet season each year and were tested in a laboratory according to Standard examination methods for drinking water—radiological parameters (GB/T 5750.13—2006). Results From 2018 to 2021, the gross alpha radioactivity in drinking water within 30 km of Shidao Bay Nuclear Power Plant was within the range of about 0.004-0.420 Bq/L, which does not exceed the guided gross alpha radioactivity specified in the National Standard; from 2018 to 2021, the gross beta radioactivity level was about 0.008-1.050 Bq/L. In 2018, the gross beta radioactivity at the sampling site 4.7 km from the Nuclear Power Plant exceeded the guided level specified in the National Standards for Drinking Water Quality (GB 5749—2006), but it fell within the guided level in a repeat laboratory test after deducting the effect of 40K on the gross beta radioactivity. Conclusion After deducting the effect of 40K on the gross beta radioactivity, the gross alpha and gross beta radioactivity levels in drinking water within 30 km of Shidao Bay Nuclear Power Plant are within the guided levels specified in the National Standards.
  • LI Qingxin, LIU Sihai, JIANG Jianmei
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    Objective To determine the current situation of radiological health management in medical institutions in Nanyang, China, to analyze existing problems and propose improvement measures, and to improve the management level of radiological diagnosis and treatment practice in medical institutions. Methods According to the work plan of the Occupational Disease Prevention and Control Project in Henan Province, China, 66 medical institutions engaged in radiological diagnosis and treatment at different levels were selected for a questionnaire survey, in combination with on-site inspections, inquiries, and access to relevant materials. Results Of 66 medical institutions, 65 institutions held radiological diagnosis and treatment licenses, with a license holding rate of 98.5%. There were 17 “new construction, reconstruction, and expansion” projects, with an evaluation rate of 94.1%. In this survey, a total of 391 radiological diagnosis and treatment equipment were involved, and 387 units of equipment were tested for status, with a detection rate of 99.0% and a qualification rate of 94.8% (367/387); 55 units of equipment were tested for stability, with a detection rate of 14.1%; the workplace protection detection rate was 99.0%, and the qualification rate was 100%; 66 medical institutions had 1809 radiation workers, with an occupational health examination rate of 97.8%; 1262 people were trained, with a training rate of 95.7%; 1773 people were monitored for individual dose, with a monitoring rate of 98.0%. Conclusion Medical institutions should further strengthen management in licensing change, construction project evaluation, and equipment stability monitoring to improve the level of radiological health management.
  • DONG Liang, WU Yunyun, SONG Yanchao, JI Xuli, SUN Yanling, LI Hongcheng
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    Objective To primarily investigate the indoor radon concentrations in the urban and rural dwellings in Yinchuan, China, and to estimate the effective dose. Methods A total of 67 dwellings, which included 49 urban households and 18 rural households in Yinchuan, were selected to cumulatively measure the indoor radon concentrations for more than 3 months using solid state nuclear track detection. Results The arithmetic mean, geometric mean, median, and range of indoor radon concentrations in urban and rural areas in Yinchuan were 64 Bq/m3, 59 Bq/m3, 57 Bq/m3, and 25-172 Bq/m3, respectively. Surveillance sites with an indoor radon concentration higher than 100 Bq/m3 accounted for 7.5%. Indoor radon concentrations in rural areas were higher than those in urban areas. Indoor radon concentrations were highest in winter and lowest in summer. The effective dose of indoor radon exposure among residents in Yinchuan was 1.86 mSv/a. Conclusion The results of indoor radon concentrations measured in this investigation in Yinchuan are significantly higher than those measured in the 1990s. The annual effective dose is higher than the mean levels in the world and China.
  • LI Yueming, TANG Shicheng, CHEN Zhujun, CAO Shizhou, SUN Mingxia
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    Objective To analyze the results of acceptance testing of 60 extraoral dental X-ray equipment in Beijing, China from 2021 to 2022, and understand the main types and performance parameters of newly installed extraoral dental X-ray machines in the clinical market of Beijing, as well as the level of installation and trial run of the whole machine by various manufacturers, and to summarize the problems found in acceptance testing for improving equipment testing. Methods Field acceptance testing and evaluation were carried out according to the Specification for Testing of Quality Control in Medical X-Ray Diagnostic Equipment (WS 76—2020). Results The overall qualified rate of 60 extraoral dental X-ray equipment was 98.33%. Under the same condition of the same tube voltage for one dental equipment, the maximum deviation of the tube voltage indicated by the two modes (panorama and skull) is 5.5%, and the maximum difference of the half-value layer of the useful beam is 1.22 mm Al. There is also a certain difference between the exposure time indicating deviation from the panorama and the skull, with a maximum difference of 75.51%.Conclusion Strengthening ex-factory quality control, installing, and debugging of equipment can basically guarantee the performance of newly installed equipment. In the testing process, it is critical to ensure the effective point of measurement of the dose detector located on the central axis of the primary beam.
  • ZHANG Xiuyun, LIU Jie, LIU Zhenyou, CHE Zijing
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    Objective To investigate the current status of interventional radiology resources, radiation protection equipment, and the rate of wearing of personal dosimeters in Qingdao, China, and to provide a data basis for strengthening radiation protection and health management for interventional radiation workers. Methods A questionnaire survey was performed on all medical institutions with interventional radiation services in Qingdao. The data from April 1, 2020 to March 31, 2021 were pooled and analyzed. Results A total of 31 medical institutions in Qingdao were investigated, including 23 (74.20%) tertiary hospitals and 8 (25.80%) secondary hospitals. There were 88 pieces of interventional radiation equipment in total in Qingdao, 89.77% of which were in tertiary hospitals. A total of 921 interventional professionals participated, with 865 (93.92%) from tertiary hospitals and 56 (6.08%) from secondary hospitals. The mean annual number of visits to interventional services was 5.72 per 1000 people. Among personal protective equipment, the equipment rates of lead-rubber aprons, lead-rubber caps, and lead-rubber collars were highest, all being 100%. The rate of equipment of interventional protective gloves was lowest, which was only 51.61%. The mean number of each accessory protective equipment for each interventional machine was less than 1. The rate of wearing of dual-dosimeters was 84.36%. Conclusion Tertiary hospitals were dominant among the medical institutions in this survey of interventional radiology services in Qingdao. The most frequently equipped personal protective goods were lead-rubber aprons, caps, and collars. The equipment rates of interventional protective gloves and protective accessories and the rate of wearing of dual-dosimeters were relatively low.
  • HUANG Qiang, LI Wei, LI Kui
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    Objective To investigate the radionuclide content in food in Chongqing, China by conducting a survey on the radioactivity in food. Methods A total of 114 samples of vegetables, grain, milk powder, and tea were collected in Chongqing. The samples were dried, pulverized into powder, added into Marinelli beakers, and then measured for radionuclides using a high-purity germanium gamma spectrometer (GEM40P4-765). Results The mean activity concentrations of natural radionuclides 238U, 232Th, 226Ra, and 40K in food in Chongqing were (0.396 ± 0.510), (0.199 ± 0.296), (0.140 ± 0.209), and (119.250 ± 105.470) Bq/kg, respectively. The contents of radionuclides in different foods were significantly different (P < 0.05). The mean activity concentration of the artificial radionuclide 137Cs was (0.091 ± 0.308) Bq/kg, and the mean activity concentration of 90Sr measured in nine tea samples was (1.243 ± 0.860) Bq/kg. Conclusion The contents of radionuclides in food in Chongqing are lower than the national standard limits, but the safety of radioactivity in food still needs to be taken seriously, and long-term surveillance of radioactivity in food is needed.
  • TANG Hui, LI Yuandong, BI Chaowen, MAO Wanchong, WANG Qian, YU Qiang, LIU Xin, CHEN Cheng
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    Objective To investigate the content of thorium (Th) in surface water in Sichuan Province, China, and to evaluate Th-associated health risk via water intake for residents. Methods Twenty-three monitoring sections were set in main surface water bodies in Sichuan Province. From 2016 to 2021, the Th radioactivity level in the water bodies was measured during dry and normal-water seasons. The health risk of residents was evaluated by calculating radioactive Th intake from the surface water bodies combined with the use of a health risk assessment model. Results The Th radioactivity level of the surface water bodies in Sichuan Province was 0.02-0.67 μ./L. There was no significant difference in the Th radioactivity level of different years or different surface water bodies (P > 0.05). A significant difference was observed in the Th radioactivity level of different water seasons (P < 0.05). The total mean annual committed effective doses of Th in all age groups caused by drinking water and water immersion ranged from 3.14 × 10?8 to 8.75 × 10?7 Sv, all lower than the World Health Organization (WHO)-recommended reference level of 0.1 mSv. The overall carcinogenic risks for residents in all age groups ranged from 3.93 × 10?10 to 1.09 × 10?8, all below the most rigorous control limits issued by WHO and International Commission on Radiological Protection. Conclusion The Th-associated health risk via direct water intake and water immersion in main surface water bodies of Sichuan Province is at an acceptable level. Th in main surface water bodies of Sichuan Province is safe for all age groups.
  • WANG Huan, MENG Qinghua, SUN Yaru, BAI Bin, KONG Yuxia, MA Yongzhong
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    Objective To ensure the accuracy of gamma spectrometer in our laboratory for the analysis of radionuclides in samples and to improve the laboratory personnel’s ability to perform analyses of radionuclides. Methods Our laboratory had continuously participated in the national assessments of gamma spectrometry of radionuclides organized by the Chinese Center for Disease Control and Prevention. The samples were measured by a high-purity germanium gamma spectrometer (GEM-MX7080P4). An analysis was performed on the results of the gamma spectrometry assessments from 2014 to 2021. Results Our laboratory had an overall qualified rate of 100% (8/8) and an overall excellent rate of 39% (3/8) in the gamma spectrometry assessments from 2014 to 2021. The distribution ranges of RD, Z, U, and Urel for 28 measurements involving radionuclides 208Tl, 228Ac, 232Th, 40K, 238U, and 137Cs were −11.82% to 5.97%, −0.59 to 0.30, 0.02 to 0.92, and 4.33% to 10.49%, respectively. Conclusion The methods used in our laboratory for gamma spectrometry of radionuclides are accurate and the testing reports issued by our laboratory are reliable.
  • WANG Canhui, DENG Li
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    This paper presents a nuclear radiation environment monitoring scheme based on the Internet of Things technology. The scheme primarily utilizes ZigBee wireless communication protocol, dedicated line network topology, and cloud-based processing techniques to achieve the entire process of acquisition, localization, transmission, tracking, monitoring, and management of X, γ, α, β, and neutron radiation data at nuclear radiation monitoring sites. Through initial application, the system demonstrates favorable characteristics such as good portability, strong scalability, secure information transmission, and deep data mining.
  • FANG Jiangqi, YANG Jinzheng, AN Zhengwei, WANG Zhe, LI Huaiyuan
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    With the development and utilization of nuclear energy, the safe operation of nuclear facilities has become a social issue of great concern. China attaches great importance to nuclear emergency plan and the construction of legal, institutional, and mechanism systems. Among them, the emergency preparedness and response of airborne monitoring for nuclear emergency is one of the important components of the national nuclear emergency system. The technology system of airborne monitoring for nuclear emergency is being developed and combines the advantages of manned aircraft and unmanned aerial vehicle (UAV) airborne monitoring. In recent years, UAVs with different loads and types have been developed, with diversified sizes and types of detectors carried by UAVs. The research on UAV airborne monitoring techniques for nuclear emergency has been continuously deepened and improved, and the technical system of airborne monitoring for nuclear emergency has been developed at the same time. The construction of UAV airborne monitoring technology system for nuclear emergency is discussed from the perspectives of monitoring equipment and technology, emergency response plan, emergency monitoring and evaluation, monitoring standards, emergency personnel, emergency support, and training and exercise. The UAV is a rapidly developing aircraft. With the continuous improvement in UAV performance and the continuous innovation and development of nuclear emergency airborne monitoring technology, the UAV airborne monitoring technology system for nuclear emergency will be constantly improved and developed towards networking, intelligence, and standardization.
  • BI Xinlin, ZHANG Pu
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    Occupational health management is one of the major indicators for evaluating the occupational disease prevention and control status of employers. However, there is still a lack of occupational health management evaluation standards or specifications in China. Analysis and evaluation of the problems in occupational health management by employers require technicians to master the relevant laws, regulations, standards, and specifications. In contrast to this high technical demand, in reality various methods have been used for occupational health management evaluation. There are great differences in evaluation contents and the analysis is incomplete, resulting in numerous problems and low practical feasibility. In the Occupational Disease Prevention and Control Act (2016 Amendment), the cancellation of the certificates for institutions and individuals in evaluation of the damage caused by occupational diseases resulted in an increased number of assessment report writers with insufficient capability. Since 2018, the duty of occupational health supervision has been transferred from the work safety administrative department to the health administrative department. The ability of occupational health supervisors needs to be improved urgently. This article mainly analyzes and discusses the contents and methods of occupational health management evaluation, as well as the problems and suggestions. Our results provide a guideline for improvement of occupational health management.
  • DONG Defeng, GE Jingjing, DU Liwei
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    This paper reviews the investigation of examining a child without protective equipment exposed to an exceptionally large radiation field, in order to provide a reference for the investigation and handling of similar cases in the future. Based on the analysis of the way of obtaining evidence and the application of law, the authors put forward some suggestions, such as improving the standards, laws, and regulations related to radiation, enhancing the protective facilities, standardizing the law enforcement procedures, and strengthening the publicity and training of radiation hygiene. The health-related rights and interests of the examinees shall be effectively protected.
  • XI Cong, FAN Yaohua, WANG Hongtao, WANG Ziwei
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    Objective To analyze the implementation of national training on quality control testing of radiodiagnostic and radiotherapy equipment from 2018 to 2022, and to summarize the effects of the training program. Methods We collected and analyzed the information on the national training program for quality control testing of radiodiagnostic and radiotherapy equipment organized by the National Institute for Radiological Protection, Chinese Center for Disease Control and Prevention from 2018 to 2022. Results Five sessions of national training on quality control testing of radiodiagnostic and radiotherapy equipment were conducted from 2018 to 2022, with each session lasting four days. The proportion of teachers with senior professional titles was 87.5% (35/40). There were a total of 1045 attendances for radiological technician training, among which 75.1% (785/1045) had intermediate or lower technical titles and 87.1% (910/1045) had a bachelor’s degree or above. The qualified rate of training was 97.7% (905/926). In terms of the content, arrangement, and other key parts of training, the degrees of satisfaction of the trainees were all above 96.0%. Conclusion The national training program for quality control testing of radiodiagnostic and radiotherapy equipment worked well, with both the qualified rate and satisfaction degree above 95.0%. The program has helped professionals better understand and master the quality control testing of radiodiagnostic and radiotherapy equipment, and improved the high-quality development of continuing radiological education.
  • CHEN Jigang, YIN Aimin, YAO Yebao, WANG Xiaoting, JIANG Dejuan, LI Qingguo, CAO Wurui, LUO Yingying, LIU Chengjun
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    Objective To investigate the protective effect of berberine (BBR) against ionizing radiation injury in rats and its mechanism of action. Methods Sprague-Dawley rats were divided into seven groups: normal control group, 1-Gy radiation group, 1-Gy radiation plus low-dose BBR (50 mg/kg) group, 1-Gy radiation plus high-dose BBR (150 mg/kg) group, 3-Gy radiation group, 3-Gy radiation plus low-dose BBR (50 mg/kg) group, and 3-Gy radiation plus high-dose BBR (150 mg/kg) group. All the groups except the normal control group were exposed to external irradiation with a medical electron linear accelerator, followed by BBR administration by gavage for consecutive ten days. The serum levels of superoxide dismutase (SOD), reduced glutathione (GSH), and malondialdehyde (MDA) were measured by using the micromethod. The pathological changes of the bone marrow and small intestine were observed with HE staining. Results Compared with the normal control group, the radiation groups showed significantly increased MDA levels (P < 0.05), significantly decreased SOD and GSH levels (P < 0.05), and more severe pathological damage of the bone marrow and small intestine. Compared with the radiation groups, the BBR groups showed significantly decreased MDA levels (P < 0.05), significantly increased SOD and GSH levels (P < 0.05), and reduced pathological damage to the bone marrow and small intestine, which were more marked in the high-dose BBR group. Conclusion BBR has a certain protective effect against radiation injury in rats, which may be through increasing the activity of antioxidant substances, enhancing free radical clearance, and thereby alleviating free radicals-caused oxidative damage.