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Measurement of Radon Concentration and Estimation of Cancer Risk in Twenty-Four Model Houses in the Town of Koudougou

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Open Journal of Applied Sciences 2024年第1期14卷 193-204页

作者： Moumouni Derra Luc Telado Bambara Karim Kaboré Yalgado Zakaria Sawadogo Ousmane Cissé François Zougmoré Physics Department University Norbert Zongo Koudougou Burkina Faso Physics and Chemical Department Institute of Sciences and Technology “Ecole Normale Supérieure” Ouagadougou Burkina Faso Physics Department Virtual University Ouagadougou Burkina Faso Laboratory of Materials and Environment University Joseph Ki-Zerbo Ouagadougou Burkina Faso

The objective of our study is to evaluate the concentration of radon (86Rn) inside houses in the town of Koudougou in order to estimate its impact on the health of the population. Indeed, when uranium-rich minerals are found near the surface of the ground, radon concentrations can reach tens of becquerels per cubic meter in enclosed spaces. Given the nature of the geological base of Burkina Faso, this situation is quite probable and certain places that are sometimes poorly ventilated (house, school, office, etc.) can have radon levels high enough to constitute a health problem for occupants. Thus, twenty-four (24) sample houses were identified. In each house, the Corentium digital detector was between 0.8 m and 2 m for at least one week in a place where the occupants estimate that they spend more time of time and measure the concentration of radon in the long term and short term. The recorded data allowed us to determine the absorbed dose and the Annual Effective dose of radon gas for each house in order to estimate the Risk of Cancer and the probable Number of Cases of Lung Cancer per million inhabitants. Thus, the results indicate that the long-term radon concentration varies between 6 Bq/m3 and 285 Bq/m3 respectively in houses 11 and 4 compared to 1 Bq/m3 to 208 Bq/m3 in the short term in the same houses. Also, in the long term, in control houses 1, 3 and 4, the radon level is above the recommended threshold interval. For the short term, these are houses 1, 3, 4 and 17 respectively with 110 Bq/m3, 142 Bq/m3, 208 Bq/m3 and 105 Bq/m3. As for the long-term and short-term effective doses, only houses 1, 3, 4, 17 and 24 have values between 3 - 10 Sv/year. The estimation of the relative risk of lung cancer gives values relatively close to unity and between 1.006 and 1.142 with an average of 1.035 and that of the Number of Lung Cancer Cases per million inhabitants gives values between 8 and 166 with an average of 42. Th

关键词： Radon absorbed dose Annual Effective dose Cancer Risk

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The Effect of the Size of Radiotherapy Photon Beams on the absorbed dose to an Al_2O_3 Dosimeter

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Plasma Science and Technology 2012年第6期14卷 558-562页

作者：陈少文张文澜范丽仙唐强刘小伟 Dongguan University of Technology School of Physics and Engineering Sun Yat-sen University

The effect of the size of radiotherapy photon beams on the absorbed dose to an Al2O3 dosimeter was investigated using the Monte Carlo method. The EGSnrc/DOSRZnrc program code was used to simulate the absorbed dose to the Al2O3 dosimeter, as well as the absorbed dose to water at the corresponding position in the absence of the dosimeter. The incident beams were 60Co γ and 6 MV with a different beam radius ranging from 0.1 cm to 2 cm. Results revealed that the absorbed dose ratio factor depends on the size of the incident photon beam. When the radius of the incident beam is smaller than that of the dosimeter, the absorbed dose ratio factor decreases as the incident beam size increases. The absorbed dose ratio factor reaches its minimum when the radius of the incident beam is almost the same as that of the dosimeter. When the radius of the incident beam is larger than that of the dosimeter, the absorbed dose ratio factor increases as the incident beam size increases. The maximum difference among these absorbed dose ratio factors can be up to 14% in 60Co γ beams and 23% in 6 MV beams. However, when the size of the incident beam is much larger than that of the dosimeter, the effect of the incident beam size on the absorbed dose ratio factor becomes quite small. The maximum discrepancy between the absorbed dose ratio factors and the average value is not more than 1%.

关键词： Al2O3 dosimeter absorbed dose Monte Carlo radiotherapy photon beams

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International Recommendations on Calculation of absorbed dose in Biota:A Comprehensive Revue

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Journal of Environmental Protection 2014年第9期5卷 751-759页

作者： Wagner de S.Pereira Alphonse Kelecom Multidisciplinary Group of Radio Protection(GMR) Servico de RadioprotecaoUnidade de Tratamento de MinerioIndustrias Nucleares do BrasilCaldasBrazil Laboratory of Radiobiology and Radiometry Pedro Lopes dos Santos(LARARA-PLS) Group of Environmental Themes Assessment(GETA)Universidade Federal Fluminense(UFF)NiteroiBrazil

Since the early times, radioprotection has been focused on the human being. Currently this approach has changed, being now also necessary to take care of the protection of the environment from unwanted effects of ionizing radiation. To this end, several institutions (UNSCEAR, ICRP, IAEA, DOE, ACRP) and consortia of institutions (FASSET, ERICA) have established procedures in order to protect the biota of such effects. Developed procedures are based on the calculation of the absorbed dose in biota (ICRP, DOE, IAEA), or on environmental risk assessment―ERA (DOE, ACRP, FASSET, ERICA);but even in this latter approach the parameters used are related to the absorbed doses in biota. The calculation of dose is the standard procedure in human radioprotection, and this points such an approach as the most interesting for providing a convergence between human and nonhuman (= biota) radioprotections. On the other hand, the ERA approach is easier to apply, because this methodology is used in several countries for non-radioactive contamination assessments. Since the world radioprotection system follows a number of institutions (UNSCEAR, ICRP, IAEA and regulatory institutions of member countries) that use dose calculation, this appears to be the way for biota radioprotection. We here review and comment the evolution of the concepts and approaches of the recommendations for radioprotection of non-human biota.

关键词： Biota absorbed dose Radioprotection International Recommendations

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Studies of the radiation environment on the Mars surface using the Geant4 toolkit

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Nuclear Science and Techniques 2022年第1期33卷 120-130页

作者： Jun-Liang Chen Su-Jun Yun Tie-Kuang Dong Zhong-Zhou Ren Xiao-Ping Zhang Key Laboratory of Modern Acoustics and Department of Physics Nanjing UniversityNanjing 210093China School of Electronic Engineering Nanjing XiaoZhuang UniversityHongjing RoadNanjing 211171China Key Laboratory of Dark Matter and Space Astronomy Purple Mountain ObservatoryCAS2 West Beijing RoodNanjing 210008China School of Physics Science and Engineering Tongji UniversitySiping Rood 1239Shanghai 200092China State Key Laboratory of Lunar and Planetary Sciences Macao University of Science and TechnologyMacao 999078China

The radiation environment on the surface of Mars is a potential threat for future manned exploration missions to this planet.In this study,a simple geometrical model was built for simulating the radiation environment on the Mars surface caused by galactic cosmic rays;the model was built and studied using the Geant4 toolkit.The simulation results were compared with the data reported by a radiation assessment detector(RAD).The simulated spectra of neutrons,photons,protons,α particles,and particle groups Z=3-5,Z=6-8,Z=9-13,and Z=14-24 were in a reasonable agreement with the RAD data.However,for deuterons,tritons,and 3He,the simulations yielded much smaller values than for the corresponding RAD data.In addition,the particles’spectra within the 90 zenith angle were also obtained.Based on these spectra,we calculated the radiation dose that would have been received by an average human body on Mars.The distribution of the dose throughout the human body was not uniform.The absorbed and equivalent doses for the brain were the highest among all of the organs,reaching 62.0±1.7 mGy/y and 234.1±8.0 mSv/y,respectively.The average absorbed and equivalent doses for the entire body were approximately 44 mGy/y and 153 mSv/y,respectively.Further analysis revealed that most of the radiation dose was owing to a particles,protons,and heavy ions.We then studied the shielding effect of the Mars soil with respect to the radiation.The body dose decreased significantly with increasing soil depth.At the depth of 1.5 m,the effective dose for the entire body was 17.9±2.4 mSv/y,lower than the dose limit for occupational exposure.At the depth of 3 m,the effective dose to the body was 2.7±1.0 mSv/y,still higher than the accepted dose limit.

关键词： Galactic cosmic rays Radiation environment of the Mars absorbed dose Equivalent dose Geant4

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Radiation dose effects on the morphological development of M_(1) generation pea(Pisum sativum)

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Nuclear Science and Techniques 2021年第11期32卷 63-76页

作者： Da-Peng Xu Hu-Yuan Feng Jian-Bin Pan Ze-En Yao Jun-Run Wang School of Nuclear Science and Technology Lanzhou UniversityLanzhou 730000China School of Life Sciences Lanzhou UniversityLanzhou 730000China Engineering Research Center for Neutron Application Technology Ministry of EducationLanzhou UniversityLanzhou 730000China

We irradiated pea seeds with neutrons from a ^(252)Cf source and studied the radiation dose effects on various morphological development parameters during the growth of M_(1) generation peas.We found that in the dose range of 0.51-9.27 Gy,with the increase in neutron-absorbed dose,the morphological development parameters of M_(1) generation peas at the initial seedling stage showed an obvious trend with three fluctuations.With the development of pea,this trend gradually weakened.Further analysis and verification showed that the main trend in the M_(1) generation of pea seeds was an inhibitory effect induced by neutron irradiation and there was a good linear correlation between the inhibitory effect and neutron absorption dose We successfully demonstrated the background removal of mutant plants and defined morphological developmen parameters for peas that match the overall development of plants.Our results will positively impact neutron mutation breeding and automatic agriculture.

关键词： Neutron irradiation Pea(Pisum sativum) ^(252)Cf source Radiation does effects absorbed dose Morphological development

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Calculation of Mass Stopping Power and Range of Protons as Well as Important Radiation Quantities in Some Biological Human Bodyparts (Water, Muscle, Skeletal and Bone, Cortical)

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International Journal of Medical Physics, Clinical Engineering and Radiation Oncology 2022年第2期11卷 99-112页

作者： Ahlam S. Almutairi Khalda T. Osman Department of Physics College of Science Qassim University AL-Rass Saudi Arabia Department of Physics College of Science Qassim University Buraydah Saudi Arabia

In this work, the electronic mass stopping power and the range of protons in some biological human body parts (Water, Muscle, Skeletal and Bone, Cortical) were calculated in the energy range of protons 0.04 to 200 MeV using the theory of Bethe-Bloch formula as giving in the references. All these calculations were done using Matlab program. The data related to the densities, average atomic number to mass number and excitation energies for the present tissues and substances were collected from ICRU Report 44 (1989). The present results for electronic mass stopping powers and ranges were compared with the data of PSTAR and good agreements were found between them, especially at energies between 1 - 200 MeV for stopping power and 4 - 200 MeV for the range. Also in this study, several important quantities in the field of radiation, such as thickness, linear energy transfer (LET), absorbed dose, equivalent dose, and effective dose of the protons in the given biological human body parts were calculated at protons energy 0.04 - 200 MeV.

关键词： Biological Human Bodyparts Protons Range MatLab PSTAR Electronic Mass Stopping Power LET absorbed dose Effective and Equivalent dose

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Evaluation of Radon Concentration and the Health Risk in the Offices of the Institute of Science and Technology of the “École Normale Supérieure”, Burkina Faso

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World Journal of Nuclear Science and Technology 2023年第3期13卷 41-54页

作者： Rouamba M. M. Jonathan Bambara Telado Luc Doumounia Ali Kohio Nièssan Ouédraogo Soumaila François Zougmore Laboratory of Materials and Environment Physics Department University Joseph Ki-Zerbo Ouagadougou Burkina Faso Institute of Science and Technology Ecole Normale Supérieure Koudougou Burkina Faso

The second most important cause of lung cancer after smoking is radon gas. Thus, the determination of indoor radon concentrations in residential buildings and workplaces is an important public health concern. The purpose of this research was to measure the concentration of radon gas in the offices of the Institute of Science and Technology and to evaluate the effective dose in the lungs and the risk of cancer. This study used Corentium’s AIR THINGS digital radon detector to determine the radon concentration in sixteen (16) offices. The digital radon detector air Things of Corentium was placed in each office for a minimum period of one week and the concentration values were recorded every 24 hours. The values recorded in each office were the short-term average and the long-term average during seven days of measurement. The short-term radon concentrations vary between 5.286 Bq/m3 and 192.714 Bq/m3 with an average of 48.01 Bq/m3 and those in the long-term were between 6.143 Bq/m3 and 172.571 Bq/m3 with an average of 52.46 Bq/m3. The measurements in office N°6 and 13 were above the lower limit of 100 Bq/m3 proposed by the WHO. The short-term and long-term effective doses in the lungs for offices N°6 and 13 were above the “normal” background level of 1.1 mSv/year proposed by UNSCEAR-2000. The short-term effective dose in the lungs for office N°6 was above the lower limit of 3 mSv per the ICRP-23 recommendation. The average number of lung cancer cases per year per million people was 15.

关键词： Radon Concentration absorbed dose Effective dose

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Investigation of the Radiological Risk of Farmlands and the Transfer Factor from Soil to Crops in Jalingo and Wukari L.G.A of Taraba State, Nigeria

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Journal of Environmental Protection 2022年第1期13卷 1-14页

作者： Alexander A. Tyovenda John A. Ocheje Sombo Terver Effiong U. Uttah Department of Physics Federal University of Agriculture Makurdi Makurdi Benue State Nigeria Department of Pure and Applied Physics Federal University Wukari Wukari Taraba State Nigeria Department of Physics University of Uyo Uyo Akwa-Ibom State Nigeria

The activity concentrations of radionuclides, absorbed dose rate, excess lifetime cancer risk, and soil-to-plant transfer factor have been evaluated in soil and crop samples from Jalingo and Wukari Local Government Area of Taraba State, Nigeria. The activity concentrations were determined with the aid of High Purity Germanium detector. The absorbed dose and excess lifetime cancer risk were evaluated and forecasted for 60 years using the ResRad off-site model. The average activity concentration of 40K, 232Th, and 238U in the soil samples were 633.13, 141.15, and 71.20 Bq·kg-1 respectively, for the Jalingo study area, and while that of the Wukari study area was;199.21, 87.23, and 25.37 Bq·kg-1 respectively. The average soil-to-plant transfer factors for 40K, 232Th, and 238U were 0.51, 0.10, and 0.27 respectively for the Jalingo study area while that of Wukari are 0.40, 0.57, and 0.74 respectively. The mean annual effective dose equivalent for the study area is higher than the world average of 0.07 mS·vy-1. The excess lifetime cancer risk for the study areas has values that are higher than the safety limit. The ResRed model showed that direct radiation from the crops is the major contributor to excess cancer risk among other pathways. The radiological hazard indices reveal health risks to farmers, especially in the Jalingo area.

关键词： Activity Concentration Transfer Factor absorbed dose Excess Lifetime Cancer Risk

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Assessment on Radiation Hazard Indices from Selected Dumpsites in Lafia Metropolis,Nasarawa State,Nigeria

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Journal of Oncology Research 2022年第1期4卷 20-26页

作者： Bello Aisha Ademoh Usman Rilwan Musa Yusuf Department of Physics Federal UniversityLafiaNasarawa StateNigeria Department of Physics Nigerian Army UniversityPMB 1500 BiuBorno StateNigeria

This research reports an assessment of ionizing radiation in some chosen Dumpsites in Lafia Local government area of Nasarawa State.Ionizing radiation measurement was conducted at four Dump sites.The survey was done using a radiation survey meter(Radex one Outdoor 55130719 NA).Radiation exposure rate in micro sievert per hour(μSvhr^(-1))was measured.Readings were taken by placing the detector at gonad level about 1 meter above the ground.Result showed that the average annual effective dose rate in the selected dumpsites were 0.22 mSv/yr for Lafia modern market,0.17 mSv/yr for dumpsite opposite governor Isa house,0.15 mSv/yr for Timber shade Lafia and 0.20 mSv/yrfor Science School Lafia respectively with a mean value of 0.19 mSv/yr for all location,while the mean calculated excess life cancer risk(ELCR)is 0.65×10^(-3).Dumpsites yearly absorbed dose rate and their corresponding ELCR values did not exceed the 1.0 mSv/y Basic Safety Standard set for the masses by International Council on Radiation Protection(ICRP,1999)and mean world average ECLR value of 1.16×10^(-3).Based on these results there are no radiation consequence to the scavengers,dumpsite workers and residents living around the dumpsites.

关键词： Radiation Dumpsites Scavengers absorbed dose Effective dose

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Assessment of radioactivity levels in some cement produced locally in Iraq

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Radiation Detection Technology and Methods 2021年第4期5卷 633-640页

作者： Maitham S.Amana Najwa J.Jubier Mohammed J.R.Aldhuhaibat A.A.Salim Department of Physics College of ScienceUniversity of WasitKutWasitIraq Laser Center&Physics Department Faculty of ScienceUniversiti Teknologi MalaysiaJohor bahruJohorMalaysia

Purpose Due to the rapid expansion of the construction industries,cement production is ever-increasing worldwide and maintaining the qualities of the local cement became vital for safe and durable structures.In this regard,the radiometric assessment of cement plays a significant role.Method The specific activities of the naturally occurring radionuclides present in ten Portland cement samples that can cause possible health hazards were determined using a gamma-ray spectrometer equipped with(3×3)inch NaI(Tl)detector with 1024 channels.Result and conclusion The measured activity concentrations of Ra-226,Th-232,and K-40 were found in the range of 12.38–55.75(average of 31.29 Bq/kg),6.29–57.54(average of 15.97 Bq/kg),and 112.63–266.37(average of 168.24 Bq/kg),respectively.The recorded average activity concentration of these radionuclides in the cement was below the stipulated world standard by UNSCEAR(Sources and Effects of Ionizing Radiation,United Nations Scientific Committee on the Effects of Atomic Radiation UNSCEAR 2000 Report to the General Assembly,with Scientific Annexes,vol.I,2000).The obtained mean activity concentration of Raeq in the cement(67.101 Bq/kg)was much lower than the recommended guideline of 370 Bq/kg.In addition,the mean value of the calculated absorbed dose rate(59.947 nGy·h^(−1)),annual effective dose(0.220 mSv·y^(−1)),activity concentration index(0.240),alpha index(0.156),excess lifetime cancer risk(0.771×10^(−3))external(0.084)and internal(0.300)hazard index of the studied samples were much below the recommended safety limits.It is affirmed that the cement sold in the local market can safely be used for building constructions.

关键词： Cement Concentration absorbed dose Alpha index Health hazards

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