Ajay Sharma, P. Bagdare, P. Chadha, P. Shree, M. Gupta, R. Chauhan, I. Jaiswal, K. Talapatra
The aim of this study was to compare the dosimetric parameters of Co-planar Intensity modulated radiotherapy (C-IMRT), non-coplanar (NC-IMRT), and volumetric arc therapy (VMAT) planning technique in hippocampal sparing (HS) whole brain radiotherapy (WBRT). Fifteen patients of brain metastasis (BM) treated with hippocampal sparing whole-brain palliative radiation were selected for this study. C-IMRT, NC-IMRT and VMAT plans were generated for the comparison. Generated plans were evaluated based on planning target volume (PTV) coverage, conformity index (CI), homogeneity index (HI), beam-on time (BOT) and dose delivered to organs at risk (OARs) for the prescribed dose (PD) of 30 Gy in 10 fractions. Statistically significant difference was found in PTVD95%, PTVmax, HI, BOT, MU, Dmax of the brainstem, Dmean of eyes, Dmax of lenses and Dmax, Dmean and D2% of the bilateral hippocampus. However, a non-significant difference was observed in CI, D100% of both the hippocampus, Dmax of the optic chiasm, optic nerves, and Dmax of eyes in all the three planning techniques. Considering the superior plan quality, both NC-IMRT and VMAT are better than the C-IMRT planning technique. Based on beam-on time and delivery efficiency VMAT is found to be superior to both the C-IMRT and NC-IMRT technique. Doses to OARs are very well within the limits in all the three planning techniques.
{"title":"Dosimetric comparison of coplanar intensity-modulated radiotherapy, noncoplanar intensity-modulated radiotherapy, and volumetric arc therapy planning technique in hippocampal-sparing whole-brain radiotherapy","authors":"Ajay Sharma, P. Bagdare, P. Chadha, P. Shree, M. Gupta, R. Chauhan, I. Jaiswal, K. Talapatra","doi":"10.4103/rpe.rpe_48_20","DOIUrl":"https://doi.org/10.4103/rpe.rpe_48_20","url":null,"abstract":"The aim of this study was to compare the dosimetric parameters of Co-planar Intensity modulated radiotherapy (C-IMRT), non-coplanar (NC-IMRT), and volumetric arc therapy (VMAT) planning technique in hippocampal sparing (HS) whole brain radiotherapy (WBRT). Fifteen patients of brain metastasis (BM) treated with hippocampal sparing whole-brain palliative radiation were selected for this study. C-IMRT, NC-IMRT and VMAT plans were generated for the comparison. Generated plans were evaluated based on planning target volume (PTV) coverage, conformity index (CI), homogeneity index (HI), beam-on time (BOT) and dose delivered to organs at risk (OARs) for the prescribed dose (PD) of 30 Gy in 10 fractions. Statistically significant difference was found in PTVD95%, PTVmax, HI, BOT, MU, Dmax of the brainstem, Dmean of eyes, Dmax of lenses and Dmax, Dmean and D2% of the bilateral hippocampus. However, a non-significant difference was observed in CI, D100% of both the hippocampus, Dmax of the optic chiasm, optic nerves, and Dmax of eyes in all the three planning techniques. Considering the superior plan quality, both NC-IMRT and VMAT are better than the C-IMRT planning technique. Based on beam-on time and delivery efficiency VMAT is found to be superior to both the C-IMRT and NC-IMRT technique. Doses to OARs are very well within the limits in all the three planning techniques.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"22 - 27"},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46364242","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"II. Dr. Srikumar Banerjee: Some fond reminiscences","authors":"M. Iyer","doi":"10.4103/rpe.rpe_17_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_17_21","url":null,"abstract":"","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"56 - 57"},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47908611","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Planning and preparedness for response to any kind of radiation emergency are an evolving and dynamic assignment with expertise developed over a period of time. The lessons learnt in this specialized field are from the past/reported emergencies, guiding documents available on response to radiation emergencies in national/international arena, worldwide security scenario on the use of nuclear and other radioactive material including attempted malicious usage and requirements of national/international regulatory framework. The above sources help us to evolve the planning, preparedness, build response capability, and periodic revision in overall capabilities. Response planning is to mitigate the consequences of nuclear emergency – a low probability, high impact scenario at the sites/general public living in the vicinity of operating nuclear facilities, and radiological emergency – a moderate probability, low impact scenario at any locations in public domain due to typical initiating scenarios – although could be different, most of our radiation emergency response centers, developed, revised to respond to any such challenges and response procedures are evolved, set. This article on planning, preparedness for response to radiation emergency describes the present level of planning and response capability by Department of Atomic Energy, India.
{"title":"Planning, preparedness, and response to nuclear/radiological emergency","authors":"S. Saindane, S. Murali, S. Dhole, N. Karmalkar","doi":"10.4103/rpe.rpe_9_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_9_21","url":null,"abstract":"Planning and preparedness for response to any kind of radiation emergency are an evolving and dynamic assignment with expertise developed over a period of time. The lessons learnt in this specialized field are from the past/reported emergencies, guiding documents available on response to radiation emergencies in national/international arena, worldwide security scenario on the use of nuclear and other radioactive material including attempted malicious usage and requirements of national/international regulatory framework. The above sources help us to evolve the planning, preparedness, build response capability, and periodic revision in overall capabilities. Response planning is to mitigate the consequences of nuclear emergency – a low probability, high impact scenario at the sites/general public living in the vicinity of operating nuclear facilities, and radiological emergency – a moderate probability, low impact scenario at any locations in public domain due to typical initiating scenarios – although could be different, most of our radiation emergency response centers, developed, revised to respond to any such challenges and response procedures are evolved, set. This article on planning, preparedness for response to radiation emergency describes the present level of planning and response capability by Department of Atomic Energy, India.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"47 - 53"},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"44366750","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
A. Patra, T. Jaison, S. Wagh, M. Jha, I. Saradhi, A. Kumar
The activity and gamma-absorbed dose rate due to the naturally occurring (226Ra, 232Th, and 40K) and anthropogenic (137Cs) radionuclides in the terrestrial environment were determined in soil samples collected around Mithivirdi Atomic Power Project Site, Bhavnagar District, Gujarat, by using gamma-ray spectrometry. The mean concentration levels measured in soil from the naturally occurring radioisotopes 226Ra, 232Th, and 40K are lower than the corresponding global average values reported worldwide. 137Cs activity in the soil sample is comparable with the preoperational baseline level activity of other nuclear power plant sites in India. The total outdoor effective dose rates due to soil ranged 16.7–79.5 μSv/y with the median value of 34.3 μSv/y. The absorbed dose rate due to cosmic components around Mithivirdi site was found to be in the range of 44.4–90.6 nGy/h.
{"title":"Studies on natural and fallout radioactivity mapping of the proposed Mithivirdi Atomic Power Project Site in Bhavnagar District, Gujarat, India","authors":"A. Patra, T. Jaison, S. Wagh, M. Jha, I. Saradhi, A. Kumar","doi":"10.4103/rpe.rpe_5_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_5_21","url":null,"abstract":"The activity and gamma-absorbed dose rate due to the naturally occurring (226Ra, 232Th, and 40K) and anthropogenic (137Cs) radionuclides in the terrestrial environment were determined in soil samples collected around Mithivirdi Atomic Power Project Site, Bhavnagar District, Gujarat, by using gamma-ray spectrometry. The mean concentration levels measured in soil from the naturally occurring radioisotopes 226Ra, 232Th, and 40K are lower than the corresponding global average values reported worldwide. 137Cs activity in the soil sample is comparable with the preoperational baseline level activity of other nuclear power plant sites in India. The total outdoor effective dose rates due to soil ranged 16.7–79.5 μSv/y with the median value of 34.3 μSv/y. The absorbed dose rate due to cosmic components around Mithivirdi site was found to be in the range of 44.4–90.6 nGy/h.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"12 - 18"},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"43039195","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Simultaneous observations of ambient gamma dose levels, temperature, relative humidity, and atmospheric pressure were carried out at National Atmospheric Research Laboratory (NARL), Gadanki, India (13.459°N and 79.175°E), from November 2011 to May 2014. The results show that about 92% of ambient gamma dose values lie between 150 and 200 nSv/h and best possible fit resulted in Gaussian fit with adjusted R2 of 0.99. A weak Pearson's correlation coefficient was found between ambient gamma dose levels and selected meteorological parameters measured over the location. No seasonal trend was observed in ambient gamma dose levels, but pronounced seasonal variations in temperature, relative humidity, and air pressure were found. A sudden increase in ambient gamma levels was observed during precipitation event (Nilam cyclone) and may be attributed to an additional contribution of precipitation washed 222Rn progeny aerosols within the atmosphere. The mean ambient gamma dose over NARL was 186 ± 4.3 nSv/h and is within world average given by UNSCEAR.
{"title":"Study of ambient gamma dose levels at national atmospheric research laboratory, Gadanki, India","authors":"K. Kumar, T. Prasad, Nagaraja Kamsali","doi":"10.4103/rpe.rpe_62_20","DOIUrl":"https://doi.org/10.4103/rpe.rpe_62_20","url":null,"abstract":"Simultaneous observations of ambient gamma dose levels, temperature, relative humidity, and atmospheric pressure were carried out at National Atmospheric Research Laboratory (NARL), Gadanki, India (13.459°N and 79.175°E), from November 2011 to May 2014. The results show that about 92% of ambient gamma dose values lie between 150 and 200 nSv/h and best possible fit resulted in Gaussian fit with adjusted R2 of 0.99. A weak Pearson's correlation coefficient was found between ambient gamma dose levels and selected meteorological parameters measured over the location. No seasonal trend was observed in ambient gamma dose levels, but pronounced seasonal variations in temperature, relative humidity, and air pressure were found. A sudden increase in ambient gamma levels was observed during precipitation event (Nilam cyclone) and may be attributed to an additional contribution of precipitation washed 222Rn progeny aerosols within the atmosphere. The mean ambient gamma dose over NARL was 186 ± 4.3 nSv/h and is within world average given by UNSCEAR.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"28 - 33"},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"44684268","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Amar N. Pant, Anilkumar S. Pillai, N. Krishnan, A. Verma
Identification and assessment of the isotopic composition of confiscated uranium are of very much concern when it enters the public domain. This paper describes the methodology used for the estimation of 235U and 234U concentration in five uranium samples using alpha and gamma spectrometry, and the results are compared with that of mass spectrometry technique. The activity ratio of 238U to 235U is obtained from the measurement on the 185 keV gamma-line of 235U and 1001 keV gamma-line of 234mPa. The isotopic abundance of 235U in the confiscated sample using radioanalytical techniques was found in the range of 0.22%–0.24%.
{"title":"Assessment of 235U and 234U concentration in confiscated uranium samples by alpha- and gamma-ray spectrometry techniques","authors":"Amar N. Pant, Anilkumar S. Pillai, N. Krishnan, A. Verma","doi":"10.4103/rpe.rpe_30_20","DOIUrl":"https://doi.org/10.4103/rpe.rpe_30_20","url":null,"abstract":"Identification and assessment of the isotopic composition of confiscated uranium are of very much concern when it enters the public domain. This paper describes the methodology used for the estimation of 235U and 234U concentration in five uranium samples using alpha and gamma spectrometry, and the results are compared with that of mass spectrometry technique. The activity ratio of 238U to 235U is obtained from the measurement on the 185 keV gamma-line of 235U and 1001 keV gamma-line of 234mPa. The isotopic abundance of 235U in the confiscated sample using radioanalytical techniques was found in the range of 0.22%–0.24%.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"43 1","pages":"134 - 139"},"PeriodicalIF":0.0,"publicationDate":"2020-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"43843549","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
A. Bakshi, S. Chatterjee, S. Dawn, Mudit Beck, T. Selvam
Shielding of a neutron source housing for 1 Ci 241Am-Be source has been designed and fabricated based on the simulation carried out using Monte Carlo code FLUKA. Neutron and photon dose equivalent rates at the surface and at 1 m distance from the surface of the housing were calculated using FLUKA simulation and measured using gamma and neutron dose rate meters. The calculated and measured gamma and neutron dose equivalent rates agree well. Neutron spectra outside the source housing were generated using FLUKA simulation and measured with the ROSPEC + simple scintillation spectrometer neutron spectrometry system and also agree reasonably well. Gamma spectra outside the source housing and residual activity due to activation products in stainless steel and lead of the housing were also generated through simulation.
在蒙特卡罗程序FLUKA的模拟基础上，设计并制作了1 Ci 241Am-Be源的中子源外壳屏蔽。使用FLUKA模拟计算了壳体表面和距离壳体表面1 m处的中子和光子剂量当量率，并使用伽马和中子剂量率计进行了测量。计算和测量的伽马和中子剂量当量率吻合良好。利用FLUKA模拟生成了源壳外的中子能谱，并用ROSPEC +简易闪烁光谱仪中子能谱系统进行了测量，结果也吻合较好。通过模拟得到了源外壳外的伽马能谱以及由于不锈钢和外壳中铅的活化产物而产生的剩余活度。
{"title":"Shielding designing of 241Am-Be neutron source housing experiment and Monte Carlo simulation","authors":"A. Bakshi, S. Chatterjee, S. Dawn, Mudit Beck, T. Selvam","doi":"10.4103/rpe.rpe_54_20","DOIUrl":"https://doi.org/10.4103/rpe.rpe_54_20","url":null,"abstract":"Shielding of a neutron source housing for 1 Ci 241Am-Be source has been designed and fabricated based on the simulation carried out using Monte Carlo code FLUKA. Neutron and photon dose equivalent rates at the surface and at 1 m distance from the surface of the housing were calculated using FLUKA simulation and measured using gamma and neutron dose rate meters. The calculated and measured gamma and neutron dose equivalent rates agree well. Neutron spectra outside the source housing were generated using FLUKA simulation and measured with the ROSPEC + simple scintillation spectrometer neutron spectrometry system and also agree reasonably well. Gamma spectra outside the source housing and residual activity due to activation products in stainless steel and lead of the housing were also generated through simulation.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"43 1","pages":"154 - 161"},"PeriodicalIF":0.0,"publicationDate":"2020-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"70842765","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Southern Tamil Nadu has placer deposits, which is rich in minerals like zircon, garnet, monazite and rutile containing with radionuclides of U, Th and their decayed products. The present study is to identify the high background radiation areas in the regions of South west–east coast of Tamil Nadu. The ground radiometric survey was conducted in different seasons using portable radiation survey meter and global positioning system. Total of 137 observation spots were marked from 5 blocks for repeat measurements. Then calculated for the outdoor effective external terrestrial dose to the public residing in these blocks. The survey found average absorbed dose rate of block in this order 3>2> 4>1>5 (1394, 641, 247, 225, 167 nGy/h, respectively). From the data, a spatial mapping was performed for seasonal variation and interpolated for the unknown areas of dose rate. The outdoor effective dose to the public was found to be 1.66> 0.79>0.31>0.27>0.20 mSv/y with respective blocks. Conclusion: The dose to public was found to be lower, when compared with other high background radiation areas in the world. Therefore, there is no significant radiological risks to the public from natural radiation exposure.
{"title":"Spatial mapping and radiometric survey of high background radiation areas in Southern Tamil Nadu, India","authors":"K. Baskaran, K. Arunachalam","doi":"10.4103/rpe.rpe_47_20","DOIUrl":"https://doi.org/10.4103/rpe.rpe_47_20","url":null,"abstract":"Southern Tamil Nadu has placer deposits, which is rich in minerals like zircon, garnet, monazite and rutile containing with radionuclides of U, Th and their decayed products. The present study is to identify the high background radiation areas in the regions of South west–east coast of Tamil Nadu. The ground radiometric survey was conducted in different seasons using portable radiation survey meter and global positioning system. Total of 137 observation spots were marked from 5 blocks for repeat measurements. Then calculated for the outdoor effective external terrestrial dose to the public residing in these blocks. The survey found average absorbed dose rate of block in this order 3>2> 4>1>5 (1394, 641, 247, 225, 167 nGy/h, respectively). From the data, a spatial mapping was performed for seasonal variation and interpolated for the unknown areas of dose rate. The outdoor effective dose to the public was found to be 1.66> 0.79>0.31>0.27>0.20 mSv/y with respective blocks. Conclusion: The dose to public was found to be lower, when compared with other high background radiation areas in the world. Therefore, there is no significant radiological risks to the public from natural radiation exposure.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"43 1","pages":"162 - 170"},"PeriodicalIF":0.0,"publicationDate":"2020-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"44933877","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
P. Savitri, T. Murty, J. Sudhakar, N. Krishna, S. Sahoo, A. Gupta, A. Kumar
Naturally occurring radionuclides of uranium, thorium series, and potassium are significant contributors of ingestion dose. Radioactive concentrations of 226Ra, 228Ra, and 40K in plant origin food cultivated around BARC, Visakhapatnam, were determined and the assessment of the ingestion dose through food consumption to different groups of population was estimated. Radionuclides in the samples analyzed were measured by high purity germanium gamma spectrometry system. The estimated annual effective dose from the ingestion of cereals, pulses, vegetables, fruits, and leafy vegetables due to 226Ra, 228Ra, and 40K radionuclides is 0.32 mSv. In this paper the estimated annual effective dose in the study area is compared to the ingestion dose due to intake of different food materials by various natural radionuclides reported in various parts of India and world. The data generated will be a useful baseline studies for the upcoming BARC facilities at Visakhapatnam, India.
{"title":"Ingestion dose due to 226Ra, 228Ra, and 40K in the plant origin food materials grown around BARC, Visakhapatnam","authors":"P. Savitri, T. Murty, J. Sudhakar, N. Krishna, S. Sahoo, A. Gupta, A. Kumar","doi":"10.4103/rpe.rpe_37_20","DOIUrl":"https://doi.org/10.4103/rpe.rpe_37_20","url":null,"abstract":"Naturally occurring radionuclides of uranium, thorium series, and potassium are significant contributors of ingestion dose. Radioactive concentrations of 226Ra, 228Ra, and 40K in plant origin food cultivated around BARC, Visakhapatnam, were determined and the assessment of the ingestion dose through food consumption to different groups of population was estimated. Radionuclides in the samples analyzed were measured by high purity germanium gamma spectrometry system. The estimated annual effective dose from the ingestion of cereals, pulses, vegetables, fruits, and leafy vegetables due to 226Ra, 228Ra, and 40K radionuclides is 0.32 mSv. In this paper the estimated annual effective dose in the study area is compared to the ingestion dose due to intake of different food materials by various natural radionuclides reported in various parts of India and world. The data generated will be a useful baseline studies for the upcoming BARC facilities at Visakhapatnam, India.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"43 1","pages":"140 - 147"},"PeriodicalIF":0.0,"publicationDate":"2020-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46587081","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
In the current examination, the ingestion and inhalation dose measurements for the particular body organs in light of the intake of radon through ground water used by the inhabitants have been surveyed in the various locations of Amritsar province, India, using an electrostatic collection type radon monitor (RAD7) analyzer with RAD-H2O accessory. The mean radon activity level in water was seen to be 5.93 ± 2.34 BqL-1. However, the radiation dose received by all different body organs significantly less than the UNSCEAR and WHO suggested a level of 100 μSvY-1. The annual effective dose for the diverse body organs in view of the intake of radon was additionally ascertained and found the maximum dose for lungs than other organs. The radiation dose received by bronchial epithelium by the means of inhalation was likewise high when contrasted with that by stomach walls through ingestion.
{"title":"Occurrence of radon contamination in ground water samples of Amritsar city, Punjab, India","authors":"Sumit Sharma, K. Kaur, Amanpreet Kaur, Ajay Kumar","doi":"10.4103/rpe.rpe_28_20","DOIUrl":"https://doi.org/10.4103/rpe.rpe_28_20","url":null,"abstract":"In the current examination, the ingestion and inhalation dose measurements for the particular body organs in light of the intake of radon through ground water used by the inhabitants have been surveyed in the various locations of Amritsar province, India, using an electrostatic collection type radon monitor (RAD7) analyzer with RAD-H2O accessory. The mean radon activity level in water was seen to be 5.93 ± 2.34 BqL-1. However, the radiation dose received by all different body organs significantly less than the UNSCEAR and WHO suggested a level of 100 μSvY-1. The annual effective dose for the diverse body organs in view of the intake of radon was additionally ascertained and found the maximum dose for lungs than other organs. The radiation dose received by bronchial epithelium by the means of inhalation was likewise high when contrasted with that by stomach walls through ingestion.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"43 1","pages":"171 - 178"},"PeriodicalIF":0.0,"publicationDate":"2020-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"42963644","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
京公网安备 11010802042870号
京ICP备2023020795号-1
扫码关注我们
求助内容：
应助结果提醒方式：