{"title":"ISO/IEC 17025: Accreditation standard for testing and calibration laboratories","authors":"D. Rao","doi":"10.4103/rpe.rpe_41_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_41_21","url":null,"abstract":"","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"121 - 122"},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45732078","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}
This study presents our initial experience on the effective approach to apply real-time radiation dose monitoring during computed tomography (CT)-guided interventional procedures and the potential effects on overall radiation dose. A phantom study using multiple detectors at different body levels was conducted to determine badge positioning and possible effects on scatter radiation doses at three angles; parallel, perpendicular, and 45° relative to the CT gantry. A retrospective study was also conducted to compare scatter radiation and patient radiation doses during live CT fluoroscopy-guided procedures. Highest dose rates were observed when detector faced the scatter source in the perpendicular position to the gantry. There is no significant difference between wearing the detector at the shoulder or at the waist level. The use of real-time dose monitoring system provides immediate feedback during CT fluoroscopy procedures allowing for timely behavior modification.
{"title":"Initial experience on the use of real-time displayed radiation dose monitoring system in computed tomography fluoroscopy","authors":"D. Raissi, T. Seay, J Zhang","doi":"10.4103/rpe.rpe_34_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_34_21","url":null,"abstract":"This study presents our initial experience on the effective approach to apply real-time radiation dose monitoring during computed tomography (CT)-guided interventional procedures and the potential effects on overall radiation dose. A phantom study using multiple detectors at different body levels was conducted to determine badge positioning and possible effects on scatter radiation doses at three angles; parallel, perpendicular, and 45° relative to the CT gantry. A retrospective study was also conducted to compare scatter radiation and patient radiation doses during live CT fluoroscopy-guided procedures. Highest dose rates were observed when detector faced the scatter source in the perpendicular position to the gantry. There is no significant difference between wearing the detector at the shoulder or at the waist level. The use of real-time dose monitoring system provides immediate feedback during CT fluoroscopy procedures allowing for timely behavior modification.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"141 - 145"},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"49017284","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}
The potential use of stable fission products from the decay of radioactive contaminants in recreating the impact assessment of radioactivity releases from nuclear power stations is examined. With the advances in mass spectrometry, Minimum Detectable Limits (MDLs) comparable to radioactive measurements have been achieved in the case of stable isotopes as well. The applications of stable fission products in safeguards and environmental surveillance by the author are mentioned. The limited application of stable fission products in the analysis of Fukushima environmental samples is reviewed. The article examines the possible candidates for such analysis and points out the enormous possibilities. This is a neglected field in environmental impact assessment till now and calls for standardizing measurement procedures and analysis methodologies. The stable fission product signatures can also be used to study the uptake and transport of radionuclides in the environment.
{"title":"Stable isotope analysis in environmental impact assessment of radioactivity releases from nuclear power plants","authors":"M. Iyer","doi":"10.4103/rpe.rpe_40_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_40_21","url":null,"abstract":"The potential use of stable fission products from the decay of radioactive contaminants in recreating the impact assessment of radioactivity releases from nuclear power stations is examined. With the advances in mass spectrometry, Minimum Detectable Limits (MDLs) comparable to radioactive measurements have been achieved in the case of stable isotopes as well. The applications of stable fission products in safeguards and environmental surveillance by the author are mentioned. The limited application of stable fission products in the analysis of Fukushima environmental samples is reviewed. The article examines the possible candidates for such analysis and points out the enormous possibilities. This is a neglected field in environmental impact assessment till now and calls for standardizing measurement procedures and analysis methodologies. The stable fission product signatures can also be used to study the uptake and transport of radionuclides in the environment.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"167 - 170"},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47167236","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}
K. Reddy, C. Kaliprasad, C. Suresh, C. Ningappa, B. Mata, E. Srinivasa
The indoor 222Rn and 220Rn were measured by using deposition progeny sensors and single-entry pinhole dosimeter around Kolar Gold Fields of Karnataka state, India. The thirty different places were identified and fixed the dosimetry cups for the determination. The 222Rn and 220Rn concentrations of indoor environment range from 26.2 ± 1.3 to 138.4 ± 1.6 and 21.2 ± 0.8 to 133.3 ± 1.5 Bq/m3 with a mean value of 68.8 ± 1.6 and 61.8 ± 1.5 Bq/m3, respectively. The equivalent concentrations of 222Rn and 220Rn values vary from 0.9 ± 0.4 to 7.6 ± 1.1 and 6.8 ± 0.8 to 19.8 ± 1.8 Bq/m3 with a standard value of 4.3 ± 0.8 and 14.2 ± 1.3 Bq/m3, respectively. The values between the equilibrium factor between 222Rn, 220Rn, and their daughter were also calculated and found to be 0.23 and 0.07, respectively. The average annual intake of 222Rn, 220Rn, and their daughters' products is 2.28 mSv/y1, slightly below the global average of 2.4 mSv/y1 from all components. The data obtained compare average values in the world.
{"title":"Estimation of indoor 222Rn and 220Rn concentration and annual inhalation dose in the indoor environment around Kolar district of Karnataka state, India","authors":"K. Reddy, C. Kaliprasad, C. Suresh, C. Ningappa, B. Mata, E. Srinivasa","doi":"10.4103/rpe.rpe_33_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_33_21","url":null,"abstract":"The indoor 222Rn and 220Rn were measured by using deposition progeny sensors and single-entry pinhole dosimeter around Kolar Gold Fields of Karnataka state, India. The thirty different places were identified and fixed the dosimetry cups for the determination. The 222Rn and 220Rn concentrations of indoor environment range from 26.2 ± 1.3 to 138.4 ± 1.6 and 21.2 ± 0.8 to 133.3 ± 1.5 Bq/m3 with a mean value of 68.8 ± 1.6 and 61.8 ± 1.5 Bq/m3, respectively. The equivalent concentrations of 222Rn and 220Rn values vary from 0.9 ± 0.4 to 7.6 ± 1.1 and 6.8 ± 0.8 to 19.8 ± 1.8 Bq/m3 with a standard value of 4.3 ± 0.8 and 14.2 ± 1.3 Bq/m3, respectively. The values between the equilibrium factor between 222Rn, 220Rn, and their daughter were also calculated and found to be 0.23 and 0.07, respectively. The average annual intake of 222Rn, 220Rn, and their daughters' products is 2.28 mSv/y1, slightly below the global average of 2.4 mSv/y1 from all components. The data obtained compare average values in the world.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"146 - 151"},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"41754008","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}
M. Lawal, P. Ayanlola, O. Oladapo, Michael Oni, A. Aremu
The recent interest in the applications of mineral rocks for interior building decoration has been a major concern from the radiological perspective because the breaking down of rocks into various shapes and sizes releases radioactive gaseous element that is harmful to human health. Hence, this study assessed the radon exhalation rates of different rock types in Nigeria and their implications on human health. A total of 45 samples comprising five samples per rock type were prepared, packed, and sealed inside a modified closed can and thereafter subjected to radon concentration measurement using a RAD7 detector. The results of the study showed that granite and limestone rock types had high radon concentrations and exhalation rates as compared to other rock samples assessed. The radon concentration for granite and limestone rockfalls within the action level limit. Thus, effort should be made to ensure adequate ventilation of any building that uses these rock types in building decoration. The results obtained can be used as baseline data for future investigation of the rock types in any locality.
{"title":"Assessment of radon exhalation rates in mineral rocks used in building decoration in Nigeria","authors":"M. Lawal, P. Ayanlola, O. Oladapo, Michael Oni, A. Aremu","doi":"10.4103/rpe.rpe_39_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_39_21","url":null,"abstract":"The recent interest in the applications of mineral rocks for interior building decoration has been a major concern from the radiological perspective because the breaking down of rocks into various shapes and sizes releases radioactive gaseous element that is harmful to human health. Hence, this study assessed the radon exhalation rates of different rock types in Nigeria and their implications on human health. A total of 45 samples comprising five samples per rock type were prepared, packed, and sealed inside a modified closed can and thereafter subjected to radon concentration measurement using a RAD7 detector. The results of the study showed that granite and limestone rock types had high radon concentrations and exhalation rates as compared to other rock samples assessed. The radon concentration for granite and limestone rockfalls within the action level limit. Thus, effort should be made to ensure adequate ventilation of any building that uses these rock types in building decoration. The results obtained can be used as baseline data for future investigation of the rock types in any locality.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"161 - 166"},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45828986","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}
To perform patient-specific quality assurance (QA), the accuracy of the dose calculation algorithm is vital, especially in the lung cancer stereotactic body radiation therapy (SBRT). The present study is based on the evaluation of two widely used algorithms, analytical anisotropic algorithm (AAA) and Acuros XB (AXB) inside the in-house developed heterogeneous thorax phantom (HTP) and a homogeneous slab phantom (HSP) simultaneously. To evaluate dosimetric differences between the two algorithms, point dose measurement was performed for pretreatment QA plans of 35 lung cancer patients by keeping the same monitor units and beam angles as those for the actual patient treatment. The dose was calculated on the Eclipse treatment planning system inside both the medium by using both AAA and AXB algorithms. Plans were delivered on the Edge linear accelerator (LA) (Varian Medical Systems, Palo Alto, CA, USA), and measurements were taken by using a 0.01 cc ion chamber and DOSE1 electrometer. Statistical analysis was performed on the observed data set, and percentage (%) variations between the measured and planned doses were calculated and analyzed. The mean % variations between the measured and planned doses inside HTP for all QA plans were found to be 2.61 (standard deviation [SD]: 0.66) and 2.19 (SD: 0.64) for AAA and AXB algorithms, respectively. Whereas, inside HSP, it was found to be 1.79 (SD: 0.74) and 1.64 (SD: 0.70) for AAA and AXB algorithms, respectively. The mean % difference between the measured dose and the planned dose was derived to be statistically significant for HTP, however, it was found to be statistically insignificant inside the HSP at P < 0.01. The Pearson's correlation coefficient test showed a strong positive correlation between the measured dose and the planned dose for both AAA and AXB inside HTP as well for HSP. The results obtained from this study showed that as the actual patient body is heterogeneous, thus to get more realistic results, patient-specific QA must be performed inside the heterogeneous phantom instead of homogeneous. Moreover, in the homogeneous medium, both the algorithms predict the dose efficiently, however, in heterogeneous medium, AAA over/under predicts the dose, whereas AXB shows good concurrence with measurements.
为了进行患者特异性质量保证（QA），剂量计算算法的准确性至关重要，尤其是在癌症立体定向身体放射治疗（SBRT）中。本研究基于对两种广泛使用的算法的评估，即分析各向异性算法（AAA）和Acuros XB（AXB），这两种算法同时在内部开发的非均质胸部体模（HTP）和均质平板体模（HSP）中。为了评估两种算法之间的剂量测量差异，通过保持与实际患者治疗相同的监测单元和波束角度，对35名癌症患者的预处理QA计划进行了点剂量测量。通过使用AAA和AXB算法在两种培养基内的Eclipse治疗计划系统上计算剂量。在Edge线性加速器（LA）（Varian Medical Systems，Palo Alto，CA，USA）上交付计划，并使用0.01cc离子室和DOSE1静电计进行测量。对观察到的数据集进行统计分析，并计算和分析测量剂量和计划剂量之间的百分比（%）变化。对于AAA和AXB算法，发现所有QA计划的HTP内测量剂量和计划剂量之间的平均%变化分别为2.61（标准偏差[SD]:0.66）和2.19（SD:0.64）。然而，在HSP内部，AAA和AXB算法分别为1.79（SD:0.74）和1.64（SD:0.70）。HTP的测量剂量和计划剂量之间的平均%差异具有统计学意义，但在HSP内部发现其具有统计学意义（P<0.01）。Pearson相关系数检验显示，HTP内AAA和AXB以及HSP的测量剂量与计划剂量之间存在强正相关。从这项研究中获得的结果表明，由于实际患者身体是异质的，因此为了获得更真实的结果，必须在异质体模内而不是同质体模内进行患者特异性QA。此外，在均匀介质中，两种算法都能有效地预测剂量，然而，在异质介质中，AAA对剂量的预测过高/过低，而AXB与测量结果显示出良好的一致性。
{"title":"Dosimetric evaluation of analytic anisotropic algorithm and Acuros XB algorithm using in-house developed heterogeneous thorax phantom and homogeneous slab phantom for stereotactic body radiation therapy technique","authors":"S. Dubey, P. Bagdare, Sanjay Ghosh","doi":"10.4103/rpe.rpe_52_20","DOIUrl":"https://doi.org/10.4103/rpe.rpe_52_20","url":null,"abstract":"To perform patient-specific quality assurance (QA), the accuracy of the dose calculation algorithm is vital, especially in the lung cancer stereotactic body radiation therapy (SBRT). The present study is based on the evaluation of two widely used algorithms, analytical anisotropic algorithm (AAA) and Acuros XB (AXB) inside the in-house developed heterogeneous thorax phantom (HTP) and a homogeneous slab phantom (HSP) simultaneously. To evaluate dosimetric differences between the two algorithms, point dose measurement was performed for pretreatment QA plans of 35 lung cancer patients by keeping the same monitor units and beam angles as those for the actual patient treatment. The dose was calculated on the Eclipse treatment planning system inside both the medium by using both AAA and AXB algorithms. Plans were delivered on the Edge linear accelerator (LA) (Varian Medical Systems, Palo Alto, CA, USA), and measurements were taken by using a 0.01 cc ion chamber and DOSE1 electrometer. Statistical analysis was performed on the observed data set, and percentage (%) variations between the measured and planned doses were calculated and analyzed. The mean % variations between the measured and planned doses inside HTP for all QA plans were found to be 2.61 (standard deviation [SD]: 0.66) and 2.19 (SD: 0.64) for AAA and AXB algorithms, respectively. Whereas, inside HSP, it was found to be 1.79 (SD: 0.74) and 1.64 (SD: 0.70) for AAA and AXB algorithms, respectively. The mean % difference between the measured dose and the planned dose was derived to be statistically significant for HTP, however, it was found to be statistically insignificant inside the HSP at P < 0.01. The Pearson's correlation coefficient test showed a strong positive correlation between the measured dose and the planned dose for both AAA and AXB inside HTP as well for HSP. The results obtained from this study showed that as the actual patient body is heterogeneous, thus to get more realistic results, patient-specific QA must be performed inside the heterogeneous phantom instead of homogeneous. Moreover, in the homogeneous medium, both the algorithms predict the dose efficiently, however, in heterogeneous medium, AAA over/under predicts the dose, whereas AXB shows good concurrence with measurements.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"110 - 115"},"PeriodicalIF":0.0,"publicationDate":"2021-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47724042","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}
Optically stimulated luminescence (OSL) of quartz obtained from ceramics, concrete, and soil has been studied extensively for its use in retrospective dosimetry. The OSL properties of quartz separated from surface soil of different parts of India were investigated for its application as a retrospective dosimeter. Different parameters such as recuperation, recycling ratio, equivalent dose plateau, and relevant to single-aliquot regenerative protocol were investigated. The dose recovery tests were also performed. These studies show that the soil samples can be used for dose evaluation during any radiation accident.
{"title":"Thermoluminescence and optically stimulated luminescence studies of Indian soils for its application in retrospective dosimetry","authors":"S. Menon, S. Kadam","doi":"10.4103/rpe.rpe_8_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_8_21","url":null,"abstract":"Optically stimulated luminescence (OSL) of quartz obtained from ceramics, concrete, and soil has been studied extensively for its use in retrospective dosimetry. The OSL properties of quartz separated from surface soil of different parts of India were investigated for its application as a retrospective dosimeter. Different parameters such as recuperation, recycling ratio, equivalent dose plateau, and relevant to single-aliquot regenerative protocol were investigated. The dose recovery tests were also performed. These studies show that the soil samples can be used for dose evaluation during any radiation accident.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"98 - 102"},"PeriodicalIF":0.0,"publicationDate":"2021-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"44128937","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}
Deepu Radhakrishnan, M. Boopathy, V. Gopalakrishnan, P. Rakesh, S. Chandrasekaran, C. Srinivas, R. Venkatesan, B. Venkatraman
In this work, the analysis of the long-term environmental radiation monitoring data collected within the Department of Atomic Energy site, Kalpakkam using gamma monitors such as GammaTRACERS (GTs) from 2013 to 2018 and Autonomous Gamma Dose Loggers (AGDLs) located in the site boundary at distances from 1.25 to 2.5 km from 2016 to 2018 are presented with respect to dose variation in different locations/wind sectors/seasons. The average background dose rates are in the range of 140–220 nGy/h except at a location (GT2) where a dose rate of 400 ± 20 nGy/h is found. It is observed that the detectors generally measure the normal background doses and at times slightly higher doses (above background) due to exposure to 41Ar plume during normal operations from Madras Atomic Power Stations. The monitors were categorized into four groups: Group 1 to Group 4. Dose rates higher than normal were observed in Group 1 detectors during winter and North-east monsoon seasons and in Group 3 and Group 4 detectors during summer and South-west monsoon seasons and during January to March months in Group 2 detectors. The gamma dose rates during 41Ar plume transit vary in the range of 600–900 nGy/h. The cumulative annual effective doses at the site boundary, analyzed from 2016 to 2018, due to normal operational releases varied from 11 μSv to 114 μSv in different sectors which is significantly lower compared to annual dose limit (1000 μSv) for public.
{"title":"Long-term trends in gamma radiation monitoring at the multi-facility nuclear site, Kalpakkam, South-India","authors":"Deepu Radhakrishnan, M. Boopathy, V. Gopalakrishnan, P. Rakesh, S. Chandrasekaran, C. Srinivas, R. Venkatesan, B. Venkatraman","doi":"10.4103/rpe.rpe_18_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_18_21","url":null,"abstract":"In this work, the analysis of the long-term environmental radiation monitoring data collected within the Department of Atomic Energy site, Kalpakkam using gamma monitors such as GammaTRACERS (GTs) from 2013 to 2018 and Autonomous Gamma Dose Loggers (AGDLs) located in the site boundary at distances from 1.25 to 2.5 km from 2016 to 2018 are presented with respect to dose variation in different locations/wind sectors/seasons. The average background dose rates are in the range of 140–220 nGy/h except at a location (GT2) where a dose rate of 400 ± 20 nGy/h is found. It is observed that the detectors generally measure the normal background doses and at times slightly higher doses (above background) due to exposure to 41Ar plume during normal operations from Madras Atomic Power Stations. The monitors were categorized into four groups: Group 1 to Group 4. Dose rates higher than normal were observed in Group 1 detectors during winter and North-east monsoon seasons and in Group 3 and Group 4 detectors during summer and South-west monsoon seasons and during January to March months in Group 2 detectors. The gamma dose rates during 41Ar plume transit vary in the range of 600–900 nGy/h. The cumulative annual effective doses at the site boundary, analyzed from 2016 to 2018, due to normal operational releases varied from 11 μSv to 114 μSv in different sectors which is significantly lower compared to annual dose limit (1000 μSv) for public.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"79 - 91"},"PeriodicalIF":0.0,"publicationDate":"2021-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47313689","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}
This study presents the activity and outdoor gamma absorbed dose rates (terrestrial and cosmic) due to the naturally occurring (226Ra, 232Th, and 40K) and anthropogenic (137Cs) radionuclides around Kakrapar Gujarat site. The activity level (Bq/kg) in the soil ranged 5.7–48.4 for 226Ra, 9.7–28.0 for 232Th, 83.9–585.7 for 40K, and 0.2–4.6 for 137Cs, respectively. The mean concentration levels measured in Kakrapar soil from the naturally occurring radioisotopes are lower than the corresponding global average values. 137Cs activity in the soil is comparable with the preoperational period. The total effective dose rates in air outdoors ranged 17.2–78.1 μSv/y with the mean value of 32.8 μSv/y. The mean value of absorbed dose rate due to cosmic components was 37.5 nGy/h which is comparable to the worldwide reported values.
{"title":"Natural and fallout radioactivity mapping of Kakrapar Gujarat site, India","authors":"S. Wagh, A. Patra, I. Saradhi, A. Kumar","doi":"10.4103/rpe.rpe_16_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_16_21","url":null,"abstract":"This study presents the activity and outdoor gamma absorbed dose rates (terrestrial and cosmic) due to the naturally occurring (226Ra, 232Th, and 40K) and anthropogenic (137Cs) radionuclides around Kakrapar Gujarat site. The activity level (Bq/kg) in the soil ranged 5.7–48.4 for 226Ra, 9.7–28.0 for 232Th, 83.9–585.7 for 40K, and 0.2–4.6 for 137Cs, respectively. The mean concentration levels measured in Kakrapar soil from the naturally occurring radioisotopes are lower than the corresponding global average values. 137Cs activity in the soil is comparable with the preoperational period. The total effective dose rates in air outdoors ranged 17.2–78.1 μSv/y with the mean value of 32.8 μSv/y. The mean value of absorbed dose rate due to cosmic components was 37.5 nGy/h which is comparable to the worldwide reported values.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"92 - 97"},"PeriodicalIF":0.0,"publicationDate":"2021-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45124920","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}
Vedesh Varakhedkar, Sanjay Vanave, Aramana Baburajan, I. Saradhi
This report presents the directional dependence of surface scaling parameters, namely, roughness length and corresponding friction velocity, for neutral category at the Tarapur coastal site. The average roughness length of the lowest value of 0.5 m in the west (W) direction and the highest value of 0.885 m in the N direction has been observed and average friction velocity of the lowest value 0.39 m/s in the W direction and the highest value 0.73 m/s in the NW direction was observed for 2019. Sector average turbulent kinetic energy was estimated to be 1.413 m2/s2 and its dissipation rate as 0.33 m2/s3 for the 10 m elevation from the surface. Surface drag coefficient for the 10 m height was 0.0229 for the smooth ocean surface and 0.0255 for the land surface was observed for the Tarapur coastal site.
{"title":"Estimation of surface layer scaling parameters using SODAR for the coastal site of Tarapur","authors":"Vedesh Varakhedkar, Sanjay Vanave, Aramana Baburajan, I. Saradhi","doi":"10.4103/rpe.rpe_7_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_7_21","url":null,"abstract":"This report presents the directional dependence of surface scaling parameters, namely, roughness length and corresponding friction velocity, for neutral category at the Tarapur coastal site. The average roughness length of the lowest value of 0.5 m in the west (W) direction and the highest value of 0.885 m in the N direction has been observed and average friction velocity of the lowest value 0.39 m/s in the W direction and the highest value 0.73 m/s in the NW direction was observed for 2019. Sector average turbulent kinetic energy was estimated to be 1.413 m2/s2 and its dissipation rate as 0.33 m2/s3 for the 10 m elevation from the surface. Surface drag coefficient for the 10 m height was 0.0229 for the smooth ocean surface and 0.0255 for the land surface was observed for the Tarapur coastal site.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"103 - 109"},"PeriodicalIF":0.0,"publicationDate":"2021-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"41918383","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}
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