S. Sahu, M. Tiwari, R. Bhangare, V. Pulhani, AVinod Kumar
The distribution of naturally occurring radioactive materials (NORM) generated/discharged in nonnuclear industries such as coal combustion residuals from different coal-based power plants, fertilizer, construction, tobacco, and other industries into the environment, has not been reviewed in the Indian context. In the present review, systematic survey and analysis of the reported occurrence of U238, Th232, and K40 in these nonnuclear industrial sectors is discussed. Most of the data compiled and described in this review are sourced from major popularly referred, peer-reviewed scientific journal publications since the year 2005. Apart from radioactivity levels in products from nonnuclear industrial sectors different radiological indices such as absorbed dose, dose rate, etc., are also compared and discussed. Overall, this review presents a comprehensive analysis of NORMs in nonnuclear industrial sectors of India.
{"title":"A review on current status of radioactivity monitoring in Indian nonnuclear industries","authors":"S. Sahu, M. Tiwari, R. Bhangare, V. Pulhani, AVinod Kumar","doi":"10.4103/rpe.rpe_31_22","DOIUrl":"https://doi.org/10.4103/rpe.rpe_31_22","url":null,"abstract":"The distribution of naturally occurring radioactive materials (NORM) generated/discharged in nonnuclear industries such as coal combustion residuals from different coal-based power plants, fertilizer, construction, tobacco, and other industries into the environment, has not been reviewed in the Indian context. In the present review, systematic survey and analysis of the reported occurrence of U238, Th232, and K40 in these nonnuclear industrial sectors is discussed. Most of the data compiled and described in this review are sourced from major popularly referred, peer-reviewed scientific journal publications since the year 2005. Apart from radioactivity levels in products from nonnuclear industrial sectors different radiological indices such as absorbed dose, dose rate, etc., are also compared and discussed. Overall, this review presents a comprehensive analysis of NORMs in nonnuclear industrial sectors of India.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"46 1","pages":"3 - 13"},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"44510147","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}
TK Srinivasan, P. Annadurai, Akila Raghuraman, R. Sarangapani
Gamma spectrometry of the KAMINI reactor coolant lines at the selected spots/locations was carried out during 20kWt power and shutdown using portable spectrometers such as RIIDEye-X, RayMon (Cadmium Zinc Telluride), and hyper pure germanium.133Xe (81 keV),85m Kr (150 keV), and 135Xe (250 keV) isotopes could be identified. The spectra results did not indicate the presence of internal contamination due to any corrosion activation products such as 56Mn, 59Fe, 60Co, and fission products. The gamma radiation level observed during reactor power on the selected locations is only due to the fission product noble gases (FPNGs) and their short-lived radionuclides 88Rb and 138Cs generated and not any pipeline internal contamination.137Cs and trace quantities of 60Co were identified in the mixed bed regenerated liquid. The presence of 137Cs could be attributed due to the tramp fuel fissions.
{"title":"Gamma spectrometry of coolant lines of KAMINI reactor","authors":"TK Srinivasan, P. Annadurai, Akila Raghuraman, R. Sarangapani","doi":"10.4103/rpe.rpe_30_23","DOIUrl":"https://doi.org/10.4103/rpe.rpe_30_23","url":null,"abstract":"Gamma spectrometry of the KAMINI reactor coolant lines at the selected spots/locations was carried out during 20kWt power and shutdown using portable spectrometers such as RIIDEye-X, RayMon (Cadmium Zinc Telluride), and hyper pure germanium.133Xe (81 keV),85m Kr (150 keV), and 135Xe (250 keV) isotopes could be identified. The spectra results did not indicate the presence of internal contamination due to any corrosion activation products such as 56Mn, 59Fe, 60Co, and fission products. The gamma radiation level observed during reactor power on the selected locations is only due to the fission product noble gases (FPNGs) and their short-lived radionuclides 88Rb and 138Cs generated and not any pipeline internal contamination.137Cs and trace quantities of 60Co were identified in the mixed bed regenerated liquid. The presence of 137Cs could be attributed due to the tramp fuel fissions.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"46 1","pages":"33 - 39"},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47658086","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}
Tejpal Menaria, D. Rathore, S. Tiwari, A. Patra, I. Saradhi, AVinod Kumar
Water samples collected from water resources in Chittorgarh district of Rajasthan were processed radiochemically to evaluate uranium concentration along with associated geochemical parameters. LED fluorimetry was used to measure uranium concentration, while multi-parameter kits were used to evaluate the geochemical parameters. The mean uranium concentration was 14.0 ± 11.4 μgL−1 in the premonsoon period and 16.3 ± 13.2 μgL−1 in the postmonsoon period, which was found to be within the limit of 30 μgL−1, as recommended by the Bureau of Indian Standards (BIS, 2021). Geochemical parameters such as pH, conductivity, total dissolved solid (TDS), oxidation reduction potential, dissolved oxygen, chloride, fluoride, nitrate, hardness, and alkalinity ranged from 7.1–9.4, 226–4540 μScm−1, 125–2630 ppm, 149–287 mV, 9.1–11.4 ppm, 14–690 ppm, 0.1–2.2 ppm, 12–181 ppm, 135–990 ppm, and 129–1266 ppm, respectively. TDS, hardness, alkalinity, and nitrate were observed to be higher than the BIS limit at some locations. Maximum geochemical parameters were within the guidance limit for drinking water (BIS, 2012) excluding nitrate. The distribution of geochemical parameters and uranium content were vastly heterogeneous, signifying the influence of regional lithology and geochemistry.
{"title":"Uranium distribution and its correlation with geochemical parameters in Chittorgarh district of Rajasthan, India","authors":"Tejpal Menaria, D. Rathore, S. Tiwari, A. Patra, I. Saradhi, AVinod Kumar","doi":"10.4103/rpe.rpe_20_23","DOIUrl":"https://doi.org/10.4103/rpe.rpe_20_23","url":null,"abstract":"Water samples collected from water resources in Chittorgarh district of Rajasthan were processed radiochemically to evaluate uranium concentration along with associated geochemical parameters. LED fluorimetry was used to measure uranium concentration, while multi-parameter kits were used to evaluate the geochemical parameters. The mean uranium concentration was 14.0 ± 11.4 μgL−1 in the premonsoon period and 16.3 ± 13.2 μgL−1 in the postmonsoon period, which was found to be within the limit of 30 μgL−1, as recommended by the Bureau of Indian Standards (BIS, 2021). Geochemical parameters such as pH, conductivity, total dissolved solid (TDS), oxidation reduction potential, dissolved oxygen, chloride, fluoride, nitrate, hardness, and alkalinity ranged from 7.1–9.4, 226–4540 μScm−1, 125–2630 ppm, 149–287 mV, 9.1–11.4 ppm, 14–690 ppm, 0.1–2.2 ppm, 12–181 ppm, 135–990 ppm, and 129–1266 ppm, respectively. TDS, hardness, alkalinity, and nitrate were observed to be higher than the BIS limit at some locations. Maximum geochemical parameters were within the guidance limit for drinking water (BIS, 2012) excluding nitrate. The distribution of geochemical parameters and uranium content were vastly heterogeneous, signifying the influence of regional lithology and geochemistry.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"46 1","pages":"25 - 32"},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"43045675","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":"The International Commission on Radiological Protection general recommendations: Future expectations","authors":"D. Rao","doi":"10.4103/rpe.rpe_41_23","DOIUrl":"https://doi.org/10.4103/rpe.rpe_41_23","url":null,"abstract":"","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"46 1","pages":"1 - 2"},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"44236628","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 exposure from natural sources of radiation imparts a major contribution to doses, both due to external and internal exposures that would be received by members of public, and its levels rely upon the lithology, altitude, and building construction materials. The measurement results of ambient indoor and outdoor radiation levels at 28 locations (villages) of Reasi district, Jammu and Kashmir, India, are presented. The ambient radiation levels were measured utilizing a portable gamma survey meter. For the outdoor environment, the minimum and maximum gamma dose rates were 0.09 and 0.29 μSv/h, whereas, at indoors, the minimum and maximum gamma dose rates were 0.08 and 0.22 μSv/h, respectively. Impact of elevation (height above sea level) on radiation levels has been investigated, and it revealed a weak positive relationship with altitude. Effects of lithology on indoor and outdoor gamma dose rates have likewise been investigated. The average annual effective dose value due to ambient radiation levels was well within the world average values.
{"title":"Variation of annual indoor and outdoor gamma dose rate in the lower Himalayan region of Reasi district of Jammu and Kashmir, India","authors":"Ajay Kumar, Sumit Sharma, D. Sharma","doi":"10.4103/rpe.rpe_32_22","DOIUrl":"https://doi.org/10.4103/rpe.rpe_32_22","url":null,"abstract":"The exposure from natural sources of radiation imparts a major contribution to doses, both due to external and internal exposures that would be received by members of public, and its levels rely upon the lithology, altitude, and building construction materials. The measurement results of ambient indoor and outdoor radiation levels at 28 locations (villages) of Reasi district, Jammu and Kashmir, India, are presented. The ambient radiation levels were measured utilizing a portable gamma survey meter. For the outdoor environment, the minimum and maximum gamma dose rates were 0.09 and 0.29 μSv/h, whereas, at indoors, the minimum and maximum gamma dose rates were 0.08 and 0.22 μSv/h, respectively. Impact of elevation (height above sea level) on radiation levels has been investigated, and it revealed a weak positive relationship with altitude. Effects of lithology on indoor and outdoor gamma dose rates have likewise been investigated. The average annual effective dose value due to ambient radiation levels was well within the world average values.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"46 1","pages":"46 - 52"},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"42398023","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":"Note on the 6th Asian and Oceanic Congress for Radiation Protection: AOCRP-6","authors":"M. Kulkarni","doi":"10.4103/rpe.rpe_42_23","DOIUrl":"https://doi.org/10.4103/rpe.rpe_42_23","url":null,"abstract":"","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"46 1","pages":"60 - 61"},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47122804","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}
Thoron is an emerging field of study due to recent realization of its radiological significance. A code has been developed for determination of dose conversion factor (DCF) of thoron progeny based on the revised International Commission on Radiological Protection 130 human respiratory tract model. Using this code, DCF for an adult male doing light exercise with a breathing rate (BR) of 0.75 m3 h−1 was found to be 35.7 nSv h−1 per Bq m−3 which is very close to the UNSCEAR proposed value. If the BR increased to 1.2 m3 h−1 as considered in case of occupational workers, DCF increases by a factor of 1.5. Along with the BR, DCF was also observed to be largely dependent on the particle size of the thoron progeny.
钍是一个新兴的研究领域，由于最近认识到它的放射意义。根据经修订的国际放射防护委员会130人呼吸道模型，制定了一套测定钍子代剂量转换因子的规范。使用此代码，发现呼吸频率(BR)为0.75 m3 h−1的轻度运动的成年男性的DCF为35.7 nSv h−1 / Bq m−3，非常接近UNSCEAR建议的值。如果职业工人的BR增加到1.2 m3 h−1，则DCF增加1.5倍。与BR一样，DCF也被观察到在很大程度上依赖于thoron子代的颗粒大小。
{"title":"Estimation of dose conversion factor of thoron progeny using ICRP 130 human respiratory tract model","authors":"R. Rout, R. Mishra, ArshadT Khan, B. Sapra","doi":"10.4103/rpe.rpe_21_23","DOIUrl":"https://doi.org/10.4103/rpe.rpe_21_23","url":null,"abstract":"Thoron is an emerging field of study due to recent realization of its radiological significance. A code has been developed for determination of dose conversion factor (DCF) of thoron progeny based on the revised International Commission on Radiological Protection 130 human respiratory tract model. Using this code, DCF for an adult male doing light exercise with a breathing rate (BR) of 0.75 m3 h−1 was found to be 35.7 nSv h−1 per Bq m−3 which is very close to the UNSCEAR proposed value. If the BR increased to 1.2 m3 h−1 as considered in case of occupational workers, DCF increases by a factor of 1.5. Along with the BR, DCF was also observed to be largely dependent on the particle size of the thoron progeny.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"46 1","pages":"19 - 24"},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"48611359","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}
Cryogenic materials, widely used in industries and facilities associated with nuclear technology and science and radiological applications, pose occupational health and safety hazards owing to their unique properties. The major health hazards include cold burns, asphyxiation, hot burns, and major safety hazards are explosion, fire, and equipment failure. Risk assessment consistent with material safety data sheet and hazard analysis is essential to assess the potential dangers while using cryogenic materials. Safe handling of cryogenic materials in nuclear and radiological facilities requires special considerations to ensure the protection of personnel and the environment. Administrative measures such as access control, training, checklists, and engineering controls such as ventilation, gas detection systems, and purging techniques are applied to deal with cryogenic hazards. Many personal proactive equipments are available to protect users from cryogenic hazards. While some protective measures for cryogenic hazards could suffice for low radioactivity laboratories, additional personal protective equipments are required to protect workers from radiation exposure in workplaces with potentially significant radiation hazards. The formulation of preparedness plans for emergencies resulting from cryogenic hazards should essentially take into account the unique constraints and requirements of radiological facilities. Simultaneous occurrence of radiological and cryogenic emergencies presents complex challenges requiring special mitigative measures.
{"title":"Occupational health and safety aspects in the handling of cryogenic materials in nuclear and radiological facilities","authors":"Vyom Saxena","doi":"10.4103/rpe.rpe_31_23","DOIUrl":"https://doi.org/10.4103/rpe.rpe_31_23","url":null,"abstract":"Cryogenic materials, widely used in industries and facilities associated with nuclear technology and science and radiological applications, pose occupational health and safety hazards owing to their unique properties. The major health hazards include cold burns, asphyxiation, hot burns, and major safety hazards are explosion, fire, and equipment failure. Risk assessment consistent with material safety data sheet and hazard analysis is essential to assess the potential dangers while using cryogenic materials. Safe handling of cryogenic materials in nuclear and radiological facilities requires special considerations to ensure the protection of personnel and the environment. Administrative measures such as access control, training, checklists, and engineering controls such as ventilation, gas detection systems, and purging techniques are applied to deal with cryogenic hazards. Many personal proactive equipments are available to protect users from cryogenic hazards. While some protective measures for cryogenic hazards could suffice for low radioactivity laboratories, additional personal protective equipments are required to protect workers from radiation exposure in workplaces with potentially significant radiation hazards. The formulation of preparedness plans for emergencies resulting from cryogenic hazards should essentially take into account the unique constraints and requirements of radiological facilities. Simultaneous occurrence of radiological and cryogenic emergencies presents complex challenges requiring special mitigative measures.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"46 1","pages":"40 - 45"},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46207067","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}
Natural radionuclides from building materials are one of the potential sources of external as well as internal radiation exposure to the human body. Currently, this exposure has been increasing since people spend more than their time indoors. In this study, 16 cement samples collected from Abidjan district were analyzed using a high-resolution high-purity germanium gamma spectrometry. Activity concentrations of primordial radionuclides 226Ra, 232Th, and 40K were found with mean specific activities of 9.95 ± 1.94 Bq/kg, 21.81 ± 3.2 Bq/kg, and 196.50 ± 4.5 Bq/kg, respectively. The obtained data were below world average values of 35, 30, and 400 Bq/kg. Radiological parameters such as radium equivalent activity, absorbed dose rate (D), and annual effective dose were calculated and compared to the worldwide average values. Further, statistical analyses were performed and discussed for the resulted data. The estimated radiological indices were below the recommended levels; therefore, the study shows that the measured radioactivity for cement does not pose a significant source of radiation and is safe for use in the construction of dwellings. The data from this study can be used as a reference for future studies on building materials in Côte d'Ivoire and by other researchers around the world.
{"title":"Determination of natural radioactivity and health risks of cement in Abidjan District, Côte d'Ivoire","authors":"Samafou Penabeï, Jean-ClaudeOlkalé Brigui, BogbéDouo Louis Huberson Gogon, Koudou Djagouri, GeorgesAlain Monnehan","doi":"10.4103/rpe.rpe_35_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_35_21","url":null,"abstract":"Natural radionuclides from building materials are one of the potential sources of external as well as internal radiation exposure to the human body. Currently, this exposure has been increasing since people spend more than their time indoors. In this study, 16 cement samples collected from Abidjan district were analyzed using a high-resolution high-purity germanium gamma spectrometry. Activity concentrations of primordial radionuclides 226Ra, 232Th, and 40K were found with mean specific activities of 9.95 ± 1.94 Bq/kg, 21.81 ± 3.2 Bq/kg, and 196.50 ± 4.5 Bq/kg, respectively. The obtained data were below world average values of 35, 30, and 400 Bq/kg. Radiological parameters such as radium equivalent activity, absorbed dose rate (D), and annual effective dose were calculated and compared to the worldwide average values. Further, statistical analyses were performed and discussed for the resulted data. The estimated radiological indices were below the recommended levels; therefore, the study shows that the measured radioactivity for cement does not pose a significant source of radiation and is safe for use in the construction of dwellings. The data from this study can be used as a reference for future studies on building materials in Côte d'Ivoire and by other researchers around the world.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"136217029","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":"What is required to make nuclear power acceptable to public?","authors":"M. Iyer","doi":"10.4103/rpe.rpe_24_23","DOIUrl":"https://doi.org/10.4103/rpe.rpe_24_23","url":null,"abstract":"","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"45 1","pages":"105 - 106"},"PeriodicalIF":0.0,"publicationDate":"2022-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45103230","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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