Pub Date : 2018-11-05DOI: 10.11648/J.NS.20180302.11
Z. A. Mansoor, Takrid Muneam Nafae, Ali Kareem K. Jelaot
Eight samples of cement were collected from different commercial factories (Al-Koufa, Al-Basra, Al-Najaf and Kerkouk factories) located in Iraq. They were analyzed using a gamma ray spectroscopy system. The activity concentrations of 226Ra, 232Th and 40K were ranged from 5.8 to 43.17 Bq kg-1, from 0.99 to 55.79 Bq kg-1 and from 53.28 to 185.34 Bq kg-1, respectively. The potential radiological hazards were assessed by calculating the radium equivalent activity (Raeq), the indoor absorbed gamma dose rate (D), the annual effective dose equivalent (AEDE), the alpha index (Iα), the gamma index (Iγ), and the external hazard (Hex) and internal hazard (Hin) indices. The highest value of Raeq is estimated of 101.36 Bq kg-1, which is significantly less than the upper limit of 370 Bq kg-1. The estimated maximum value of the absorbed gamma dose rate of 54.71 nGy h-1 is within the world average value of 55 nGy h-1, and the annual effective dose equivalent in the studied samples were 0.05 (outdoor), 0.18 (indoor) mSv y-1, which is lower than the recommended limit reported in the UNSCEAR (2000). The values of the hazard indices were below the recommended levels; therefore, the study shows that the measured radioactivity for cement does not pose as significant source of radiation hazard and is safe for use in the construction of dwellings.
{"title":"Assessment of Natural Radioactivity Levels and Radiological Hazards of Cement in Iraq","authors":"Z. A. Mansoor, Takrid Muneam Nafae, Ali Kareem K. Jelaot","doi":"10.11648/J.NS.20180302.11","DOIUrl":"https://doi.org/10.11648/J.NS.20180302.11","url":null,"abstract":"Eight samples of cement were collected from different commercial factories (Al-Koufa, Al-Basra, Al-Najaf and Kerkouk factories) located in Iraq. They were analyzed using a gamma ray spectroscopy system. The activity concentrations of 226Ra, 232Th and 40K were ranged from 5.8 to 43.17 Bq kg-1, from 0.99 to 55.79 Bq kg-1 and from 53.28 to 185.34 Bq kg-1, respectively. The potential radiological hazards were assessed by calculating the radium equivalent activity (Raeq), the indoor absorbed gamma dose rate (D), the annual effective dose equivalent (AEDE), the alpha index (Iα), the gamma index (Iγ), and the external hazard (Hex) and internal hazard (Hin) indices. The highest value of Raeq is estimated of 101.36 Bq kg-1, which is significantly less than the upper limit of 370 Bq kg-1. The estimated maximum value of the absorbed gamma dose rate of 54.71 nGy h-1 is within the world average value of 55 nGy h-1, and the annual effective dose equivalent in the studied samples were 0.05 (outdoor), 0.18 (indoor) mSv y-1, which is lower than the recommended limit reported in the UNSCEAR (2000). The values of the hazard indices were below the recommended levels; therefore, the study shows that the measured radioactivity for cement does not pose as significant source of radiation hazard and is safe for use in the construction of dwellings.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"95 1","pages":"23"},"PeriodicalIF":0.0,"publicationDate":"2018-11-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80820541","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}
Pub Date : 2018-05-17DOI: 10.11648/J.NS.20180301.13
Esraa Al-Sarray, A. Jabbar
A hidden danger, no color and no taste for nuclear radiation that can have effects in human health While increasing the use of ionizing radiation The risk of health increases If is not used or contained correctly. And in order to avoid the risks of this radiation to the health of workers And clients With these radiations to look for a continuous and extensive search In all materials that can protect them from this radiation. These materials must be inherently harmless, with a low material cost. In this study, four samples were done with different mixing ratios for studying the attenuation coefficient of gamma rays and beta particles barriers made of polymer, epoxy, FeSO4.7H2O compounds in addition to Eggshells and in certain proportions and the use of these samples measure the attenuation coefficient of gamma rays and beta particles using radioactive sources. (Caesium-137 and Strontium-90). At the end of this research the ability of Eggshells to attenuate beta particles and excelled On FeSO4.7H2O compounds. The gamma attenuation coefficient is very close to FeSO4.7H2O compounds. These readings were taken at the Directorate of Treatment and Management of Iraqi Radioactive Waste based.
{"title":"Investigate the Ability of the Eggshell to Attenuate the Gamma and Beta Rays as Compared with Composite FeSO 4 .7H 2 O","authors":"Esraa Al-Sarray, A. Jabbar","doi":"10.11648/J.NS.20180301.13","DOIUrl":"https://doi.org/10.11648/J.NS.20180301.13","url":null,"abstract":"A hidden danger, no color and no taste for nuclear radiation that can have effects in human health While increasing the use of ionizing radiation The risk of health increases If is not used or contained correctly. And in order to avoid the risks of this radiation to the health of workers And clients With these radiations to look for a continuous and extensive search In all materials that can protect them from this radiation. These materials must be inherently harmless, with a low material cost. In this study, four samples were done with different mixing ratios for studying the attenuation coefficient of gamma rays and beta particles barriers made of polymer, epoxy, FeSO4.7H2O compounds in addition to Eggshells and in certain proportions and the use of these samples measure the attenuation coefficient of gamma rays and beta particles using radioactive sources. (Caesium-137 and Strontium-90). At the end of this research the ability of Eggshells to attenuate beta particles and excelled On FeSO4.7H2O compounds. The gamma attenuation coefficient is very close to FeSO4.7H2O compounds. These readings were taken at the Directorate of Treatment and Management of Iraqi Radioactive Waste based.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"26 1","pages":"16"},"PeriodicalIF":0.0,"publicationDate":"2018-05-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77460398","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}
Pub Date : 2018-04-08DOI: 10.11648/J.NS.20180301.12
G. Tektas, C. Celiktas
A virtual delay generator was developed via software by considering the features of a real ‘gate and delay generator’. The signals supplied from a pulse generator were processed with a preamplifier, an amplifier and a timing single channel analyzer (SCA) and, the SCA output signals were transferred to the real ‘gate and delay generator’ (real instrument) and the virtual delay generator (virtual instrument; VI) simultaneously. They were compared with each other by changing amplitude, delay time and width values of the output signals from both instruments. It was found that the results from the virtual generator were highly in compatible with those of the real one. Obtained results showed that the developed virtual delay generator could be used as the real one.
{"title":"A Virtual Delay Generator Design and Its Application","authors":"G. Tektas, C. Celiktas","doi":"10.11648/J.NS.20180301.12","DOIUrl":"https://doi.org/10.11648/J.NS.20180301.12","url":null,"abstract":"A virtual delay generator was developed via software by considering the features of a real ‘gate and delay generator’. The signals supplied from a pulse generator were processed with a preamplifier, an amplifier and a timing single channel analyzer (SCA) and, the SCA output signals were transferred to the real ‘gate and delay generator’ (real instrument) and the virtual delay generator (virtual instrument; VI) simultaneously. They were compared with each other by changing amplitude, delay time and width values of the output signals from both instruments. It was found that the results from the virtual generator were highly in compatible with those of the real one. Obtained results showed that the developed virtual delay generator could be used as the real one.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"28 1","pages":"9"},"PeriodicalIF":0.0,"publicationDate":"2018-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84261376","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}
Pub Date : 2018-01-15DOI: 10.11648/j.ns.20170204.11
H. Mansour, Y. M. Z. Al-bakhat, H. N. Karkosh
Samples of flowered grasses, herbs and jungles were collected from scrap yard (B) at Al-Tuwaitha Nuclear Site and analyzed in the laboratory using gamma-ray spectroscopy system. The activity concentrations for radionuclides grown on the studied area were found to be ranged from 1.05 to 5.45 Bq/kg (average 2.86 Bq/kg) for 226Ra, below detection limit (BDL) to 1.4 Bq/kg (average 0.16 Bq/kg) for 232Th, 483.2 to 595.7 Bq/kg (average 528.33 Bq/kg) for 40K, and BDL to 1.15 Bq/kg (average 0.35 Bq/kg) for 235U. No radionuclides of artificial origin (such as 137Cs) were detected in any of the analyzed samples. Gamma absorbed dose rates (D), radium equivalent activities (Raeq), external hazard index (Hex), and internal hazard index (Hin) were calculated and found to be considerably lower than their corresponding allowable limits and worldwide average values. Accordingly, it was found that natural radioactivity levels for the investigated plants species grown at the studied area pose no significant radiological threat to human health or the environment.
{"title":"Measurement of Radioactivity Levels and Assessment of Radiation Hazards for Plants Species Grown at Scrap Yard (B) at Al-Tuwaitha Nuclear Site (Iraq)","authors":"H. Mansour, Y. M. Z. Al-bakhat, H. N. Karkosh","doi":"10.11648/j.ns.20170204.11","DOIUrl":"https://doi.org/10.11648/j.ns.20170204.11","url":null,"abstract":"Samples of flowered grasses, herbs and jungles were collected from scrap yard (B) at Al-Tuwaitha Nuclear Site and analyzed in the laboratory using gamma-ray spectroscopy system. The activity concentrations for radionuclides grown on the studied area were found to be ranged from 1.05 to 5.45 Bq/kg (average 2.86 Bq/kg) for 226Ra, below detection limit (BDL) to 1.4 Bq/kg (average 0.16 Bq/kg) for 232Th, 483.2 to 595.7 Bq/kg (average 528.33 Bq/kg) for 40K, and BDL to 1.15 Bq/kg (average 0.35 Bq/kg) for 235U. No radionuclides of artificial origin (such as 137Cs) were detected in any of the analyzed samples. Gamma absorbed dose rates (D), radium equivalent activities (Raeq), external hazard index (Hex), and internal hazard index (Hin) were calculated and found to be considerably lower than their corresponding allowable limits and worldwide average values. Accordingly, it was found that natural radioactivity levels for the investigated plants species grown at the studied area pose no significant radiological threat to human health or the environment.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"167 1","pages":"94"},"PeriodicalIF":0.0,"publicationDate":"2018-01-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73927361","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}
Pub Date : 2017-08-14DOI: 10.11648/j.ns.20170203.13
W. Pereira, A. Kelecom, Ademir X. Silva, S. B. Magalhães
Ionizing radiation can expose individuals, and this exposure may cause deleterious biological effects. Protection against these effects, called radioprotection is accomplished through actions at the source, on the exposure routes and on the individual. It is assumed a proportional relationship between increased exposure and increased risk of stochastic effects of exposure. This approach allows dividing the network events and exposure situations and evaluating steps which are important for radioprotection. The aim of this study is to evaluate the state of the art radiation protection recommendations published by the International Commission on Radiological Protection (ICRP). For operational reasons, the radioprotection needs to perform simplifications in the relations between sources and biological effects. The last simplification was made in 2007, dividing the relations according to the sources and individuals. The principles of radioprotection (justification, dose limitation and optimization) were maintained and strengthened. The ratio depending on the source allowed the inclusion in the sources of regulatory framework previously not included and definitions of dose constraint concepts and reference levels. All this, when used with the principle of optimization of radiation protection can restrict individual doses. The maintenance of the three radiation protection principles demonstrates the robustness of these principles, as well as the maintenance of the dose limits demonstrates the confidence of the radioprotection community in the safety of these limits. Brazilian radioprotection did not reach yet the state of the art described here and is still based on ICRP previous recommendation edited in 1990, but being the legal regulations for Brazil they must be obeyed. All legislation based on ICRP No 60 and subsequent recommendations are able to protect quite adequately the environment and workers, although they are not in the state of the art as defined by the ICRP No 103 and subsequent recommendations.
{"title":"The State of the Art of the World Radioprotection System","authors":"W. Pereira, A. Kelecom, Ademir X. Silva, S. B. Magalhães","doi":"10.11648/j.ns.20170203.13","DOIUrl":"https://doi.org/10.11648/j.ns.20170203.13","url":null,"abstract":"Ionizing radiation can expose individuals, and this exposure may cause deleterious biological effects. Protection against these effects, called radioprotection is accomplished through actions at the source, on the exposure routes and on the individual. It is assumed a proportional relationship between increased exposure and increased risk of stochastic effects of exposure. This approach allows dividing the network events and exposure situations and evaluating steps which are important for radioprotection. The aim of this study is to evaluate the state of the art radiation protection recommendations published by the International Commission on Radiological Protection (ICRP). For operational reasons, the radioprotection needs to perform simplifications in the relations between sources and biological effects. The last simplification was made in 2007, dividing the relations according to the sources and individuals. The principles of radioprotection (justification, dose limitation and optimization) were maintained and strengthened. The ratio depending on the source allowed the inclusion in the sources of regulatory framework previously not included and definitions of dose constraint concepts and reference levels. All this, when used with the principle of optimization of radiation protection can restrict individual doses. The maintenance of the three radiation protection principles demonstrates the robustness of these principles, as well as the maintenance of the dose limits demonstrates the confidence of the radioprotection community in the safety of these limits. Brazilian radioprotection did not reach yet the state of the art described here and is still based on ICRP previous recommendation edited in 1990, but being the legal regulations for Brazil they must be obeyed. All legislation based on ICRP No 60 and subsequent recommendations are able to protect quite adequately the environment and workers, although they are not in the state of the art as defined by the ICRP No 103 and subsequent recommendations.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"18 1","pages":"87"},"PeriodicalIF":0.0,"publicationDate":"2017-08-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89513739","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}
Pub Date : 2017-08-01DOI: 10.11648/J.NS.20170203.12
W. R. Campbell, Jerry Chen
Understanding the Grid to rod fretting wear (GTRFW) initiation is critical for reducing the risk of fuel leak. In this paper, a simplified 3D FEA model is set up to analyze its mechanics. The initiation of GTRFW under a series of interferences was modeled and analyzed. It is found that slip and wear usually initiate from the edge of the grid to rod contact contour and eventually propagates to the entire contour. Due to the stress concentration, the contact at sharp corners should be avoided.
{"title":"An Analysis of GTRFW Initiation Using Finite Element Method","authors":"W. R. Campbell, Jerry Chen","doi":"10.11648/J.NS.20170203.12","DOIUrl":"https://doi.org/10.11648/J.NS.20170203.12","url":null,"abstract":"Understanding the Grid to rod fretting wear (GTRFW) initiation is critical for reducing the risk of fuel leak. In this paper, a simplified 3D FEA model is set up to analyze its mechanics. The initiation of GTRFW under a series of interferences was modeled and analyzed. It is found that slip and wear usually initiate from the edge of the grid to rod contact contour and eventually propagates to the entire contour. Due to the stress concentration, the contact at sharp corners should be avoided.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"34 1","pages":"82"},"PeriodicalIF":0.0,"publicationDate":"2017-08-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86954299","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}
Pub Date : 2017-05-05DOI: 10.11648/j.ns.20170203.11
F. Galetto
Statistics is used in Physics (and in Nuclear Science as well): Six Sigma can be useful if properly applied; therefore scientists have to take into account the “correct” ideas. The document shows the ideas of the author to overcome the deep ignorance on Quality as it is found in many books dealing with Statistical Quality Control and Six Sigma. It is evident that there are many types of falseness provided by the “6 SigMONA practitioners”: they rob money from their clients that are not aware of that. When the 6σ BMWists say “A company’s performance is measured by the sigma level of their business processes” they lie: they do not know that, IF they compute s from the company’s data, they know the estimate s (NOT σ) AND s is never equal to σ! The 1st falseness is the statement “variation is the enemy of Quality”. The 2nd falseness is the statement “variability reduction is Quality”. The 3rd falseness is the wide-spread use of the “Normal Distribution”. The 4th falseness is the statement “the number of defectives is 3.4 ppm”. The “6 SigMONA movement” does not deal properly with problem prevention, as on the contrary is done by GIQA. Scientificness is absent in the “6 SigMONA applications” as shown in the authors books.
{"title":"Six Sigma Hoax: The Way Professionals Deceive Science","authors":"F. Galetto","doi":"10.11648/j.ns.20170203.11","DOIUrl":"https://doi.org/10.11648/j.ns.20170203.11","url":null,"abstract":"Statistics is used in Physics (and in Nuclear Science as well): Six Sigma can be useful if properly applied; therefore scientists have to take into account the “correct” ideas. The document shows the ideas of the author to overcome the deep ignorance on Quality as it is found in many books dealing with Statistical Quality Control and Six Sigma. It is evident that there are many types of falseness provided by the “6 SigMONA practitioners”: they rob money from their clients that are not aware of that. When the 6σ BMWists say “A company’s performance is measured by the sigma level of their business processes” they lie: they do not know that, IF they compute s from the company’s data, they know the estimate s (NOT σ) AND s is never equal to σ! The 1st falseness is the statement “variation is the enemy of Quality”. The 2nd falseness is the statement “variability reduction is Quality”. The 3rd falseness is the wide-spread use of the “Normal Distribution”. The 4th falseness is the statement “the number of defectives is 3.4 ppm”. The “6 SigMONA movement” does not deal properly with problem prevention, as on the contrary is done by GIQA. Scientificness is absent in the “6 SigMONA applications” as shown in the authors books.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"41 1","pages":"59"},"PeriodicalIF":0.0,"publicationDate":"2017-05-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78983073","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}
Pub Date : 2017-04-12DOI: 10.11648/J.NS.20170202.14
Ali Mehdi, K. Khan, A. Jabbar, Abdul Rashid
Due to constant exposure of Human beings to radiation caused by terrestrial, extra-terrestrial and anthropogenic radio nuclides, it is necessary to determine/estimate the activity of various radio nuclides in environmental media such as vegetation, soil, and water. In the present research, the activities of 226Ra, 232Th and 40K are measured in soil, vegetation and water samples, collected from Talagang Tehsil-District Chakwal of Pakistan using a HPGe based gamma spectrometry system. The measured mean activity of 226Ra, 232Th and 40K in soil samples was found to be 31.19±1.2, 47.00±2.30 and 589.31±17.52 Bqkg-1, respectively. The measured mean activity of these radionuclides in all water samples was found to be below minimum detectable activity. The measured mean activity of 226Ra, 232Th and 40K in vegetation samples was 19.92±3.09, 25.36±8.11 and 4982.94±85.68 Bqkg-1, respectively. No anthropogenic 137Cs was detected in these environmental samples. Mean radium equivalent activity (Raeq), external radiation hazard index (Hex), internal radiation hazard index (Hin) and absorbed dose rate (D) for the area under study were determined as 142.92 Bqkg-1, 0.38, 0.47 and 66.47 nGyh-1, respectively. The annual effective dose equivalent (AEDE) varied in the range from 0.03 to 0.12 mSv y-1. It is concluded that the surveyed area do not pose any significant radiological risk to the population and environment.
{"title":"Measurement of Gamma Emitting Radionuclides in Environmental Samples of Talagang Tehsil-District Chakwal","authors":"Ali Mehdi, K. Khan, A. Jabbar, Abdul Rashid","doi":"10.11648/J.NS.20170202.14","DOIUrl":"https://doi.org/10.11648/J.NS.20170202.14","url":null,"abstract":"Due to constant exposure of Human beings to radiation caused by terrestrial, extra-terrestrial and anthropogenic radio nuclides, it is necessary to determine/estimate the activity of various radio nuclides in environmental media such as vegetation, soil, and water. In the present research, the activities of 226Ra, 232Th and 40K are measured in soil, vegetation and water samples, collected from Talagang Tehsil-District Chakwal of Pakistan using a HPGe based gamma spectrometry system. The measured mean activity of 226Ra, 232Th and 40K in soil samples was found to be 31.19±1.2, 47.00±2.30 and 589.31±17.52 Bqkg-1, respectively. The measured mean activity of these radionuclides in all water samples was found to be below minimum detectable activity. The measured mean activity of 226Ra, 232Th and 40K in vegetation samples was 19.92±3.09, 25.36±8.11 and 4982.94±85.68 Bqkg-1, respectively. No anthropogenic 137Cs was detected in these environmental samples. Mean radium equivalent activity (Raeq), external radiation hazard index (Hex), internal radiation hazard index (Hin) and absorbed dose rate (D) for the area under study were determined as 142.92 Bqkg-1, 0.38, 0.47 and 66.47 nGyh-1, respectively. The annual effective dose equivalent (AEDE) varied in the range from 0.03 to 0.12 mSv y-1. It is concluded that the surveyed area do not pose any significant radiological risk to the population and environment.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"40 1","pages":"54"},"PeriodicalIF":0.0,"publicationDate":"2017-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88485004","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}
Pub Date : 2017-03-15DOI: 10.11648/J.NS.20170202.13
O. Ebyan, Mahmoud R. Khattab, M. Abdel‐Rahman
In this study, forty samples of different types of raw sands, magnetite, green silicate and processed mixture of ilmenite, magnetite and green silicates have been mineralogical and radiometrically investigated after preparation. Determination of the mineral contents, radioactivity levels and their corresponding environmental impacts was also carried out. The radioactivity: 238U, 232Th, 226Ra and 40K, of these samples are of naturally occurring origin. The EDX analysis was applied for identification of trace elements in the samples. The microscopic investigations of the samples indicate that the black sand samples are economically rich in heavy minerals such as ilmenite, magnetite, zircon, rutile and monazite; in addition to leucoxene. While the processed and unprocessed green silicate contain ilmenite, zircon, sphene, monazite and calamine with quartz and other silicate minerals. The highest values of activity concentrations of 238U, 232Th, 226Ra and 40K were observed in black sand, processed and unprocessed green silicates samples. These high radioactivities are attributed to the presence of zircon, monazite and sphene. The radiological hazard parameters; the absorbed dose rate (D), annual effective dose equivalent AEDE, radium equivalent activity Raeq, external hazard index Hex, internal hazard index Hin and gamma activity concentration index Iγ of the studied samples were estimated. The results obtained were tabulated, evaluated, interpreted and discussed.
{"title":"Mineralogical and Radiological Micro-Analysis of Raw Sands and Their Processed By-Products for Land Reclamation Applications","authors":"O. Ebyan, Mahmoud R. Khattab, M. Abdel‐Rahman","doi":"10.11648/J.NS.20170202.13","DOIUrl":"https://doi.org/10.11648/J.NS.20170202.13","url":null,"abstract":"In this study, forty samples of different types of raw sands, magnetite, green silicate and processed mixture of ilmenite, magnetite and green silicates have been mineralogical and radiometrically investigated after preparation. Determination of the mineral contents, radioactivity levels and their corresponding environmental impacts was also carried out. The radioactivity: 238U, 232Th, 226Ra and 40K, of these samples are of naturally occurring origin. The EDX analysis was applied for identification of trace elements in the samples. The microscopic investigations of the samples indicate that the black sand samples are economically rich in heavy minerals such as ilmenite, magnetite, zircon, rutile and monazite; in addition to leucoxene. While the processed and unprocessed green silicate contain ilmenite, zircon, sphene, monazite and calamine with quartz and other silicate minerals. The highest values of activity concentrations of 238U, 232Th, 226Ra and 40K were observed in black sand, processed and unprocessed green silicates samples. These high radioactivities are attributed to the presence of zircon, monazite and sphene. The radiological hazard parameters; the absorbed dose rate (D), annual effective dose equivalent AEDE, radium equivalent activity Raeq, external hazard index Hex, internal hazard index Hin and gamma activity concentration index Iγ of the studied samples were estimated. The results obtained were tabulated, evaluated, interpreted and discussed.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"80 1","pages":"44"},"PeriodicalIF":0.0,"publicationDate":"2017-03-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80952190","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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