I. Saptiama, F. Rindiyantono, A. Aries, Y. V. Kaneti, M. Iqbal
Molybdenum-99 (99Mo) is the parent radioisotope of technetium-99m (99mTc),an essential medical radioisotope for diagnostic agents in nuclear medicine.In 99Mo/99mTc generator, a chromatography column system with 99Mo adsorbent as afiller is usually used to produce 99mTc in hospitals. However, it is still challenging to find high-performance adsorbentsfor Mo adsorption.We have synthesized both ordered and disordered mesoporous alumina and compared their performance as 99Mo adsorbents. These materials were prepared via a soft-templated method using a triblock copolymer as the template, followed by air calcination at 400°C.The amount of nitric acid (HNO3) and the drying time were adjusted systematically to synthesize the ordered mesoporous alumina. The obtained ordered and disordered mesoporous alumina were characterized by low-and wide-angle X-ray diffractions (XRD), nitrogen adsorption-desorption, thermogravimetric analysis (TGA), scanning electron microscopy (SEM), and transmission electron microscopy (TEM). The 99Mo adsorption capacities of these materials were evaluated by using the batch method. The experimental results show that the ordered mesoporous alumina hasa higher 99Mo adsorption capacity of 72.06 mg(Mo)g-1 than the disordered mesoporous alumina (50.12 mg(Mo)g-1). The results indicate the excellent potential of ordered mesoporous alumina as an adsorbent for the 99Mo/99mTc generator column.
{"title":"Synthesis and Characterization of Ordered and Disordered Mesoporous Alumina as High-Performance Molybdenum-99 Adsorbents","authors":"I. Saptiama, F. Rindiyantono, A. Aries, Y. V. Kaneti, M. Iqbal","doi":"10.17146/AIJ.2021.1000","DOIUrl":"https://doi.org/10.17146/AIJ.2021.1000","url":null,"abstract":"Molybdenum-99 (99Mo) is the parent radioisotope of technetium-99m (99mTc),an essential medical radioisotope for diagnostic agents in nuclear medicine.In 99Mo/99mTc generator, a chromatography column system with 99Mo adsorbent as afiller is usually used to produce 99mTc in hospitals. However, it is still challenging to find high-performance adsorbentsfor Mo adsorption.We have synthesized both ordered and disordered mesoporous alumina and compared their performance as 99Mo adsorbents. These materials were prepared via a soft-templated method using a triblock copolymer as the template, followed by air calcination at 400°C.The amount of nitric acid (HNO3) and the drying time were adjusted systematically to synthesize the ordered mesoporous alumina. The obtained ordered and disordered mesoporous alumina were characterized by low-and wide-angle X-ray diffractions (XRD), nitrogen adsorption-desorption, thermogravimetric analysis (TGA), scanning electron microscopy (SEM), and transmission electron microscopy (TEM). The 99Mo adsorption capacities of these materials were evaluated by using the batch method. The experimental results show that the ordered mesoporous alumina hasa higher 99Mo adsorption capacity of 72.06 mg(Mo)g-1 than the disordered mesoporous alumina (50.12 mg(Mo)g-1). The results indicate the excellent potential of ordered mesoporous alumina as an adsorbent for the 99Mo/99mTc generator column.","PeriodicalId":8647,"journal":{"name":"Atom Indonesia","volume":" ","pages":""},"PeriodicalIF":0.4,"publicationDate":"2021-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47253026","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 investigated the background ionizing radiation of Abakaliki rice mills. The requirement to monitor this site is because the prevalent activities in the site suggest that it is a source of ionizing radiation. The activities include fuel stations and excavation sites. Other sources are various chemicals and agrochemicals (like Phosphate, Uranium, Thorium, and Radium) used during the planting of the different rice species. There is, therefore, an urgent need to investigate the radiation level of Abakaliki rice mills in Ebonyi state, Nigeria to ascertain if it has passed the safety standards. The investigation was carried out using the Radalert 100 radiation monitor and a geographical positioning system (Garmin GPSMAP 765). The studied site was split into different points with each representing a mill that houses different grinding plants. This study included all the sections of the mill. The mean background radiation exposure rate ranges from 0.014 mRhr -1 to 0.0204 mRhr -1 . The obtained values are higher than the world standard limit of 0.013 mRhr -1 recommended by ICRP except point 7 which corresponds to the top of the rice husk dumpsite. The calculated absorbed dose rates for the various sections of the mill ranged from 99.18 nGh -1 to 177.48 nGyh -1 . These values of absorbed dose rates were observed to be far higher than the world permissible value of 89 nGyh -1 . The annual effective dose equivalent (AEDE) for the exposure values ranged from 0.122 mSvy -1 to 0.218 mSvy -1 which are far lower than the ICRP permissible limits of 1.00 mSvlyr for the public and therefore implies absence of any immediate radiological risk. The excess lifetime cancer risk for the mill users were all above the 0.29 × 10 -3 world recommended value. This suggests a possibility of the rice mill workers developing radiation-related illnesses over time.
{"title":"Investigation on the Background Radiation of Abakaliki Rice Mill in Ebonyi State, Nigeria","authors":"A. Nwachukwu, F. C. Ikeagwuani, A. Adeboje","doi":"10.17146/AIJ.2021.1040","DOIUrl":"https://doi.org/10.17146/AIJ.2021.1040","url":null,"abstract":"This study investigated the background ionizing radiation of Abakaliki rice mills. The requirement to monitor this site is because the prevalent activities in the site suggest that it is a source of ionizing radiation. The activities include fuel stations and excavation sites. Other sources are various chemicals and agrochemicals (like Phosphate, Uranium, Thorium, and Radium) used during the planting of the different rice species. There is, therefore, an urgent need to investigate the radiation level of Abakaliki rice mills in Ebonyi state, Nigeria to ascertain if it has passed the safety standards. The investigation was carried out using the Radalert 100 radiation monitor and a geographical positioning system (Garmin GPSMAP 765). The studied site was split into different points with each representing a mill that houses different grinding plants. This study included all the sections of the mill. The mean background radiation exposure rate ranges from 0.014 mRhr -1 to 0.0204 mRhr -1 . The obtained values are higher than the world standard limit of 0.013 mRhr -1 recommended by ICRP except point 7 which corresponds to the top of the rice husk dumpsite. The calculated absorbed dose rates for the various sections of the mill ranged from 99.18 nGh -1 to 177.48 nGyh -1 . These values of absorbed dose rates were observed to be far higher than the world permissible value of 89 nGyh -1 . The annual effective dose equivalent (AEDE) for the exposure values ranged from 0.122 mSvy -1 to 0.218 mSvy -1 which are far lower than the ICRP permissible limits of 1.00 mSvlyr for the public and therefore implies absence of any immediate radiological risk. The excess lifetime cancer risk for the mill users were all above the 0.29 × 10 -3 world recommended value. This suggests a possibility of the rice mill workers developing radiation-related illnesses over time.","PeriodicalId":8647,"journal":{"name":"Atom Indonesia","volume":"12 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2021-04-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"41261354","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 was performed at University of Kufa, Iraq, using canned liquid juice samples found in Iraqi markets due to the absence of environmental contamination from radionuclides emitting 222 Rn concentrations using RAD-7 detectors. The annual effective dose (AED) of 222 Rn was estimated for children and adults from the ingestion of canned liquid juice samples. The estimated concentrations of 222 Rn in unit (mBq/L) ranged from 35.4 to 249.1, with an average of 77.880.24 ± 15.42. It also shows that the AED values for children and adults in (nSv/y) ranged from 19.11 to 134.48 with an average of 43.31 ± 8.32 and from 22.67 to 159.55 with an average of 51.39 ± 9.88, respectively. All estimated results of 222 Rn concentrations for juice samples were lower than the natural limits provided by the WHO and the European Union Commission to the public (0.5 and 1 Bq/L, respectively). Therefore, there are no health hazards from drinking juice sold in Iraq markets.
{"title":"Radon Concentrations in Canned Liquid Juice","authors":"A. Abojassim","doi":"10.17146/AIJ.2020.1030","DOIUrl":"https://doi.org/10.17146/AIJ.2020.1030","url":null,"abstract":"This study was performed at University of Kufa, Iraq, using canned liquid juice samples found in Iraqi markets due to the absence of environmental contamination from radionuclides emitting 222 Rn concentrations using RAD-7 detectors. The annual effective dose (AED) of 222 Rn was estimated for children and adults from the ingestion of canned liquid juice samples. The estimated concentrations of 222 Rn in unit (mBq/L) ranged from 35.4 to 249.1, with an average of 77.880.24 ± 15.42. It also shows that the AED values for children and adults in (nSv/y) ranged from 19.11 to 134.48 with an average of 43.31 ± 8.32 and from 22.67 to 159.55 with an average of 51.39 ± 9.88, respectively. All estimated results of 222 Rn concentrations for juice samples were lower than the natural limits provided by the WHO and the European Union Commission to the public (0.5 and 1 Bq/L, respectively). Therefore, there are no health hazards from drinking juice sold in Iraq markets.","PeriodicalId":8647,"journal":{"name":"Atom Indonesia","volume":" ","pages":""},"PeriodicalIF":0.4,"publicationDate":"2021-04-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"48094415","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}
D. Hartanto, A. Alshamsi, A. AlSuwaidi, A. Bilkhair, H. A. Hukal, M. Zubair
Safety and reliability are the most desirable conditions that each nuclear power plant should improve. Since the Fukushima Daiichi accident, Accident-Tolerant Fuel (ATF) has been extensively researched to improve the performance of the nuclear fuel system. This paper presents the investigation of the ATF system from a neutronics perspective, which positively reflects on the performance of the APR-1400 nuclear power plant. Several advanced fuel candidates such as UC, U 3 Si 2 , and UN, which have better thermophysical properties than current UO 2 nuclear fuel, have been considered. Meanwhile, advanced cladding candidates such as FeCrAl, Zr-alloy with coating, and SiC which can reduce or even eliminate the oxidation rate of current Zr-alloy cladding have been adopted in this study. The Monte Carlo Serpent code, in conjunction with ENDF/B-VII.1 nuclear data library, has been used to calculate and evaluate the important neutronics parameters at the assembly level such as the fuel residence time, discharge burnup, kinetics parameters, pin power distribution, temperature reactivity feedbacks, and fissile evolution. The advanced fuels show better neutronics performance than the current UO 2 fuel. In addition, SiC provides optimum neutronic performance as cladding.
{"title":"Neutronics Assessment of Accident-Tolerant Fuel in Advanced Power Reactor 1400 (APR1400)","authors":"D. Hartanto, A. Alshamsi, A. AlSuwaidi, A. Bilkhair, H. A. Hukal, M. Zubair","doi":"10.17146/aij.2020.1073","DOIUrl":"https://doi.org/10.17146/aij.2020.1073","url":null,"abstract":"Safety and reliability are the most desirable conditions that each nuclear power plant should improve. Since the Fukushima Daiichi accident, Accident-Tolerant Fuel (ATF) has been extensively researched to improve the performance of the nuclear fuel system. This paper presents the investigation of the ATF system from a neutronics perspective, which positively reflects on the performance of the APR-1400 nuclear power plant. Several advanced fuel candidates such as UC, U 3 Si 2 , and UN, which have better thermophysical properties than current UO 2 nuclear fuel, have been considered. Meanwhile, advanced cladding candidates such as FeCrAl, Zr-alloy with coating, and SiC which can reduce or even eliminate the oxidation rate of current Zr-alloy cladding have been adopted in this study. The Monte Carlo Serpent code, in conjunction with ENDF/B-VII.1 nuclear data library, has been used to calculate and evaluate the important neutronics parameters at the assembly level such as the fuel residence time, discharge burnup, kinetics parameters, pin power distribution, temperature reactivity feedbacks, and fissile evolution. The advanced fuels show better neutronics performance than the current UO 2 fuel. In addition, SiC provides optimum neutronic performance as cladding.","PeriodicalId":8647,"journal":{"name":"Atom Indonesia","volume":" ","pages":""},"PeriodicalIF":0.4,"publicationDate":"2020-12-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45416399","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. Tayebi, H. Bezzout, M. El Maghraoui, H. Faylali
In this work, an efficient algorithm, using a finite-difference time-domain (FDTD) technique, is proposed for modeling the variation of radon concentration as a function of soil structure parameters and vice versa. The development of the FDTD model is based on the simultaneous resolution of the radon transport equation in a porous, homogeneous medium, namely the soil. This equation describes the concentration of radon per pore volume unit. The numerical results are compared with those of the literature or with the theoretical ones.
{"title":"Finite-Difference Time-Domain Simulations of Radon Transport in Porous Media","authors":"A. Tayebi, H. Bezzout, M. El Maghraoui, H. Faylali","doi":"10.17146/aij.2020.902","DOIUrl":"https://doi.org/10.17146/aij.2020.902","url":null,"abstract":"In this work, an efficient algorithm, using a finite-difference time-domain (FDTD) technique, is proposed for modeling the variation of radon concentration as a function of soil structure parameters and vice versa. The development of the FDTD model is based on the simultaneous resolution of the radon transport equation in a porous, homogeneous medium, namely the soil. This equation describes the concentration of radon per pore volume unit. The numerical results are compared with those of the literature or with the theoretical ones.","PeriodicalId":8647,"journal":{"name":"Atom Indonesia","volume":" ","pages":""},"PeriodicalIF":0.4,"publicationDate":"2020-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45838737","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}
D. Tetriana, S. Purnami, Tur Rahardjo, Wiwin Mailana, S. Nurhayati, Eko Pudjadi, S. T. Widyaningtyas, T. Ishida, D. Ramadhani
The evaluation of the tumor protein p53 (TP53) codon 72 polymorphism (rs1042522) status in a population exposed to high background radiation was performed in this study. Real-time polymerase chain reaction (Q-PCR) was used to genotype the rs1042522 polymorphism in 100 subjects from Takandeang, Salleto, and Ahu villages in Mamuju district, West Sulawesi. An in silico study was then conducted to identify the potential effects of the proline substitution associated with this polymorphism on protein stability. The in silico analysis was performed using three different computational tools, namely I-Mutant Suite, iStable, and Protein Variation Effect Analyzer (PROVEAN). Secondary and three-dimensional (3D) structural models for wild-type (WT) and variant TP53 were generated to predict potential structural changes in the protein. Electrostatic surface charge calculations were also performed to identify changes in the electrostatic charge of codon 72. The Pro72 and Arg72 frequencies among the inhabitants in the Takandeang, Salleto, and Ahu villages, who are Mandarese Austronesian-speaking ethnic group members, were 0.56 and 0.44, respectively. The in silico analysis revealed no negative effects on protein stability due to the proline substitution at codon 72, although molecular modeling showed several differences in the secondary and 3D structures of the TP53 variant compared with the structure of WT TP53. To determine the impact of the proline-coding allele on individual sensitivity to radiation exposure, we compared the micronucleus (MN) frequencies of each genotype. The results showed that the MN frequencies in individuals harboring the proline-coding allele were not significantly higher than those expressing the arginine-coding allele. In conclusion, this study revealed that the proline-coding allele for codon 72 of the TP53 gene represented the predominant genotype among Takandeang, Salleto, and Ahu villages inhabitants. The present study also demonstrated that individuals who carried the proline-coding allele were not more sensitive to radiation compared with those expressing the arginine-coding allele for codon 72 of the TP53 gene.
{"title":"Molecular and in silico Study of TP53 Codon 72 Polymorphism (rs1042522) in a Population Exposed to High Background Radiation in Mamuju-West Sulawesi","authors":"D. Tetriana, S. Purnami, Tur Rahardjo, Wiwin Mailana, S. Nurhayati, Eko Pudjadi, S. T. Widyaningtyas, T. Ishida, D. Ramadhani","doi":"10.17146/aij.2020.984","DOIUrl":"https://doi.org/10.17146/aij.2020.984","url":null,"abstract":"The evaluation of the tumor protein p53 (TP53) codon 72 polymorphism (rs1042522) status in a population exposed to high background radiation was performed in this study. Real-time polymerase chain reaction (Q-PCR) was used to genotype the rs1042522 polymorphism in 100 subjects from Takandeang, Salleto, and Ahu villages in Mamuju district, West Sulawesi. An in silico study was then conducted to identify the potential effects of the proline substitution associated with this polymorphism on protein stability. The in silico analysis was performed using three different computational tools, namely I-Mutant Suite, iStable, and Protein Variation Effect Analyzer (PROVEAN). Secondary and three-dimensional (3D) structural models for wild-type (WT) and variant TP53 were generated to predict potential structural changes in the protein. Electrostatic surface charge calculations were also performed to identify changes in the electrostatic charge of codon 72. The Pro72 and Arg72 frequencies among the inhabitants in the Takandeang, Salleto, and Ahu villages, who are Mandarese Austronesian-speaking ethnic group members, were 0.56 and 0.44, respectively. The in silico analysis revealed no negative effects on protein stability due to the proline substitution at codon 72, although molecular modeling showed several differences in the secondary and 3D structures of the TP53 variant compared with the structure of WT TP53. To determine the impact of the proline-coding allele on individual sensitivity to radiation exposure, we compared the micronucleus (MN) frequencies of each genotype. The results showed that the MN frequencies in individuals harboring the proline-coding allele were not significantly higher than those expressing the arginine-coding allele. In conclusion, this study revealed that the proline-coding allele for codon 72 of the TP53 gene represented the predominant genotype among Takandeang, Salleto, and Ahu villages inhabitants. The present study also demonstrated that individuals who carried the proline-coding allele were not more sensitive to radiation compared with those expressing the arginine-coding allele for codon 72 of the TP53 gene.","PeriodicalId":8647,"journal":{"name":"Atom Indonesia","volume":"1 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2020-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"42667519","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":"Reactivity Initiated Transient Response of TRIGA with the Progress of Core Burnt","authors":"F. Haque, N. Badrun","doi":"10.17146/aij.2020.983","DOIUrl":"https://doi.org/10.17146/aij.2020.983","url":null,"abstract":"","PeriodicalId":8647,"journal":{"name":"Atom Indonesia","volume":" ","pages":""},"PeriodicalIF":0.4,"publicationDate":"2020-12-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45484424","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 study on the calculation of energy levels and reduced electric quadrupole transition probability for fluorine-22 isotope using Oxbash Code has been carried out. The shell model and OXBASH was used to calculate the energy levels and probability of quadratic transition B(E2) of the 22 F isotope in the SD region through PW, CWH active interactions. A comparison was made between the calculation results and the experimental data. The comparison shows considerable consistency with the experimental results. The total angular momentum of the ground level 4 + 1 was confirmed when comparing with the experimental values. A significant consistency was obtained for the calculated energy values MeV (1.734, 2.387, 2.946) with the available experimental values of the same angular momentum (1 + 1 ,12+,4 + 2 ). It can be concluded that the reduced transition probabilities B(E2) can be calculated using the PW, CWH reactions and OXBASH code.
{"title":"Calculation of Energy Levels and Reduced Electric Quadrupole Transition Probability for 22F Isotope Using Oxbash Code","authors":"A. K. Hasan, B. A. Zayed","doi":"10.17146/aij.2020.1022","DOIUrl":"https://doi.org/10.17146/aij.2020.1022","url":null,"abstract":"A study on the calculation of energy levels and reduced electric quadrupole transition probability for fluorine-22 isotope using Oxbash Code has been carried out. The shell model and OXBASH was used to calculate the energy levels and probability of quadratic transition B(E2) of the 22 F isotope in the SD region through PW, CWH active interactions. A comparison was made between the calculation results and the experimental data. The comparison shows considerable consistency with the experimental results. The total angular momentum of the ground level 4 + 1 was confirmed when comparing with the experimental values. A significant consistency was obtained for the calculated energy values MeV (1.734, 2.387, 2.946) with the available experimental values of the same angular momentum (1 + 1 ,12+,4 + 2 ). It can be concluded that the reduced transition probabilities B(E2) can be calculated using the PW, CWH reactions and OXBASH code.","PeriodicalId":8647,"journal":{"name":"Atom Indonesia","volume":" ","pages":""},"PeriodicalIF":0.4,"publicationDate":"2020-12-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"43925412","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 226 Ra, 232 Th and 40 K in soil are the primary component of the background exposure sources of the population. Study of the external exposure due to gamma-ray radiation of natural radionuclides is important because this may contribute significantly to the total annual individual dose. The purpose of this study is to investigate the natural radionuclides in soils collected from Tual and Kei islands and assess the radiological hazard due to natural radionuclides contents in soil. The soil samples were analyzed for natural radionuclides 226 Ra, 232 Th and 40 K using gamma ray spectrometry. Radiological hazard parameters were estimated from the activity concentration of these radionuclides in order to assess health implication of exposure of the general public. The activity concentrations of 226 Ra, 232 Th and 40 K in soil samples varied from 7.50 Bq kg -1 to 6326 Bq kg -1 , 0.99 Bq kg -1 to 157 Bq kg -1 , 2.97 kg -1 to 98.91 Bq kg -1 with the average value of 2162 Bq kg -1 ; 69.68 Bq kg -1 and 30.74 Bq kg -1 , respectively. The absorbed dose rates due to the presence of 226 Ra, 232 Th and 40 K, in soil samples in the studied area vary between the range of 4.88 nGy h -1 and 3018.80 nGy h -1 with the average value of 1042 nGy h -1 . The corresponding outdoor annual effective doses ranged between 0.01 mSv y -1 and 3.70 mSv y -1 with the average value of 1.28 mSv y -1 . Radium equivalent activities are calculated to be in the range of 10.42 Bq kg -1 - 6553.03 Bq kg -1 with the average value of 2264 Bq kg -1 . The external and internal hazard indexes vary from 0.03 to 17.71 with the average value of 6.12 and 0.05 to 34.81 with the average value of 11.96, respectively. All calculated average radiological hazard indices were higher than the limits recommended for individual members of the public.
{"title":"Natural Radionuclides Determination and Radiological Hazard Assessments in Soil from Tual and Kei Islands, Indonesia","authors":"S. Syarbaini, K. Kusdiana, M. Wiyono, D. Iskandar","doi":"10.17146/aij.2020.995","DOIUrl":"https://doi.org/10.17146/aij.2020.995","url":null,"abstract":"Natural radionuclides 226 Ra, 232 Th and 40 K in soil are the primary component of the background exposure sources of the population. Study of the external exposure due to gamma-ray radiation of natural radionuclides is important because this may contribute significantly to the total annual individual dose. The purpose of this study is to investigate the natural radionuclides in soils collected from Tual and Kei islands and assess the radiological hazard due to natural radionuclides contents in soil. The soil samples were analyzed for natural radionuclides 226 Ra, 232 Th and 40 K using gamma ray spectrometry. Radiological hazard parameters were estimated from the activity concentration of these radionuclides in order to assess health implication of exposure of the general public. The activity concentrations of 226 Ra, 232 Th and 40 K in soil samples varied from 7.50 Bq kg -1 to 6326 Bq kg -1 , 0.99 Bq kg -1 to 157 Bq kg -1 , 2.97 kg -1 to 98.91 Bq kg -1 with the average value of 2162 Bq kg -1 ; 69.68 Bq kg -1 and 30.74 Bq kg -1 , respectively. The absorbed dose rates due to the presence of 226 Ra, 232 Th and 40 K, in soil samples in the studied area vary between the range of 4.88 nGy h -1 and 3018.80 nGy h -1 with the average value of 1042 nGy h -1 . The corresponding outdoor annual effective doses ranged between 0.01 mSv y -1 and 3.70 mSv y -1 with the average value of 1.28 mSv y -1 . Radium equivalent activities are calculated to be in the range of 10.42 Bq kg -1 - 6553.03 Bq kg -1 with the average value of 2264 Bq kg -1 . The external and internal hazard indexes vary from 0.03 to 17.71 with the average value of 6.12 and 0.05 to 34.81 with the average value of 11.96, respectively. All calculated average radiological hazard indices were higher than the limits recommended for individual members of the public.","PeriodicalId":8647,"journal":{"name":"Atom Indonesia","volume":" ","pages":""},"PeriodicalIF":0.4,"publicationDate":"2020-08-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"42704962","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}
L. E. Lubis, I. Hariyati, D. Ryangga, I. Mu’minah, T. Mart, D. Soejoko
The use of computed tomography (CT) has become a common practice in medical diagnosis in Indonesia. Its number, however, is not matched by the availability of dedicated-performance-check phantoms. This paper aims to describe the design, construction, and evaluation of an in-house phantom for CT performance check that accommodates both radiation dose measurement and image quality performance checks. The phantom is designed as laser-cut polymethyl methacrylate (PMMA) slabs glued together to form a standard cylindrical shape, with spaces to place dose measurement and image quality modules. In this paper, measurement results on both aspects are discussed and compared with standard phantoms and other works. For dose measurement, the constructed phantom exhibited the greatest absolute discrepancy against the reference standard phantom of 8.89 %. Measurement of the CT number linearity and modulation transfer function (MTF) yielded, at most, 7.51 % and 5.07 % discrepancies against Catphan 604, respectively. Meanwhile, although found to be more linear in the phantom-based contrast linearity test, the use of the in-house phantom for clinical image contrast threshold determination requires further study. For noise power spectrum (NPS) measurement, accurate results were obtained within a limited range of spatial frequency .
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