The digital twin is considered the central component of modern industry. It has been adopted in many industrial fields. However, its application in nuclear engineering is very rare, especially for the radioactive waste deposits which is an urgent and tricky issue. Motivated by this demand and considering China's research & development guidelines for geological disposal of high-level radioactive waste (a three-step strategy by 2050 to construct the radioactive waste repository), a framework of the radioactive waste repository digital twin is proposed. The digital twin uses the framework + with a multi-layer structure. It can be adopted in the construction of the radioactive waste repository. It can significantly strengthen the management capability, reduce the operating cost, improve the safety level and deal with accidents more efficiently. The first step for the achievement for the digital twin development of radioactive waste repository based on the framework is also introduced in the paper. The proposed digital twin framework of the radioactive waste repository in this work could be widely used as a reference and easily extended to support management in other industrial fields.
{"title":"A digital twin framework for construction and operation of the radioactive waste repository","authors":"Hong Chao Xu, Yihua Duo, Tao Tang","doi":"10.2298/ntrp2203181x","DOIUrl":"https://doi.org/10.2298/ntrp2203181x","url":null,"abstract":"The digital twin is considered the central component of modern industry. It has been adopted in many industrial fields. However, its application in nuclear engineering is very rare, especially for the radioactive waste deposits which is an urgent and tricky issue. Motivated by this demand and considering China's research & development guidelines for geological disposal of high-level radioactive waste (a three-step strategy by 2050 to construct the radioactive waste repository), a framework of the radioactive waste repository digital twin is proposed. The digital twin uses the framework + with a multi-layer structure. It can be adopted in the construction of the radioactive waste repository. It can significantly strengthen the management capability, reduce the operating cost, improve the safety level and deal with accidents more efficiently. The first step for the achievement for the digital twin development of radioactive waste repository based on the framework is also introduced in the paper. The proposed digital twin framework of the radioactive waste repository in this work could be widely used as a reference and easily extended to support management in other industrial fields.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548897","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
This study investigates the effects of successive neutron and gamma radiation on the parameters of commercial solar cells. Several solar panels have been exposed to neutron radiation and then, after 30 days of recovery, to gamma radiation. A series of measurements of solar cell parameters have been undertaken to determine the reliability of solar cells in the condition of successive irradiation of different types of rays. Solar cell parameters have been measured before and after every step of irradiation. The process of annealing has also been observed. This paper aims to present the effects of both neutron and gamma radiation on the same solar cell sample.
{"title":"Successive neutron and gamma irradiation and their impact on the characteristics of solar cells","authors":"Dejan Nikolic, A. Vasić-Milovanović","doi":"10.2298/ntrp2203215n","DOIUrl":"https://doi.org/10.2298/ntrp2203215n","url":null,"abstract":"This study investigates the effects of successive neutron and gamma radiation on the parameters of commercial solar cells. Several solar panels have been exposed to neutron radiation and then, after 30 days of recovery, to gamma radiation. A series of measurements of solar cell parameters have been undertaken to determine the reliability of solar cells in the condition of successive irradiation of different types of rays. Solar cell parameters have been measured before and after every step of irradiation. The process of annealing has also been observed. This paper aims to present the effects of both neutron and gamma radiation on the same solar cell sample.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68549389","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Hailong Chen, Feifei Wu, Yunfeng Shi, Jing Kang, Bing Lian
After the accident at the Fukushima nuclear power plant in Japan, a large amount of radioactive contaminated soil was generated, which brought great challenges for treating and disposing of the soil. The recycling of slightly polluted soil can reduce the amount of contaminated soil. This paper analyzes the main exposed scenes of 137Cs polluted soil used in the construction of highway subgrade, soil bag handling and paving. The Monte Carlo algorithm (MCNP) and RESRAD-ONSITE program are used to simulate the two scenes respectively, and the concentration of 137Cs is derived in the soil at the effective dose of 1 mSv per year. It is concluded that: the annual effective doses of porter and paver are 0.41 mSv per year and 0.23 mSv per year respectively caused by 1 Bqg-1 137Cs contaminated soil; the activity of 137Cs are 2.44 Bqg-1 and 4.26 Bqg-1 respectively in the soil at 1 mSv per year for porter and paver; the calculated results are consistent with those reported by the Japan Atomic Research Agency. Also, they are lower than the activity concentration corresponding to the effective dose control level of 1 mSv per year under low-probability events in IAEA No. RS-G-1.7 slightly.
日本福岛核电站事故发生后，产生了大量的放射性污染土壤，这给土壤的处理和处置带来了巨大的挑战。对轻度污染土壤进行循环利用，可以减少污染土壤的数量。分析了137Cs污染土壤在公路路基施工、土袋处理和铺装过程中的主要暴露场景。利用蒙特卡罗算法(Monte Carlo algorithm, MCNP)和RESRAD-ONSITE程序分别模拟了这两种场景，得到了有效剂量为1msv /年时土壤中137Cs的浓度。结果表明:1 Bqg-1 137Cs污染土壤对搬运工和铺路工的年有效剂量分别为0.41 mSv /年和0.23 mSv /年;在1 mSv /年条件下，搬运工和摊铺工土壤中137Cs的活性分别为2.44和4.26 Bqg-1;计算结果与日本原子研究机构报告的结果一致。它们也低于国际原子能机构(IAEA)在低概率事件下每年1毫西沃特有效剂量控制水平所对应的活度浓度。rs - g - 1.7。
{"title":"Evaluation of the radiation effect on building highway subgrade using 137Cs slightly polluted soil after nuclear power plant accidents","authors":"Hailong Chen, Feifei Wu, Yunfeng Shi, Jing Kang, Bing Lian","doi":"10.2298/ntrp2204328c","DOIUrl":"https://doi.org/10.2298/ntrp2204328c","url":null,"abstract":"After the accident at the Fukushima nuclear power plant in Japan, a large amount of radioactive contaminated soil was generated, which brought great challenges for treating and disposing of the soil. The recycling of slightly polluted soil can reduce the amount of contaminated soil. This paper analyzes the main exposed scenes of 137Cs polluted soil used in the construction of highway subgrade, soil bag handling and paving. The Monte Carlo algorithm (MCNP) and RESRAD-ONSITE program are used to simulate the two scenes respectively, and the concentration of 137Cs is derived in the soil at the effective dose of 1 mSv per year. It is concluded that: the annual effective doses of porter and paver are 0.41 mSv per year and 0.23 mSv per year respectively caused by 1 Bqg-1 137Cs contaminated soil; the activity of 137Cs are 2.44 Bqg-1 and 4.26 Bqg-1 respectively in the soil at 1 mSv per year for porter and paver; the calculated results are consistent with those reported by the Japan Atomic Research Agency. Also, they are lower than the activity concentration corresponding to the effective dose control level of 1 mSv per year under low-probability events in IAEA No. RS-G-1.7 slightly.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68550471","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Teodora Nedić, A. Janićijević, Alija Jusić, K. Stanković
The paper represents the results of testing the effect of neutron and gamma radiation of radioactive 60Co on electrical filters. Neutron and gamma radiation was chosen because of its conductivity. The analysis of the standard structure of the electric filter found that neutron and gamma radiation can affect the value of the capacitance as the most important component of the filter. The presented results are a contribution to the wider research of the radiation resistance of elements for the coordination of insulation at the low-voltage level. The experiments were performed on commercial capacitors that are installed in electric filters. Measurements were made with professional equipment under well-controlled laboratory conditions. The combined measurement uncertainty of the experimental procedure was less than 5%.
{"title":"Influence of radiation on the stability of electrical filters characteristics as components for overvoltage protection","authors":"Teodora Nedić, A. Janićijević, Alija Jusić, K. Stanković","doi":"10.2298/ntrp2202111n","DOIUrl":"https://doi.org/10.2298/ntrp2202111n","url":null,"abstract":"The paper represents the results of testing the effect of neutron and gamma radiation of radioactive 60Co on electrical filters. Neutron and gamma radiation was chosen because of its conductivity. The analysis of the standard structure of the electric filter found that neutron and gamma radiation can affect the value of the capacitance as the most important component of the filter. The presented results are a contribution to the wider research of the radiation resistance of elements for the coordination of insulation at the low-voltage level. The experiments were performed on commercial capacitors that are installed in electric filters. Measurements were made with professional equipment under well-controlled laboratory conditions. The combined measurement uncertainty of the experimental procedure was less than 5%.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548029","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Kristina Kalkan, S. Forkapić, S. Marković, K. Bikit, R. Tošić, D. Mrdja, Nikola Milentijević
This paper is dealing with soil erosion assessment using two different approaches: nuclear model and erosion potential method, also known as Gavrilovic's method. Complex valley systems on Titel Loess Plateau were selected for investigation. Radiocaesium is favored in many studies as an optimal erosion tracer due to its relatively long half-life, negligible renewal in the environment and strongly binding ability onto soil particles. The use of gamma-spectrometry in environmental testing laboratories acts as a precise and fast measurement technique for determination of 137Cs activity concentrations, without the need for complicate preparation of samples. Annual erosion and deposition rates were estimated according to three conversion models for uncultivated land: the profile distribution model with two years of dominant fallout of 137Cs (1963 and 1986) and the diffusion and migration model using WALLING software. The applied nuclear models were validated by comparison with erosion potential model which is the most relevant empirical model for erosion processes in torrent valleys. The obtained results indicate a good agreement with overall low values of average annual soil erosion rates on all soil profiles in the investigated area. Correlation analysis has determined the different influence of slope, terrain curvature, and vegetation index on the erosion models.
{"title":"Study of hanging valley in loess-paleosoil sediments with soil erosion assessment using nuclear and erosion potential methods","authors":"Kristina Kalkan, S. Forkapić, S. Marković, K. Bikit, R. Tošić, D. Mrdja, Nikola Milentijević","doi":"10.2298/ntrp2201065k","DOIUrl":"https://doi.org/10.2298/ntrp2201065k","url":null,"abstract":"This paper is dealing with soil erosion assessment using two different approaches: nuclear model and erosion potential method, also known as Gavrilovic's method. Complex valley systems on Titel Loess Plateau were selected for investigation. Radiocaesium is favored in many studies as an optimal erosion tracer due to its relatively long half-life, negligible renewal in the environment and strongly binding ability onto soil particles. The use of gamma-spectrometry in environmental testing laboratories acts as a precise and fast measurement technique for determination of 137Cs activity concentrations, without the need for complicate preparation of samples. Annual erosion and deposition rates were estimated according to three conversion models for uncultivated land: the profile distribution model with two years of dominant fallout of 137Cs (1963 and 1986) and the diffusion and migration model using WALLING software. The applied nuclear models were validated by comparison with erosion potential model which is the most relevant empirical model for erosion processes in torrent valleys. The obtained results indicate a good agreement with overall low values of average annual soil erosion rates on all soil profiles in the investigated area. Correlation analysis has determined the different influence of slope, terrain curvature, and vegetation index on the erosion models.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548082","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Hariandra Muthu, Ramesh Kasi, R. Subramaniam, S. Bashir
Commonly consumed vegetables and their surrounding soil samples are gathered from a farm located in Klang, Selangor. Gamma spectrometry has been utilized to analyze the activity concentration of the natural radionuclides, 226Ra, 232Th, and 40K in nine vegetables and soil samples collected. These data are used to evaluate the hazard indices in the soil samples and their radiological exposure to humans. It is found that the external hazard index Hex ranged from 0.05 to 0.44 with a mean value of 0.14. The internal hazard index Hin of the soil samples ranged from 0.05 to 0.56 with a mean value of 0.17. Both Hex and Hin average values are lower than the limit established by the European Commission for Radiation Protection. The absorbed dose rate DN, The annual ingestion dose Aeff, annual effective dose equivalent AEDE, and excess life-time cancer risk, are used to learn the potential risk on the general public consuming these vegetables. For the vegetable sample, it is found that the average value for the DN is 6.70 nGyh?1 and ranged between 1.75 to 16.94 nGyh?1. The average value of Aeff is 10.17 mSv, and it ranges from 2.54 mSv to 22.89 mSv. The range of AEDE is between 2.15 mSv and 20.78 mS, with an average value of 8.21 mSv. Excess life-time cancer risk ELCR is used to determine the likelihood of cancer development due to the radiological exposure of con suming these vegetables. It is found that the average value of ELCR is 2.87?10?5, and the range is from 0.75?10?5 to 7.27?10?5. Both the Aeff and AEDE are found to be lower than the average world value recommended by UNSCEAR.
{"title":"Evaluation of radiation hazards and risk assessment in agricultural soil and commonly consumed vegetables in the district of Klang, Malaysia","authors":"Hariandra Muthu, Ramesh Kasi, R. Subramaniam, S. Bashir","doi":"10.2298/ntrp2202145m","DOIUrl":"https://doi.org/10.2298/ntrp2202145m","url":null,"abstract":"Commonly consumed vegetables and their surrounding soil samples are gathered from a farm located in Klang, Selangor. Gamma spectrometry has been utilized to analyze the activity concentration of the natural radionuclides, 226Ra, 232Th, and 40K in nine vegetables and soil samples collected. These data are used to evaluate the hazard indices in the soil samples and their radiological exposure to humans. It is found that the external hazard index Hex ranged from 0.05 to 0.44 with a mean value of 0.14. The internal hazard index Hin of the soil samples ranged from 0.05 to 0.56 with a mean value of 0.17. Both Hex and Hin average values are lower than the limit established by the European Commission for Radiation Protection. The absorbed dose rate DN, The annual ingestion dose Aeff, annual effective dose equivalent AEDE, and excess life-time cancer risk, are used to learn the potential risk on the general public consuming these vegetables. For the vegetable sample, it is found that the average value for the DN is 6.70 nGyh?1 and ranged between 1.75 to 16.94 nGyh?1. The average value of Aeff is 10.17 mSv, and it ranges from 2.54 mSv to 22.89 mSv. The range of AEDE is between 2.15 mSv and 20.78 mS, with an average value of 8.21 mSv. Excess life-time cancer risk ELCR is used to determine the likelihood of cancer development due to the radiological exposure of con suming these vegetables. It is found that the average value of ELCR is 2.87?10?5, and the range is from 0.75?10?5 to 7.27?10?5. Both the Aeff and AEDE are found to be lower than the average world value recommended by UNSCEAR.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548438","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
The aim of this work was to evaluate whether the excising margin of the clinical tumor volume and planning target volume correspond with calculated radiation margin based on systematic errors, and definition of radiation margins of individual brain lobes. This research was a retrospective cross-sectional study. We checked the systematic errors and calculated their average and the size of radiation margins. The average systematic errors were calculated in four directions: lateral, longitudinal, vertical, and rotation. The largest average systematic error was calculated in the lateral direction in the cerebellar area, and the error was also statistically significant(p < 0.05). In rotational direction we notice the statistically significant difference in frontal lopbe (p = 0.037), and cerebellar area (p = 0.002). The largest safety margin, as measured by the apverage systematic errors, is requirped for irradiation of the cerebellum. The safety margin size of 6.94 mm was calculated according to the formula of Van Herk. However, the smallest safety margin can be used for irradiation of the occipital lobe of the brain, namely 4.85 mm. The linear regression results that only cerebellar lesions affect lateral displacements. Based on our calculation of the mean systematic errors, we estimate that the clinical target volume - planning target volume safety margin can't be reduced further from the current 5 mm to a size of 3 mm without the use of image guided radiotherapy.
{"title":"Optimization of brain tumours irradiation determining the set-up margin","authors":"Valerija Zager-Marcius, L. Dolenc, U. Smrdel","doi":"10.2298/ntrp2203235z","DOIUrl":"https://doi.org/10.2298/ntrp2203235z","url":null,"abstract":"The aim of this work was to evaluate whether the excising margin of the clinical tumor volume and planning target volume correspond with calculated radiation margin based on systematic errors, and definition of radiation margins of individual brain lobes. This research was a retrospective cross-sectional study. We checked the systematic errors and calculated their average and the size of radiation margins. The average systematic errors were calculated in four directions: lateral, longitudinal, vertical, and rotation. The largest average systematic error was calculated in the lateral direction in the cerebellar area, and the error was also statistically significant(p < 0.05). In rotational direction we notice the statistically significant difference in frontal lopbe (p = 0.037), and cerebellar area (p = 0.002). The largest safety margin, as measured by the apverage systematic errors, is requirped for irradiation of the cerebellum. The safety margin size of 6.94 mm was calculated according to the formula of Van Herk. However, the smallest safety margin can be used for irradiation of the occipital lobe of the brain, namely 4.85 mm. The linear regression results that only cerebellar lesions affect lateral displacements. Based on our calculation of the mean systematic errors, we estimate that the clinical target volume - planning target volume safety margin can't be reduced further from the current 5 mm to a size of 3 mm without the use of image guided radiotherapy.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68549610","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
The paper presents the concept and characteristics of nuclear security, the elements of the nu- clear safety strategy, the legislative framework and the most important solutions from the Law on Radiation and Nuclear Safety and Security. At the international level, the most important entity in this field is the International Atomic Energy Agency, while at the national level, most important is the Directorate for Radiation and Nuclear Safety and Security of Serbia. An important role is played by the Vinca Institute of Nuclear Sciences as the most referential scientific institution in this field, as well as the operational bodies - Nuclear Facilities of Serbia, the Ministry of Internal Affairs, Ministry of Defence, and the Serbian Armed Forces. Engagement of these bodies is carried out in regular peacetime circumstances, emergency situations and wartime. The most important challenges, risks and threats to nuclear security of Serbia were pointed out as well as the need to harmonize norms, procedures and processes in purpose of the strengthening institutional mechanisms in the field of nuclear security.
{"title":"Legislative framework of nuclear security in the Republic of Serbia","authors":"Zeljko Nikac, S. Stanković, N. Radović","doi":"10.2298/ntrp2203241n","DOIUrl":"https://doi.org/10.2298/ntrp2203241n","url":null,"abstract":"The paper presents the concept and characteristics of nuclear security, the elements of the nu- clear safety strategy, the legislative framework and the most important solutions from the Law on Radiation and Nuclear Safety and Security. At the international level, the most important entity in this field is the International Atomic Energy Agency, while at the national level, most important is the Directorate for Radiation and Nuclear Safety and Security of Serbia. An important role is played by the Vinca Institute of Nuclear Sciences as the most referential scientific institution in this field, as well as the operational bodies - Nuclear Facilities of Serbia, the Ministry of Internal Affairs, Ministry of Defence, and the Serbian Armed Forces. Engagement of these bodies is carried out in regular peacetime circumstances, emergency situations and wartime. The most important challenges, risks and threats to nuclear security of Serbia were pointed out as well as the need to harmonize norms, procedures and processes in purpose of the strengthening institutional mechanisms in the field of nuclear security.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68549726","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Hariandra Muthu, Ramesh Kasi, R. Subramaniam, Shahid Bashir
The activity concentrations of naturally occurring radionuclides in vegetables and peat soil were investigated to determine the transfer factors of radionuclides from soil to vegetables obtained from farms in Klang Selangor. The results showed that the activity concentration ranges for 226Ra, 232Th, and 40K in the soil of the vegetable were 2.72-46.54 Bqkg-1, 9.01-54.84 Bqkg-1, and 19.22-477.76 Bqkg-1, respectively. The activity concentration ranges for 226Ra, 232Th, and 40K in various vegetable samples were 0.41-3.41 Bqkg-1, 0.02-3.56 Bqkg-1, and 16.22-317.49 Bqkg-1, respectively. The transfer factors from soil-to-plant for 226Ra, 232Th, and 40K were in the ranges of 0.01-0.67, 0.00-0.17, and 0.26-2.52, respectively. Radionuclide 40K has the highest transfer factor value in most vegetables, especially in the fruit type vegetable, and 232Th was found to have the lowest transfer factor value in all vegetables. The acquired results were compared to the levels that are globally recognized as acceptable. The transfer factor value of 40K was greater than 1 found in beans and fruit type vegetables, showing a similar value in other studies involving tropical plants, while transfer factor value for 226Ra was 15 times higher than the value reported in the data for tropical plants.
{"title":"Radioactivity concentration and transfer factors of natural radionuclides 226Ra, 232Th, and 40K from peat soil to vegetables in Selangor, Malaysia","authors":"Hariandra Muthu, Ramesh Kasi, R. Subramaniam, Shahid Bashir","doi":"10.2298/ntrp2201057m","DOIUrl":"https://doi.org/10.2298/ntrp2201057m","url":null,"abstract":"The activity concentrations of naturally occurring radionuclides in vegetables and peat soil were investigated to determine the transfer factors of radionuclides from soil to vegetables obtained from farms in Klang Selangor. The results showed that the activity concentration ranges for 226Ra, 232Th, and 40K in the soil of the vegetable were 2.72-46.54 Bqkg-1, 9.01-54.84 Bqkg-1, and 19.22-477.76 Bqkg-1, respectively. The activity concentration ranges for 226Ra, 232Th, and 40K in various vegetable samples were 0.41-3.41 Bqkg-1, 0.02-3.56 Bqkg-1, and 16.22-317.49 Bqkg-1, respectively. The transfer factors from soil-to-plant for 226Ra, 232Th, and 40K were in the ranges of 0.01-0.67, 0.00-0.17, and 0.26-2.52, respectively. Radionuclide 40K has the highest transfer factor value in most vegetables, especially in the fruit type vegetable, and 232Th was found to have the lowest transfer factor value in all vegetables. The acquired results were compared to the levels that are globally recognized as acceptable. The transfer factor value of 40K was greater than 1 found in beans and fruit type vegetables, showing a similar value in other studies involving tropical plants, while transfer factor value for 226Ra was 15 times higher than the value reported in the data for tropical plants.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548008","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
M. Razab, N. Nawi, R. Sunaiwi, A. Noor, M. Aziz, F. Hadzuan, Fathirah Ibrahim, A. Khaizul, N. Abdullah
Dealing with open sources of radioactive substances in nuclear medicine is a daily task since contamination due to radioactive spills may happen frequently. Proper and safe decontamination management is a vital procedure. However, regular purchase of decontamination agents incurs high costs and might be toxic due to their chemical properties. The purpose of this study is to compare graphene oxide, which is an environmentally friendly carbon-based material and marketable decontamination agent, in decontaminating radioactive spillage. Samples of pure 99mTc and 131I from the laboratory were spilled on a petri dish. The spill was immediately decontaminated with a marketable decontamination agent swab and varying concentrations of graphene oxide swab. The initial radioactivity of each swab containing 99mTc and 131I was measured using a dose calibrator. The absorbance spectra of each sample were analysed using an ultraviolet-visible spectrophotometer. The morphology image of graphene oxide was observed under field emission scanning electron microscope. For decontamination using a marketable decontamination agent, the radioactivity of 131I was slightly higher, whereas that of 99mTc was slightly lower than the high concentration of graphene oxide. The absorbance spectra of 99mTc and 131I that had been decontaminated using graphene oxide were observed at a range of 200 nm to 250 nm due ???* to the transition.
{"title":"Efficiency of marketable decontamination agent and graphene oxide on 99mTc and 131I spillages in nuclear medicine department","authors":"M. Razab, N. Nawi, R. Sunaiwi, A. Noor, M. Aziz, F. Hadzuan, Fathirah Ibrahim, A. Khaizul, N. Abdullah","doi":"10.2298/ntrp2202159r","DOIUrl":"https://doi.org/10.2298/ntrp2202159r","url":null,"abstract":"Dealing with open sources of radioactive substances in nuclear medicine is a daily task since contamination due to radioactive spills may happen frequently. Proper and safe decontamination management is a vital procedure. However, regular purchase of decontamination agents incurs high costs and might be toxic due to their chemical properties. The purpose of this study is to compare graphene oxide, which is an environmentally friendly carbon-based material and marketable decontamination agent, in decontaminating radioactive spillage. Samples of pure 99mTc and 131I from the laboratory were spilled on a petri dish. The spill was immediately decontaminated with a marketable decontamination agent swab and varying concentrations of graphene oxide swab. The initial radioactivity of each swab containing 99mTc and 131I was measured using a dose calibrator. The absorbance spectra of each sample were analysed using an ultraviolet-visible spectrophotometer. The morphology image of graphene oxide was observed under field emission scanning electron microscope. For decontamination using a marketable decontamination agent, the radioactivity of 131I was slightly higher, whereas that of 99mTc was slightly lower than the high concentration of graphene oxide. The absorbance spectra of 99mTc and 131I that had been decontaminated using graphene oxide were observed at a range of 200 nm to 250 nm due ???* to the transition.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548585","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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