{"title":"Physical Security Measures for Radioactive Materials in Albania","authors":"D. Prifti, K. Tushe, E. Bylyku, B. Daci","doi":"10.1501/nuclear.2023.51","DOIUrl":"https://doi.org/10.1501/nuclear.2023.51","url":null,"abstract":"<jats:p xml:lang=\"tr\" />","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2024-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86959366","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 : 2023-11-16DOI: 10.21608/ajnsa.2023.222779.1764
Mohamed Mitwalli, Aya Abdelrazek
The present study is carried out to investigate the influence of grain size on the level of radon radioactivity for calcium silicate (Ca 2 SiO 4 ) ore rocks, which are used widely in many construction materials, particularly cement. The polymeric nuclear detector is used to determine radon activity concentration and assessment of the radiological impact of (Ca 2 SiO 4 ) ore rocks. In addition to explaining the influence and quantification of grain size on radon radioactivity hence acts as a great radiological impact assessment and radiation protection to specify if it poses a risk to human health, moreover environmental safety. The investigated samples were analyzed by alpha trace detector (LR-115 NTD) to measure the radioactivity concentration of radon, which is produced in the continental crust by the natural decay series of uranium-238 and penetrates the pore spaces where it is imparted by diffusion and sent out into the atmosphere. The research results explained the correlation of grain size which influences the radon exhalation rate. The study indicated a normal radiation level (>1000 Bqm -3 ) regarding the international limitation and permissible levels recommended by IAEA, ICRP, and UNSCEAR.
{"title":"Correlation Influence and Quantification of Grain Size on Radon Radioactivity for (Ca2SiO4) Ore Rocks","authors":"Mohamed Mitwalli, Aya Abdelrazek","doi":"10.21608/ajnsa.2023.222779.1764","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.222779.1764","url":null,"abstract":"The present study is carried out to investigate the influence of grain size on the level of radon radioactivity for calcium silicate (Ca 2 SiO 4 ) ore rocks, which are used widely in many construction materials, particularly cement. The polymeric nuclear detector is used to determine radon activity concentration and assessment of the radiological impact of (Ca 2 SiO 4 ) ore rocks. In addition to explaining the influence and quantification of grain size on radon radioactivity hence acts as a great radiological impact assessment and radiation protection to specify if it poses a risk to human health, moreover environmental safety. The investigated samples were analyzed by alpha trace detector (LR-115 NTD) to measure the radioactivity concentration of radon, which is produced in the continental crust by the natural decay series of uranium-238 and penetrates the pore spaces where it is imparted by diffusion and sent out into the atmosphere. The research results explained the correlation of grain size which influences the radon exhalation rate. The study indicated a normal radiation level (>1000 Bqm -3 ) regarding the international limitation and permissible levels recommended by IAEA, ICRP, and UNSCEAR.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139269786","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 : 2023-11-16DOI: 10.21608/ajnsa.2023.210751.1752
E. H. Ali, M. El_Tokhy, Somaya I Kayed
The paper focuses on improving wireless communication networks for nuclear radiation monitoring by analyzing and evaluating the performance of Multi Carrier Code Division Multiple Access (MC-CDMA) as a wireless communication system. The work aims to determine the outage probability as a quality-of-service parameter and investigate the average channel capacity under channel deterioration. They use closed form expressions to present the performances of these characteristics and study the impact of the number of branches and subcarriers on the outage probability. In addition, the authors propose a robust and reliable approach to channel under fading and study the capacity of MC-CDMA with the largest number of users. The results obtained from the study confirm that exponential channel fading achieves the lowest outage probability compared to other channel degradations. Moreover, the proposed results guarantee high average channel capacity and high throughput, which are essential for the successful deployment of MC-CDMA systems. The findings of this study provide valuable information for researchers and engineers working in the field of wireless communication systems, particularly those interested in the design and optimization of MC-CDMA systems. Overall, the paper contributes to the understanding of the performance of MC-CDMA systems under various channel conditions and provides insights into the design and optimization of such systems. The results show that the importance of utilizing robust and reliable wireless communication systems in nuclear radiation monitoring to ensure the accuracy and reliability of the data obtained.
{"title":"Outage Probability and Capacity improvement of A Wireless Communication Systems","authors":"E. H. Ali, M. El_Tokhy, Somaya I Kayed","doi":"10.21608/ajnsa.2023.210751.1752","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.210751.1752","url":null,"abstract":"The paper focuses on improving wireless communication networks for nuclear radiation monitoring by analyzing and evaluating the performance of Multi Carrier Code Division Multiple Access (MC-CDMA) as a wireless communication system. The work aims to determine the outage probability as a quality-of-service parameter and investigate the average channel capacity under channel deterioration. They use closed form expressions to present the performances of these characteristics and study the impact of the number of branches and subcarriers on the outage probability. In addition, the authors propose a robust and reliable approach to channel under fading and study the capacity of MC-CDMA with the largest number of users. The results obtained from the study confirm that exponential channel fading achieves the lowest outage probability compared to other channel degradations. Moreover, the proposed results guarantee high average channel capacity and high throughput, which are essential for the successful deployment of MC-CDMA systems. The findings of this study provide valuable information for researchers and engineers working in the field of wireless communication systems, particularly those interested in the design and optimization of MC-CDMA systems. Overall, the paper contributes to the understanding of the performance of MC-CDMA systems under various channel conditions and provides insights into the design and optimization of such systems. The results show that the importance of utilizing robust and reliable wireless communication systems in nuclear radiation monitoring to ensure the accuracy and reliability of the data obtained.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139267609","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 : 2023-11-16DOI: 10.21608/ajnsa.2023.214050.1755
B. Rejah, Basma Lazem, Ban Hameed, Mostafa Mostafa
Radon is continuously emitted from natural elements, especially because of the decomposition of U-238 and Thorium-232. Radon is ordered as a second cause of lung cancer. In this paper, the absorptions of radon and thoron were stately in schools east of Baghdad, namely Abtal Al-Taf, Batalat Karbala, and In Kaldoon Schools. The concentrations of the gases are measured using the SSNTD method (solid-state nuclear track detector method). Radon gas concentrations were different and ranged from 33.8 to 63.7 Bq/m 3 , and a thoron from 48.8 to 127.1 Bq/m 3 , which are within the permissible limits stipulated in the international organization ICRP. The mean annual dose of radon and thoron gases obtained by those in the schools under study was 3.4±0.9 mSv.y -1 and the maximum value of the annual dose was 4.7 mSv.y -1 in the room of the Batalat Karbala school, while the last value was 2.6 mSv.y -1 in the garden of Ibn Kaldoon School.
{"title":"Radon and Thoron Concentrations in the Air of Three Schools in East Baghdad","authors":"B. Rejah, Basma Lazem, Ban Hameed, Mostafa Mostafa","doi":"10.21608/ajnsa.2023.214050.1755","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.214050.1755","url":null,"abstract":"Radon is continuously emitted from natural elements, especially because of the decomposition of U-238 and Thorium-232. Radon is ordered as a second cause of lung cancer. In this paper, the absorptions of radon and thoron were stately in schools east of Baghdad, namely Abtal Al-Taf, Batalat Karbala, and In Kaldoon Schools. The concentrations of the gases are measured using the SSNTD method (solid-state nuclear track detector method). Radon gas concentrations were different and ranged from 33.8 to 63.7 Bq/m 3 , and a thoron from 48.8 to 127.1 Bq/m 3 , which are within the permissible limits stipulated in the international organization ICRP. The mean annual dose of radon and thoron gases obtained by those in the schools under study was 3.4±0.9 mSv.y -1 and the maximum value of the annual dose was 4.7 mSv.y -1 in the room of the Batalat Karbala school, while the last value was 2.6 mSv.y -1 in the garden of Ibn Kaldoon School.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139267759","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 : 2023-11-16DOI: 10.21608/ajnsa.2023.209276.1747
O. Elhefnawy, A. Elabd
Egyptian natural kaolinite was supported with metal oxides ZnO and CuO to prepare modified kaolinite KCu and KZn for Th(IV) adsorption from an aqueous solution. Different analyses such as SEM, EDX, XRD, and FTIR described the morphology and structural characteristics of the new adsorbents KCu and KZn. The adsorption process was applied in batch experiments as a function of pH, contact time, initial Th(IV) concentration, temperature, regeneration, and reusability. The equilibrium stage was achieved at 120 min. Experimental data were well described by the pseudo-second-order and Langmuir models with maximum adsorption capacities of 62.89 and 56.179 mg/g for KCu and KZn, respectively. Thermodynamic parameters were calculated and proved the spontaneous and endothermic nature of the adsorption process, which showed that the modified kaolinite is sensitive to temperature. Thermodynamics studies confirmed that adsorption is feasible and spontaneous. The regeneration and reusability study showed that KCu and KZn are economically viable.
{"title":"Comparative study of synthesized Kaolinite supported-metal oxides for Th (IV) adsorption","authors":"O. Elhefnawy, A. Elabd","doi":"10.21608/ajnsa.2023.209276.1747","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.209276.1747","url":null,"abstract":"Egyptian natural kaolinite was supported with metal oxides ZnO and CuO to prepare modified kaolinite KCu and KZn for Th(IV) adsorption from an aqueous solution. Different analyses such as SEM, EDX, XRD, and FTIR described the morphology and structural characteristics of the new adsorbents KCu and KZn. The adsorption process was applied in batch experiments as a function of pH, contact time, initial Th(IV) concentration, temperature, regeneration, and reusability. The equilibrium stage was achieved at 120 min. Experimental data were well described by the pseudo-second-order and Langmuir models with maximum adsorption capacities of 62.89 and 56.179 mg/g for KCu and KZn, respectively. Thermodynamic parameters were calculated and proved the spontaneous and endothermic nature of the adsorption process, which showed that the modified kaolinite is sensitive to temperature. Thermodynamics studies confirmed that adsorption is feasible and spontaneous. The regeneration and reusability study showed that KCu and KZn are economically viable.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139268653","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 : 2023-11-16DOI: 10.21608/ajnsa.2023.237569.1777
N. El-Sahlamy, Ahmed S. Khedr
The objective of the present study is to investigate the safety parameters and their safety margins for a typical MTR pool type research reactor during a partial loss of flow or core bypass without scram. The proposed reactor is a plate type fuel element with upward core flow. The code used in the analysis is RELAP5/MOD3.3, the well-known thermal hydraulic system code. In the proposed postulated accident, an exponential decrease of the core flow rate is assumed to occur with a time constant of 25 s to 20, 40, 60, and 80% of the nominal core flow. Study results for thermal hydraulic reactor behavior were validated by comparing RELAP5 results with published results of PARET code under the same accident conditions. Also, the safety parameters and margins were calculated. From comparisons, good agreements are found between RELAP5 code results and PARET code results for the maximum coolant, clad, and fuel temperatures, as well as minimum DNBR values. Deviations are found between the results of the two codes for flow instability parameter. But, both of the two codes concluded that fuel integrity criteria, in terms of thermal hydraulic instability, are not exceeded. In the second part of the study, the effect of decreasing the time constant on the transient results was studied.
{"title":"Research Reactor Safety Analysis under Partial Loss of Flow without SCRAM","authors":"N. El-Sahlamy, Ahmed S. Khedr","doi":"10.21608/ajnsa.2023.237569.1777","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.237569.1777","url":null,"abstract":"The objective of the present study is to investigate the safety parameters and their safety margins for a typical MTR pool type research reactor during a partial loss of flow or core bypass without scram. The proposed reactor is a plate type fuel element with upward core flow. The code used in the analysis is RELAP5/MOD3.3, the well-known thermal hydraulic system code. In the proposed postulated accident, an exponential decrease of the core flow rate is assumed to occur with a time constant of 25 s to 20, 40, 60, and 80% of the nominal core flow. Study results for thermal hydraulic reactor behavior were validated by comparing RELAP5 results with published results of PARET code under the same accident conditions. Also, the safety parameters and margins were calculated. From comparisons, good agreements are found between RELAP5 code results and PARET code results for the maximum coolant, clad, and fuel temperatures, as well as minimum DNBR values. Deviations are found between the results of the two codes for flow instability parameter. But, both of the two codes concluded that fuel integrity criteria, in terms of thermal hydraulic instability, are not exceeded. In the second part of the study, the effect of decreasing the time constant on the transient results was studied.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139267456","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 : 2023-11-16DOI: 10.21608/ajnsa.2023.237153.1776
Moustafa Aziz, N. El-Sahlamy
In PWR reactors, a higher temperature than the normal operation rate causes an increase in the oxidation rate between the fuel and the clad (UO 2 / Zircaloy), and this results in the release of large quantities of hydrogen, which leads to an increase in pressure and temperature inside the reactor core and also on the walls of the pressure vessel, and perhaps partial or total damage to the reactor core. This research examines the development of new types of fuel such as Uranium Nitride (UN), Uranium Silicate (U 3 Si 2 ). Also, two types of clads such as Silicon Carbide and (Fe-Cr-Al) alloy are tested. The neutronic and thermal properties of these new types have been studied, as they are characterized by the low probability of fuel interaction with cladding, as well as the presence of good neutronic and thermal properties in terms of thermal conductivity and heat capacity, which lead to an improvement in the safety margin during operation and also in the event of nuclear accidents.
在压水堆反应堆中，高于正常运行速率的温度会导致燃料和包壳（UO 2 / Zircaloy）之间的氧化速率增加，从而释放出大量氢气，导致反应堆堆芯内部以及压力容器壁上的压力和温度升高，并可能导致反应堆堆芯的部分或全部损坏。这项研究探讨了新型燃料的开发，如氮化铀（UN）和硅酸铀（U 3 Si 2）。此外，还测试了碳化硅和（铁-铬-铝）合金等两种包壳。对这些新型堆芯的中子和热特性进行了研究，因为它们的特点是燃料与堆芯相互作用的概率较低，而且在导热性和热容量方面具有良好的中子和热特性，从而提高了运行期间以及发生核事故时的安全系数。
{"title":"Analysis of Optimum Accident Tolerant Fuel and Cladding Behavior in Advanced Pressurized Water Reactor","authors":"Moustafa Aziz, N. El-Sahlamy","doi":"10.21608/ajnsa.2023.237153.1776","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.237153.1776","url":null,"abstract":"In PWR reactors, a higher temperature than the normal operation rate causes an increase in the oxidation rate between the fuel and the clad (UO 2 / Zircaloy), and this results in the release of large quantities of hydrogen, which leads to an increase in pressure and temperature inside the reactor core and also on the walls of the pressure vessel, and perhaps partial or total damage to the reactor core. This research examines the development of new types of fuel such as Uranium Nitride (UN), Uranium Silicate (U 3 Si 2 ). Also, two types of clads such as Silicon Carbide and (Fe-Cr-Al) alloy are tested. The neutronic and thermal properties of these new types have been studied, as they are characterized by the low probability of fuel interaction with cladding, as well as the presence of good neutronic and thermal properties in terms of thermal conductivity and heat capacity, which lead to an improvement in the safety margin during operation and also in the event of nuclear accidents.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139270167","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 : 2023-11-16DOI: 10.21608/ajnsa.2023.226769.1769
Yasser Ahmed
Huge amounts of produced water that are TE-NORM-contaminated during the processes of extracting crude oil from oil&gas production fields with concentrations higher than the radiological reference levels provided by international organizations may expose the workers at these sites to potential radiation hazards. Therefore, assessing the worker doses at these sites have a great importance. This assessment is essential in determining the radiation hazards brought on by radiation exposure. The purpose of this study is to determine the activity concentration of TE-NORM contaminated produced water in different Egyptian oil&gas extraction sites, as well as using the estimated annual doses and radiation hazard indices to assess the radiation risks indices for the workers. The obtained data shows that the activity concentration of 238 U, 232 Th, and 40 K ranged from 4032 to 14567 Bq Kg -1 , 1185 to 6358 Bq Kg -1 and 184 to 423 Bq Kg -1 respectively. The calculated absorbed dose rate ranged from 2588 – 10587 nGy/h, and the calculated Annual Effective Dose Equivalent differ according to the TE-NORM activity concentrations and have the range of 3.17 to 12.99 mSv/y. it was found that the radiation hazard indices significantly more than the international values. Based on the obtained results, it could be concluded that discharging the contaminated produced water into the environment should be prohibited and using the recommended disposal methods to reduce as much as possible the exposure of radiation worker in oil & gas production fields.
{"title":"Measurement of TE-NORM Concentrations and Resulting Dose Assessment in Produced Water at Some Oil and Gas Sites..","authors":"Yasser Ahmed","doi":"10.21608/ajnsa.2023.226769.1769","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.226769.1769","url":null,"abstract":"Huge amounts of produced water that are TE-NORM-contaminated during the processes of extracting crude oil from oil&gas production fields with concentrations higher than the radiological reference levels provided by international organizations may expose the workers at these sites to potential radiation hazards. Therefore, assessing the worker doses at these sites have a great importance. This assessment is essential in determining the radiation hazards brought on by radiation exposure. The purpose of this study is to determine the activity concentration of TE-NORM contaminated produced water in different Egyptian oil&gas extraction sites, as well as using the estimated annual doses and radiation hazard indices to assess the radiation risks indices for the workers. The obtained data shows that the activity concentration of 238 U, 232 Th, and 40 K ranged from 4032 to 14567 Bq Kg -1 , 1185 to 6358 Bq Kg -1 and 184 to 423 Bq Kg -1 respectively. The calculated absorbed dose rate ranged from 2588 – 10587 nGy/h, and the calculated Annual Effective Dose Equivalent differ according to the TE-NORM activity concentrations and have the range of 3.17 to 12.99 mSv/y. it was found that the radiation hazard indices significantly more than the international values. Based on the obtained results, it could be concluded that discharging the contaminated produced water into the environment should be prohibited and using the recommended disposal methods to reduce as much as possible the exposure of radiation worker in oil & gas production fields.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139267845","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
The activities of radon content in three seawater samples taken from Lagos and Benin Republic (Sultan, Seme kpoji, and Ojo) Beaches are the focus of the current study. The seawater samples were analyzed using the RAD-7 detector to obtain activity concentration. The obtained values for radon activity concentration are 1800.0 ± 1400 Bq/m3, 3500.0 ± 1900 Bq/m3, and 5500.0±2300 Bq/m3, respectively. The findings showed that the radon concentration levels were higher than the safe levels recommended by the World Health Organization (WHO) and the International Commission on Radiological Protection (ICRP). The estimated radiation hazard indices, which include equilibrium equivalent radon concentration, potential alpha energy concentration, annual absorbed dose, annual equivalent dose, excess lifetime cancer risk, and lung cancer cases per million people per year, were outside of acceptable limits. However, monitoring the environment for Radon against respiratory cancer is crucial for public health. The result of this study adds more data to knowledge.
{"title":"Determination of radon exhalation rates from sand of some beaches in Lagos, Nigeria and Benin","authors":"Adeola Olaoye,, Hyam Khalaf, John Elijah Selome, Kolap Ademola, Israa Ahmed, Mostafa Mostafa, Howaida Mansour","doi":"10.21608/ajnsa.2023.219847.1762","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.219847.1762","url":null,"abstract":"The activities of radon content in three seawater samples taken from Lagos and Benin Republic (Sultan, Seme kpoji, and Ojo) Beaches are the focus of the current study. The seawater samples were analyzed using the RAD-7 detector to obtain activity concentration. The obtained values for radon activity concentration are 1800.0 ± 1400 Bq/m3, 3500.0 ± 1900 Bq/m3, and 5500.0±2300 Bq/m3, respectively. The findings showed that the radon concentration levels were higher than the safe levels recommended by the World Health Organization (WHO) and the International Commission on Radiological Protection (ICRP). The estimated radiation hazard indices, which include equilibrium equivalent radon concentration, potential alpha energy concentration, annual absorbed dose, annual equivalent dose, excess lifetime cancer risk, and lung cancer cases per million people per year, were outside of acceptable limits. However, monitoring the environment for Radon against respiratory cancer is crucial for public health. The result of this study adds more data to knowledge.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139270570","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 : 2023-11-16DOI: 10.21608/ajnsa.2023.236665.1775
Ahmed Amar
A comparison between deuteron and alpha particle, has been done from many aspects. Different comparative methods have been used to study alpha and deuteron properties. Diffraction model has been applied to deuteron and alpha particles. The radial region of sensitivity has been tested using the distance of the closest approach where Notch test was applied to study the sensitivity of the optical model parameters. The reaction cross section and reflexion coefficients η L of the deuteron and alpha elastically scattered by light nuclei ( 6,7 Li, 9 Be and 11 B) have been used for the comparison between the two projectiles under consideration. The imaginary potentials for deuteron and alpha elastically scattered by 7 Li has been used also, to study the difference between alpha and the deuteron. It was observed that deuteron has a signature of halo properties.
氘核和阿尔法粒子之间的比较已经从多个方面进行了研究。我们使用了不同的比较方法来研究α粒子和氘核的特性。衍射模型已应用于氘核和 α 粒子。使用最近接近距离测试了灵敏度的径向区域，其中应用了 Notch 测试来研究光学模型参数的灵敏度。氘核和α粒子被轻核（6,7 Li、9 Be 和 11 B）弹性散射的反应截面和反射系数 η L 已被用于比较两种射弹。此外，还使用了氘核和被 7 Li 弹性散射的 α 的虚势，以研究α 和氘核之间的差异。据观察，氘核具有光晕特性。
{"title":"Study the deuteron and alpha-particle properties applying comparative analyses","authors":"Ahmed Amar","doi":"10.21608/ajnsa.2023.236665.1775","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.236665.1775","url":null,"abstract":"A comparison between deuteron and alpha particle, has been done from many aspects. Different comparative methods have been used to study alpha and deuteron properties. Diffraction model has been applied to deuteron and alpha particles. The radial region of sensitivity has been tested using the distance of the closest approach where Notch test was applied to study the sensitivity of the optical model parameters. The reaction cross section and reflexion coefficients η L of the deuteron and alpha elastically scattered by light nuclei ( 6,7 Li, 9 Be and 11 B) have been used for the comparison between the two projectiles under consideration. The imaginary potentials for deuteron and alpha elastically scattered by 7 Li has been used also, to study the difference between alpha and the deuteron. It was observed that deuteron has a signature of halo properties.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139266674","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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