Pub Date : 2023-11-16DOI: 10.21608/ajnsa.2023.207848.1744
Moustafa Aziz
MCNPX computer code based on Monte Carlo method is used to design a computer model for an assembly of high temperature testing reactor (HTTR). Two models are used in the analysis, namely homogeneous and heterogeneous models. The reactor uses TRISO fuel, Graphite moderator and helium coolant. The multiplication factor of the assembly is determined as a function of fuel burnup and operation time. Axial power mapping distributions are evaluated. Time evolution of actinides (U 235 and Pu 239 ) is calculated as a result of fuel burnup. Fuel and moderator temperature coefficient of reactivity are determined as a function of operating temperature. The effect of Helium coolant losses on reactor criticality is evaluated (by assuming reduction of helium density to one percent of its nominal density). Calculations indicated that homogenous model results are in good agreement with heterogeneous models with an average difference of approximately 5 %. This enable homogeneous model to be used in full reactor core simulations. This is much easier and saves modeling and computational time.
{"title":"Core Physics Analysis of An Assembly of HTTR Reactor using Homogeneous and heterogeneous model.","authors":"Moustafa Aziz","doi":"10.21608/ajnsa.2023.207848.1744","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.207848.1744","url":null,"abstract":"MCNPX computer code based on Monte Carlo method is used to design a computer model for an assembly of high temperature testing reactor (HTTR). Two models are used in the analysis, namely homogeneous and heterogeneous models. The reactor uses TRISO fuel, Graphite moderator and helium coolant. The multiplication factor of the assembly is determined as a function of fuel burnup and operation time. Axial power mapping distributions are evaluated. Time evolution of actinides (U 235 and Pu 239 ) is calculated as a result of fuel burnup. Fuel and moderator temperature coefficient of reactivity are determined as a function of operating temperature. The effect of Helium coolant losses on reactor criticality is evaluated (by assuming reduction of helium density to one percent of its nominal density). Calculations indicated that homogenous model results are in good agreement with heterogeneous models with an average difference of approximately 5 %. This enable homogeneous model to be used in full reactor core simulations. This is much easier and saves modeling and computational time.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":"45 3","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139268679","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.2023.223615.1765
Mohamed Abd-El Aziz, Mona Attia
and oxidation
和氧化
{"title":"Effect of gamma radiation and modified CeO2 on the physicomechanical properties of silicon rubber nanocomposites","authors":"Mohamed Abd-El Aziz, Mona Attia","doi":"10.21608/ajnsa.2023.223615.1765","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.223615.1765","url":null,"abstract":"and oxidation","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":"55 6","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139269515","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.2023.236014.1774
Ahmed Adly, omar fadle, Mohamed Rezk
Combination between the distributed generator (DG) such as conventional distribution grid, tidal turbines, and nuclear power plant is increasing rapidly around the countries, because of its reliable and nature-friendly behaviors. Also, DGs are a major feature in a smart grid. However, this integration causes bidirectional current flows and contributes to the level of fault current especially during the power swing. Therefore, it changes the fault current pattern in the distribution network and adversely affects the coordination of the protection relays. Many papers have proposed different techniques to detect and classify the faults in distribution network and only isolate the faulty section such as (protection coordination using dual setting directional relays, Fuzzy logic based method, wavelet transform based method, Adaptive protection based techniques...etc). In the light of this situation, a comprehensive protection algorithm is proposed in this paper to detect any fault in distribution network with DGs during the power swing and guarantees a secure and reliable performance to avoid any unintentional disconnection during any fault case. The proposed protection direction scheme totally depends on the auto regression technique for the positive sequence component of currents angles difference (fault–prefault). It is better to depend on current signals only in designing smart protection systems. In this article, a proposed protection scheme depending on current signal of two terminals. The effectiveness of the proposed scheme is demonstrated compared to other methods in the literature
{"title":"Optimal Protection Scheme for Distribution Systems Integrated with Distributed Generator","authors":"Ahmed Adly, omar fadle, Mohamed Rezk","doi":"10.21608/ajnsa.2023.236014.1774","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.236014.1774","url":null,"abstract":"Combination between the distributed generator (DG) such as conventional distribution grid, tidal turbines, and nuclear power plant is increasing rapidly around the countries, because of its reliable and nature-friendly behaviors. Also, DGs are a major feature in a smart grid. However, this integration causes bidirectional current flows and contributes to the level of fault current especially during the power swing. Therefore, it changes the fault current pattern in the distribution network and adversely affects the coordination of the protection relays. Many papers have proposed different techniques to detect and classify the faults in distribution network and only isolate the faulty section such as (protection coordination using dual setting directional relays, Fuzzy logic based method, wavelet transform based method, Adaptive protection based techniques...etc). In the light of this situation, a comprehensive protection algorithm is proposed in this paper to detect any fault in distribution network with DGs during the power swing and guarantees a secure and reliable performance to avoid any unintentional disconnection during any fault case. The proposed protection direction scheme totally depends on the auto regression technique for the positive sequence component of currents angles difference (fault–prefault). It is better to depend on current signals only in designing smart protection systems. In this article, a proposed protection scheme depending on current signal of two terminals. The effectiveness of the proposed scheme is demonstrated compared to other methods in the literature","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":"24 4","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139270109","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 : 2023-10-01DOI: 10.21608/ajnsa.2023.191570.1716
fatma maged
Zinc oxide ZnO was synthesized via a sol-gel process, incorporated with polyvinyl alcohol (PVA) using the casting method. Different doses of gamma radiation (20,30,40 and 50) irradiated the ZnO /PVA composite. The structured shape of ZnO was examined by (HRTEM). The optical direct transition band gap was reduced from (3.25 to 2.7 eV) for (20 kGy to 40 kGy) due to limited states' influence in the forbidden band. The refractive index was examined using Wemple and Di-Domenico method. The dispersion energy E d and the oscillator energy E o are related to variations in the structural order of the ZnO/PVA by irradiation dose. The dielectric loss tangent ( tanδ ), dielectric constant ( ε' ), and AC electrical conductivities of ZnO PVA samples have been recorded. Finally, it was noticed that the A.C. electrical conductivity appears to change exponentially with frequency, and this behavior is due to significant charge carrier migration via the hopping mechanism. The nanocomposite has a specific capacitance value of 36.7 F/g and 91.75 F/g, which makes it a good candidate for optoelectronic applications.
{"title":"Effect of gamma dose on dielectric and optical properties of ZnO/PVA.","authors":"fatma maged","doi":"10.21608/ajnsa.2023.191570.1716","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.191570.1716","url":null,"abstract":"Zinc oxide ZnO was synthesized via a sol-gel process, incorporated with polyvinyl alcohol (PVA) using the casting method. Different doses of gamma radiation (20,30,40 and 50) irradiated the ZnO /PVA composite. The structured shape of ZnO was examined by (HRTEM). The optical direct transition band gap was reduced from (3.25 to 2.7 eV) for (20 kGy to 40 kGy) due to limited states' influence in the forbidden band. The refractive index was examined using Wemple and Di-Domenico method. The dispersion energy E d and the oscillator energy E o are related to variations in the structural order of the ZnO/PVA by irradiation dose. The dielectric loss tangent ( tanδ ), dielectric constant ( ε' ), and AC electrical conductivities of ZnO PVA samples have been recorded. Finally, it was noticed that the A.C. electrical conductivity appears to change exponentially with frequency, and this behavior is due to significant charge carrier migration via the hopping mechanism. The nanocomposite has a specific capacitance value of 36.7 F/g and 91.75 F/g, which makes it a good candidate for optoelectronic applications.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":"10 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135324413","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 : 2023-10-01DOI: 10.21608/ajnsa.2023.186426.1709
Noha Hamed, Huda Hammad
Exposure to gamma radiation causes oxidative stress and generation of reactive oxygen species, which cause hepatocellular apoptosis, so it is necessary to keep safe the living organisms especially humans and animals. Red beetroot ( Beta vulgaris L.) is thought to be crucial for enhancing hepatic health. Male Wistar albino rats were designated to evaluate the possible protective role of red beetroot peel extract (RBPE) to alleviate oxidative stress that associated with gamma-ray exposure. Biochemical, histopathology, and immunehistochemical analyses of rat livers exposed to acute radiation dose revealed different apoptotic patterns. According to the findings, RBPE has a DPPH (2,2-diphenyl-1-picryl-hydrazyl-hydrate) scavenging activity of 1.22±0.23 mg TE/g. The total phenolic and flavonoid contents of RBPE were 126.21±0.39 mg GE/g and 67.18±0.78 mg QE/g, respectively. Results showed that pre-administration of RBPE (50 mg/kg body weight for two weeks before and after exposure to 6 Gy gamma irradiation reduce elevations in liver enzymes and apoptotic markers [caspase-3, and B-cell lymphoma-2-associated protein X (Bax) and elevate the expression of the B-cell lymphoma-2 (Bcl-2). These findings were supported by the histological analyses, which demonstrated that RBPE shielded the rats' livers against gamma-irradiation-induced damage. The protective effects are most likely due to the potent antioxidant phenols in RBPE that working together synergistically. It is concluded that RBPE is a promising radioprotector for liver against oxidative stress induced by exposure to gamma ionizing radiation due to its antioxidant and anti-apoptotic power.
{"title":"The Protective Role of Red Beetroot (Beta Vulgaris L.) Peel Extract against Gamma Irradiation Induced Hepatic Apoptosis in Rats","authors":"Noha Hamed, Huda Hammad","doi":"10.21608/ajnsa.2023.186426.1709","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.186426.1709","url":null,"abstract":"Exposure to gamma radiation causes oxidative stress and generation of reactive oxygen species, which cause hepatocellular apoptosis, so it is necessary to keep safe the living organisms especially humans and animals. Red beetroot ( Beta vulgaris L.) is thought to be crucial for enhancing hepatic health. Male Wistar albino rats were designated to evaluate the possible protective role of red beetroot peel extract (RBPE) to alleviate oxidative stress that associated with gamma-ray exposure. Biochemical, histopathology, and immunehistochemical analyses of rat livers exposed to acute radiation dose revealed different apoptotic patterns. According to the findings, RBPE has a DPPH (2,2-diphenyl-1-picryl-hydrazyl-hydrate) scavenging activity of 1.22±0.23 mg TE/g. The total phenolic and flavonoid contents of RBPE were 126.21±0.39 mg GE/g and 67.18±0.78 mg QE/g, respectively. Results showed that pre-administration of RBPE (50 mg/kg body weight for two weeks before and after exposure to 6 Gy gamma irradiation reduce elevations in liver enzymes and apoptotic markers [caspase-3, and B-cell lymphoma-2-associated protein X (Bax) and elevate the expression of the B-cell lymphoma-2 (Bcl-2). These findings were supported by the histological analyses, which demonstrated that RBPE shielded the rats' livers against gamma-irradiation-induced damage. The protective effects are most likely due to the potent antioxidant phenols in RBPE that working together synergistically. It is concluded that RBPE is a promising radioprotector for liver against oxidative stress induced by exposure to gamma ionizing radiation due to its antioxidant and anti-apoptotic power.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":"109 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135324632","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 : 2023-10-01DOI: 10.21608/ajnsa.2023.204483.1741
Israa Ahmed, Mostafa Mostafa
Cesium (Cs-137) is a technically enhanced natural radioactive element TENORM. Cs-137 is presented out of nuclear accidents as an example of anthropogenic radionuclides. In this paper, the activity concentration of Cs-137 is estimated in fly ash samples with a NaI (Tl) detector (gamma spectroscopy). It has high efficiency for gamma measurements. Fly ash samples were collected from the electric thermal power station Al-Hartha at Basra city in the south of Iraq. About fourteen samples were collected, prepared, and measured. The Cs-137 activity concentration is found between 0 (BDL, blew detection limit) to 28±7 Bq kg -1 for the fly ash samples from electric thermal power station Al-Hartha. All measured values are lower than the worldwide background level (UNSCEAR recommendation 37 Bq kg -1 ). Also, the obtained Cs-137 activity concentration has no effect on the estimated effective dose rate, that be prophesied with the activity of Cs-137 and cosmic radiation. The Cs-137 contribution in the estimation of absorbed dose rate will discuss and calculation will present for the measured activity.
{"title":"Cs-137 Activity in fly ash from Al-Hartha Thermal Power station in the south of AL Basra City","authors":"Israa Ahmed, Mostafa Mostafa","doi":"10.21608/ajnsa.2023.204483.1741","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.204483.1741","url":null,"abstract":"Cesium (Cs-137) is a technically enhanced natural radioactive element TENORM. Cs-137 is presented out of nuclear accidents as an example of anthropogenic radionuclides. In this paper, the activity concentration of Cs-137 is estimated in fly ash samples with a NaI (Tl) detector (gamma spectroscopy). It has high efficiency for gamma measurements. Fly ash samples were collected from the electric thermal power station Al-Hartha at Basra city in the south of Iraq. About fourteen samples were collected, prepared, and measured. The Cs-137 activity concentration is found between 0 (BDL, blew detection limit) to 28±7 Bq kg -1 for the fly ash samples from electric thermal power station Al-Hartha. All measured values are lower than the worldwide background level (UNSCEAR recommendation 37 Bq kg -1 ). Also, the obtained Cs-137 activity concentration has no effect on the estimated effective dose rate, that be prophesied with the activity of Cs-137 and cosmic radiation. The Cs-137 contribution in the estimation of absorbed dose rate will discuss and calculation will present for the measured activity.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":"54 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135324650","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 : 2023-10-01DOI: 10.21608/ajnsa.2023.190166.1714
mahmouud Hassan, Rehab Attia, Nisreen Ali
.
{"title":"Water and Oil Repellent Cotton Fabrics via Coating with Electron Beam Curable Formulation.","authors":"mahmouud Hassan, Rehab Attia, Nisreen Ali","doi":"10.21608/ajnsa.2023.190166.1714","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.190166.1714","url":null,"abstract":".","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":"22 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135324641","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 : 2023-10-01DOI: 10.21608/ajnsa.2023.189116.1711
Moustafa Aziz, amal elsaway
Article history: Received: 23rd Jan. 2023 Accepted: 6th Mar. 2023 Available online: 24th May 2023 MCNPX computer code is used to model the general PWR cask which contain 32 typical PWR spent fuel assemblies. For Safe storage and transportation of the cask, factors that affect the criticality were studied using the concept of burn up credit. Several parameters such as initial fuel enrichment , fuel burnup history, cooling time, and axial burnup profile were analysed. The analysis was performed in two different steps , first burn the fuel assembly at different burnup and storage (cooling ) conditions , secondly, incorporate the details of the assemblies into the cask (canister ) model and perform a criticality calculations for the cask. Several cases of unnormal storage conditions are considered in the case of UO2PWR only. In this research high discharged fuel assemblies burn up include Standard UO2 PWR and next generation MOX fuel. The present results are compared with similar GBC-32 benchmark and satisfactory agreements were found.
{"title":"Criticality Safety Analysis for Cask Design with High Discharged Fuel Burnup Using MCNPX Code","authors":"Moustafa Aziz, amal elsaway","doi":"10.21608/ajnsa.2023.189116.1711","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.189116.1711","url":null,"abstract":"Article history: Received: 23rd Jan. 2023 Accepted: 6th Mar. 2023 Available online: 24th May 2023 MCNPX computer code is used to model the general PWR cask which contain 32 typical PWR spent fuel assemblies. For Safe storage and transportation of the cask, factors that affect the criticality were studied using the concept of burn up credit. Several parameters such as initial fuel enrichment , fuel burnup history, cooling time, and axial burnup profile were analysed. The analysis was performed in two different steps , first burn the fuel assembly at different burnup and storage (cooling ) conditions , secondly, incorporate the details of the assemblies into the cask (canister ) model and perform a criticality calculations for the cask. Several cases of unnormal storage conditions are considered in the case of UO2PWR only. In this research high discharged fuel assemblies burn up include Standard UO2 PWR and next generation MOX fuel. The present results are compared with similar GBC-32 benchmark and satisfactory agreements were found.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":"256 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135324661","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 : 2023-10-01DOI: 10.21608/ajnsa.2023.200272.1733
Ahmed Elbatrek
Impregnation of tri butyl phosphate (TBP) solvent into polymeric resin, commercially known as Siplite LX-16, using the two commonly used dry and wet methods were applied. The suitable conditions for wet impregnation were 70% solvent concentration in kerosene with solvent/resin (S/R) ratio of 6.0 and left 24 hours for impregnation at room temperature before separation and washing with hot water then drying overnight at a temperature of 50 o C, where at these conditions the resin impregnated with 1.99 g TBP/g resin. In case of dry impregnation requires solvent concentration was 55% in acetone at S/R ratio of 5.0 and shaking for 4.0 h then left in the air till complete volatilization of acetone and finally drying overnight at a temperature of 50 o C, where at these conditions one resin impregnated with 2.057 g TBP. Results of testing performance of the prepared TBP impregnated Siplite LX-16 resin against thorium extraction from nitrate medium reveal that extraction efficiency of 70.7% was achieved after 30 min. which can be enough to attain equilibrium. Thorium extraction from the nitrate medium requires high free acidity rather than nitrate from salts (salting out agent addition), however, for economical consideration and reagent saving, it can practically conduct the extraction at free normality of 3.0 N at which 62% extraction efficiency could be achieved at the condition of initial thorium concentration of 2.0 g/l, aqueous/resin “A/R” ratio of 25 and the phases contacted for 30 min. The calculated theoretical saturation capacity for the prepared TBP impregnated Siplite LX-16 resin was 292.7 mg Th / g impregnated resin which is considered high capacity, so it was recommended to use solutions containing high levels of thorium concentrations reached to several grams per liter to decrease the treated volumes at shorter time as well as verify almost complete saturation.
{"title":"TBP-Impregnated Siplite LX-16 Polymeric Resin for Thorium Extraction from Nitrate Medium, Part A: Preparation and Extraction Performance","authors":"Ahmed Elbatrek","doi":"10.21608/ajnsa.2023.200272.1733","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.200272.1733","url":null,"abstract":"Impregnation of tri butyl phosphate (TBP) solvent into polymeric resin, commercially known as Siplite LX-16, using the two commonly used dry and wet methods were applied. The suitable conditions for wet impregnation were 70% solvent concentration in kerosene with solvent/resin (S/R) ratio of 6.0 and left 24 hours for impregnation at room temperature before separation and washing with hot water then drying overnight at a temperature of 50 o C, where at these conditions the resin impregnated with 1.99 g TBP/g resin. In case of dry impregnation requires solvent concentration was 55% in acetone at S/R ratio of 5.0 and shaking for 4.0 h then left in the air till complete volatilization of acetone and finally drying overnight at a temperature of 50 o C, where at these conditions one resin impregnated with 2.057 g TBP. Results of testing performance of the prepared TBP impregnated Siplite LX-16 resin against thorium extraction from nitrate medium reveal that extraction efficiency of 70.7% was achieved after 30 min. which can be enough to attain equilibrium. Thorium extraction from the nitrate medium requires high free acidity rather than nitrate from salts (salting out agent addition), however, for economical consideration and reagent saving, it can practically conduct the extraction at free normality of 3.0 N at which 62% extraction efficiency could be achieved at the condition of initial thorium concentration of 2.0 g/l, aqueous/resin “A/R” ratio of 25 and the phases contacted for 30 min. The calculated theoretical saturation capacity for the prepared TBP impregnated Siplite LX-16 resin was 292.7 mg Th / g impregnated resin which is considered high capacity, so it was recommended to use solutions containing high levels of thorium concentrations reached to several grams per liter to decrease the treated volumes at shorter time as well as verify almost complete saturation.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":"52 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135324789","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 : 2023-10-01DOI: 10.21608/ajnsa.2023.185590.1708
Ahmed Abdelsadek, MAHMOUD HASAN, Muhammad mansy, Mohamed Breky
The sealed sources containing a mixture of 370±5% kBq ( 10±5% µCi) 137 Cs, 740±5% kBq ( 20±5% µCi) 60 Co , and 740±5% kBq ( 20±5% µCi) 152 Eu based on inorganic exchangers, preparations were made, standards were met, and quality checks were passed satisfactorily. ZrSiW matrix retaining 137 Cs, 60 Co, and 152 Eu, the core of the sealed source for the appropriate radioisotope was cleaned and dried before use. A circular disc-shaped acrylic canister was filled with a calibrated quantity of the matrix. Before being sealed, the source underwent quality control inspections, followed by radiometric standardization and encapsulation, before being placed on the local market to calibrate radiation detection and measurement equipment.
{"title":"Preparation and evaluation of mixed gamma sealed source for calibration purpose","authors":"Ahmed Abdelsadek, MAHMOUD HASAN, Muhammad mansy, Mohamed Breky","doi":"10.21608/ajnsa.2023.185590.1708","DOIUrl":"https://doi.org/10.21608/ajnsa.2023.185590.1708","url":null,"abstract":"The sealed sources containing a mixture of 370±5% kBq ( 10±5% µCi) 137 Cs, 740±5% kBq ( 20±5% µCi) 60 Co , and 740±5% kBq ( 20±5% µCi) 152 Eu based on inorganic exchangers, preparations were made, standards were met, and quality checks were passed satisfactorily. ZrSiW matrix retaining 137 Cs, 60 Co, and 152 Eu, the core of the sealed source for the appropriate radioisotope was cleaned and dried before use. A circular disc-shaped acrylic canister was filled with a calibrated quantity of the matrix. Before being sealed, the source underwent quality control inspections, followed by radiometric standardization and encapsulation, before being placed on the local market to calibrate radiation detection and measurement equipment.","PeriodicalId":8110,"journal":{"name":"Arab Journal of Nuclear Sciences and Applications","volume":"65 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135324800","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}
京公网安备 11010802042870号
京ICP备2023020795号-1
扫码关注我们
求助内容：
应助结果提醒方式：