This article presents the first results for elemental composition of 193 fragments ceramic from four sites located in Ventarrón-Collud archaeological complex, Peru. The results from EDXRF and multivariate analysis indicated statistical similarity among four groups of ceramic fragments, selected by remarkable stylistic variation, collected from different archaeological space/time contexts. The correspondence in the elemental composition of the ceramic paste of the artifacts corroborates the hypothesis that similar raw materials were used consistently throughout the entire occupation of this archaeological complex.
{"title":"Study of archaeological ceramics from the north coast of Peru by EDXRF and exploratory multivariate analysis","authors":"C.S.A. Desanti , C.R. Appoloni , R.A. Ikeoka , M.M.A. Suñer , M. Fagundes , F.A. Silva","doi":"10.1016/j.apradiso.2024.111541","DOIUrl":"10.1016/j.apradiso.2024.111541","url":null,"abstract":"<div><div>This article presents the first results for elemental composition of 193 fragments ceramic from four sites located in Ventarrón-Collud archaeological complex, Peru. The results from EDXRF and multivariate analysis indicated statistical similarity among four groups of ceramic fragments, selected by remarkable stylistic variation, collected from different archaeological space/time contexts. The correspondence in the elemental composition of the ceramic paste of the artifacts corroborates the hypothesis that similar raw materials were used consistently throughout the entire occupation of this archaeological complex.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111541"},"PeriodicalIF":1.6,"publicationDate":"2024-10-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142387486","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-04DOI: 10.1016/j.apradiso.2024.111539
Yusuf Kavun , Mustafa Eken
It is crucial to address two pressing global issues, energy shortage and environmental pollution, when producing building insulation materials. Using waste and natural fiber groups can be part of the solution. The insulation material was produced using pumpkin fiber, chicken fiber, cotton waste, vermiculite, and epoxy as binders. The samples were tested for thermal conductivity coefficient, ultrasonic sound transmission rate, density, water absorption rate, compressive and bending strength, and fire resistance at temperatures of 75, 100, 125, and 150C. The samples produced using natural and waste materials yielded a thermal conductivity value of 0.041 W/mK, an ultrasonic sound transmission speed of 0.25 km/s, a compressive strength value of 1.57 MPa, and bending strength values of 0.91 MPa. It has been clearly demonstrated that, with its low volume loss, it can serve as an alternative to the EPS-XPS types available in the market. Furthermore, the linear attenuation coefficients (LAC) were examined to obtain radiation shielding properties of the samples at 1173 and 133 keV energies using a 60Co gamma source. Also, LAC values determined between 0,1167 ± 0,0452 cm−1-0,2315 ± 0,0065 cm−1 for 1173 keV and 0,1042 ± 0,0488 cm−1 - 0,2141 ± 0,0062 cm−1 for 1333 keV. Accordingly, it has been revealed that waste compositions are effective in protecting against radiation.
{"title":"Investigation of thermal, acoustic, mechanical, and radiation shielding performance of waste and natural fibers","authors":"Yusuf Kavun , Mustafa Eken","doi":"10.1016/j.apradiso.2024.111539","DOIUrl":"10.1016/j.apradiso.2024.111539","url":null,"abstract":"<div><div>It is crucial to address two pressing global issues, energy shortage and environmental pollution, when producing building insulation materials. Using waste and natural fiber groups can be part of the solution. The insulation material was produced using pumpkin fiber, chicken fiber, cotton waste, vermiculite, and epoxy as binders. The samples were tested for thermal conductivity coefficient, ultrasonic sound transmission rate, density, water absorption rate, compressive and bending strength, and fire resistance at temperatures of 75, 100, 125, and 150C. The samples produced using natural and waste materials yielded a thermal conductivity value of 0.041 W/mK, an ultrasonic sound transmission speed of 0.25 km/s, a compressive strength value of 1.57 MPa, and bending strength values of 0.91 MPa. It has been clearly demonstrated that, with its low volume loss, it can serve as an alternative to the EPS-XPS types available in the market. Furthermore, the linear attenuation coefficients (LAC) were examined to obtain radiation shielding properties of the samples at 1173 and 133 keV energies using a 60Co gamma source. Also, LAC values determined between 0,1167 ± 0,0452 cm<sup>−1</sup>-0,2315 ± 0,0065 cm<sup>−1</sup> for 1173 keV and 0,1042 ± 0,0488 cm<sup>−1</sup> - 0,2141 ± 0,0062 cm<sup>−1</sup> for 1333 keV. Accordingly, it has been revealed that waste compositions are effective in protecting against radiation.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111539"},"PeriodicalIF":1.6,"publicationDate":"2024-10-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142387485","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-02DOI: 10.1016/j.apradiso.2024.111538
Ehsan Taghizadeh Tousi , Hamid Reza Sadeghi
This research developed a bio-based adhesive (AP) derived from industrial slaughterhouse waste, comprising over 85% protein. The adhesive was characterized by a melting point of 193.14 °C, a neutral pH of 7, and a viscosity comparable to common wood adhesives such as urea-formaldehyde and phenol-formaldehyde. Utilizing this adhesive, a Rhizophora spp. particleboard phantom was produced, featuring wood particles of ≤149 μm, an adhesive concentration of 12%, and a target density of 1 g/cm³, adhering to a standard phantom dimension of 30 cm × 30 cm × 30 cm. The dosimetric properties of this particleboard phantom were subsequently compared with those of water and Perspex phantoms within an X-ray energy range of 60–100 kVp, employing high-sensitivity thermo-luminescent dosimeters (TL–100H). The findings indicated that the percentage depth dose (PDD) values of the AP-Rhizophora spp. particleboard were closely aligned with those of the Perspex and water phantoms, with the greatest discrepancy observed at 60 kVp. Additionally, the half-value layer (HVL) of the particleboard was similar to those of Perspex and water, particularly at diagnostic X-ray energies. These results demonstrate that the AP adhesive is effective for creating Rhizophora spp. particleboard phantoms, exhibiting dosimetric properties comparable to tissue-equivalent materials.
这项研究开发了一种生物基粘合剂（AP），其原料来自工业屠宰场废物，蛋白质含量超过 85%。这种粘合剂的特点是熔点为 193.14 °C，pH 值为 7，粘度与普通木材粘合剂（如脲醛和苯酚甲醛）相当。利用这种粘合剂，我们制作了一个根瘤蚜属刨花板模型，其木质颗粒≤149 μm，粘合剂浓度为 12%，目标密度为 1 g/cm³，粘附在 30 cm × 30 cm × 30 cm 的标准模型尺寸上。随后，在 60-100 kVp 的 X 射线能量范围内，使用高灵敏度热致发光剂量计（TL-100H）将该刨花板模型的剂量特性与水模型和莹石模型的剂量特性进行了比较。研究结果表明，AP-Rhizophora spp.刨花板的深度剂量百分比（PDD）值与莹石模型和水模型的值非常接近，在 60 kVp 时差异最大。此外，刨花板的半值层（HVL）与莹石和水的半值层相似，尤其是在诊断 X 射线能量下。这些结果表明，AP 粘合剂可有效制作根瘤蚜属刨花板模型，其剂量测定特性与组织等效材料相当。
{"title":"Dosimetric evaluation of Rhizophora spp. particleboard bonded with animal protein adhesive at X-ray energies below 100 kVp","authors":"Ehsan Taghizadeh Tousi , Hamid Reza Sadeghi","doi":"10.1016/j.apradiso.2024.111538","DOIUrl":"10.1016/j.apradiso.2024.111538","url":null,"abstract":"<div><div>This research developed a bio-based adhesive (AP) derived from industrial slaughterhouse waste, comprising over 85% protein. The adhesive was characterized by a melting point of 193.14 °C, a neutral pH of 7, and a viscosity comparable to common wood adhesives such as urea-formaldehyde and phenol-formaldehyde. Utilizing this adhesive, a <em>Rhizophora</em> spp. particleboard phantom was produced, featuring wood particles of ≤149 μm, an adhesive concentration of 12%, and a target density of 1 g/cm³, adhering to a standard phantom dimension of 30 cm × 30 cm × 30 cm. The dosimetric properties of this particleboard phantom were subsequently compared with those of water and Perspex phantoms within an X-ray energy range of 60–100 kVp, employing high-sensitivity thermo-luminescent dosimeters (TL–100H). The findings indicated that the percentage depth dose (PDD) values of the AP-<em>Rhizophora</em> spp. particleboard were closely aligned with those of the Perspex and water phantoms, with the greatest discrepancy observed at 60 kVp. Additionally, the half-value layer (HVL) of the particleboard was similar to those of Perspex and water, particularly at diagnostic X-ray energies. These results demonstrate that the AP adhesive is effective for creating <em>Rhizophora</em> spp. particleboard phantoms, exhibiting dosimetric properties comparable to tissue-equivalent materials.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111538"},"PeriodicalIF":1.6,"publicationDate":"2024-10-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142444976","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-01DOI: 10.1016/j.apradiso.2024.111537
Yifan Tian , Weihua Zeng , Haoran Liu , Juncheng Liang , Zihao Fan , Qianqian Zhou , Zhijie Yang , Qisheng Zhang , Shengli Hou
When employing the TDCR method for standardization of low-activity liquid scintillation samples, fluctuations in system background can significantly impact both measurement uncertainties and minimum detectable activity (MDA). To mitigate this impact, a TDCR counting system with anti-coincidence detectors was developed. By analyzing the time difference distribution spectrum between the anti-coincidence channel and β channel, optimal parameters for the anti-coincidence module are determined. The objective of the study is to enhance the effectiveness of the anti-coincidence technique while minimizing the removal of real events. Finally, two sets of 3H and 14C samples with known activities of around 1 Bq are prepared via dilution to validate the performance of the system. Compared to without anti-coincidence, the background has been reduced by nearly 84%, leading to decreased fluctuations in the activity results.
{"title":"Development of a TDCR counting system with anti-coincidence detectors","authors":"Yifan Tian , Weihua Zeng , Haoran Liu , Juncheng Liang , Zihao Fan , Qianqian Zhou , Zhijie Yang , Qisheng Zhang , Shengli Hou","doi":"10.1016/j.apradiso.2024.111537","DOIUrl":"10.1016/j.apradiso.2024.111537","url":null,"abstract":"<div><div>When employing the TDCR method for standardization of low-activity liquid scintillation samples, fluctuations in system background can significantly impact both measurement uncertainties and minimum detectable activity (MDA). To mitigate this impact, a TDCR counting system with anti-coincidence detectors was developed. By analyzing the time difference distribution spectrum between the anti-coincidence channel and β channel, optimal parameters for the anti-coincidence module are determined. The objective of the study is to enhance the effectiveness of the anti-coincidence technique while minimizing the removal of real events. Finally, two sets of <sup>3</sup>H and <sup>14</sup>C samples with known activities of around 1 Bq are prepared via dilution to validate the performance of the system. Compared to without anti-coincidence, the background has been reduced by nearly 84%, leading to decreased fluctuations in the activity results.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111537"},"PeriodicalIF":1.6,"publicationDate":"2024-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142438304","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-10-01DOI: 10.1016/j.apradiso.2024.111536
H. Naik , R.J. Singh , S.P. Dange , W. Jang
In the epi-cadmium neutron induced fission of 235U, independent isomeric yield ratios (IR) of fission products 130,132Sb, 131,133Te, 134,136I, 135Xe and 138Cs have been measured by using an off-line gamma-ray spectrometric technique. The average neutron energy of the epi-cadmium reactor neutron spectrum is 1.9 MeV. From the IR values, the root mean square fragment angular momenta (JRMS) were deduced by using spin dependent statistical model analysis. The IR and JRMS values of considered fission products in the epi-cadmium neutron induced fission of 235U were compared with the literature data in the thermal neutron induced fission of 235U to examine the influence of excitation energy on nuclear structure effect.
{"title":"Independent isomeric yield ratios of fission products in the epi-cadmium neutron induced fission of 235U","authors":"H. Naik , R.J. Singh , S.P. Dange , W. Jang","doi":"10.1016/j.apradiso.2024.111536","DOIUrl":"10.1016/j.apradiso.2024.111536","url":null,"abstract":"<div><div>In the epi-cadmium neutron induced fission of <sup>235</sup>U, independent isomeric yield ratios (IR) of fission products <sup>130,132</sup>Sb, <sup>131,133</sup>Te, <sup>134,136</sup>I, <sup>135</sup>Xe and <sup>138</sup>Cs have been measured by using an off-line gamma-ray spectrometric technique. The average neutron energy of the epi-cadmium reactor neutron spectrum is 1.9 MeV. From the IR values, the root mean square fragment angular momenta (<em>J</em><sub><em>RMS</em></sub>) were deduced by using spin dependent statistical model analysis. The IR and J<sub>RMS</sub> values of considered fission products in the epi-cadmium neutron induced fission of <sup>235</sup>U were compared with the literature data in the thermal neutron induced fission of <sup>235</sup>U to examine the influence of excitation energy on nuclear structure effect.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111536"},"PeriodicalIF":1.6,"publicationDate":"2024-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142374989","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-09-28DOI: 10.1016/j.apradiso.2024.111535
N.S. Tawade , S. Kumar , S. Patra , R. Tripathi , C.S. Datrik , P.K. Pujari , R.G. Thomas , G. Mishra , A. Kumar , S. De , H. Kumawat
The (n,γ) reaction cross-section for the elements 68Zn, 96Zr, 121Sb and 123Sb, present in the reactor structural/shielding materials, was measured by neutron activation technique in the neutron energy region of 1–2 MeV as very limited data is available in this energy range. Further, the neutron spectrum peaks in this energy region for the fast breeder reactors and proposed accelerator driven sub-critical systems. The natural strontium (natSr) element was used as a neutron flux monitor by considering effective combined reaction cross-section for 86Sr(n,γ)87Srm and 87Sr(n,n′)87Srm reactions. The pellets of mixture of sample and monitor were irradiated by a quasi-mono energetic fast neutron beam, generated by 7Li(p,n)7Be reaction at FOTIA, Bhabha Atomic Research Centre, Mumbai, India. The activity of activation products was measured by off-line gamma-ray spectrometry using High Purity Germanium Detector (HPGe). The present data with improved uncertainty and covariance analysis enhance the cross-section data base for better constraining the evaluated data and theoretical models. The theoretical (n,γ) reaction cross-sections were calculated using TALYS 1.96, which could reasonably explain the present data with the Fermi gas level density prescription.
{"title":"Measurement of fast neutron induced (n,γ) reaction cross-section of 68Zn, 96Zr, 121Sb and 123Sb in the energy range of 1 to 2 MeV","authors":"N.S. Tawade , S. Kumar , S. Patra , R. Tripathi , C.S. Datrik , P.K. Pujari , R.G. Thomas , G. Mishra , A. Kumar , S. De , H. Kumawat","doi":"10.1016/j.apradiso.2024.111535","DOIUrl":"10.1016/j.apradiso.2024.111535","url":null,"abstract":"<div><div>The (n,γ) reaction cross-section for the elements <sup>68</sup>Zn, <sup>96</sup>Zr, <sup>121</sup>Sb and <sup>123</sup>Sb, present in the reactor structural/shielding materials, was measured by neutron activation technique in the neutron energy region of 1–2 MeV as very limited data is available in this energy range. Further, the neutron spectrum peaks in this energy region for the fast breeder reactors and proposed accelerator driven sub-critical systems. The natural strontium (<sup>nat</sup>Sr) element was used as a neutron flux monitor by considering effective combined reaction cross-section for <sup>86</sup>Sr(n,γ)<sup>87</sup>Sr<sup>m</sup> and <sup>87</sup>Sr(n,n′)<sup>87</sup>Sr<sup>m</sup> reactions. The pellets of mixture of sample and monitor were irradiated by a quasi-mono energetic fast neutron beam, generated by <sup>7</sup>Li(p,n)<sup>7</sup>Be reaction at FOTIA, Bhabha Atomic Research Centre, Mumbai, India. The activity of activation products was measured by off-line gamma-ray spectrometry using High Purity Germanium Detector (HPGe). The present data with improved uncertainty and covariance analysis enhance the cross-section data base for better constraining the evaluated data and theoretical models. The theoretical (n,γ) reaction cross-sections were calculated using TALYS 1.96, which could reasonably explain the present data with the Fermi gas level density prescription.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111535"},"PeriodicalIF":1.6,"publicationDate":"2024-09-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142364178","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-09-26DOI: 10.1016/j.apradiso.2024.111534
Ahmet Caf , Ferdi Akman , Hasan Oğul , Mustafa Recep Kaçal
This study investigates how gamma rays, neutrons, and electrons interact with five commonly found indoor plants: Spathiphyllum wallisii (SW), Ficus elastica (FE), Dieffenbachia camilla (DC), Schefflera arboricola (SA), and Ficus benjamina (FB). Utilizing experimental measurements (with HPGe detector), Monte Carlo simulations (GEANT4 and FLUKA), and theoretical calculations (ESTAR and WinXCOM), some radiation interaction parameters for gamma rays, fast neutrons, thermal neutrons, and electrons were determined. Secondary particle generation was also analyzed to provide a comprehensive assessment. The determined linear attenuation coefficients with the help of the WinXCOM are 0.1376, 0.1662, 0.1385, 0.1651 and 0.1698 cm−1 for SW, FE, DC, SA and FB, respectively. The calculated total macroscopic cross sections for indoor plants in the same sample order are 2.0290, 2.0350, 2.0285, 2.0363 and 2.0362 cm−1. Among the investigated plants, FB exhibited the highest gamma ray interaction, while SA and FB showed superior interaction against fast neutrons compared to SW and DC. The findings reveal significant variations in interaction effectiveness and secondary radiation production across these plants, offering valuable insights for radiation safety and environmental health evaluations.
{"title":"A study on the interaction parameters of charged and uncharged radiation types with some indoor plants","authors":"Ahmet Caf , Ferdi Akman , Hasan Oğul , Mustafa Recep Kaçal","doi":"10.1016/j.apradiso.2024.111534","DOIUrl":"10.1016/j.apradiso.2024.111534","url":null,"abstract":"<div><div>This study investigates how gamma rays, neutrons, and electrons interact with five commonly found indoor plants: <em>Spathiphyllum wallisii</em> (SW), <em>Ficus elastica</em> (FE), <em>Dieffenbachia camilla</em> (DC), <em>Schefflera arboricola</em> (SA), and <em>Ficus benjamina</em> (FB). Utilizing experimental measurements (with HPGe detector), Monte Carlo simulations (GEANT4 and FLUKA), and theoretical calculations (ESTAR and WinXCOM), some radiation interaction parameters for gamma rays, fast neutrons, thermal neutrons, and electrons were determined. Secondary particle generation was also analyzed to provide a comprehensive assessment. The determined linear attenuation coefficients with the help of the WinXCOM are 0.1376, 0.1662, 0.1385, 0.1651 and 0.1698 cm<sup>−1</sup> for SW, FE, DC, SA and FB, respectively. The calculated total macroscopic cross sections for indoor plants in the same sample order are 2.0290, 2.0350, 2.0285, 2.0363 and 2.0362 cm<sup>−1</sup>. Among the investigated plants, FB exhibited the highest gamma ray interaction, while SA and FB showed superior interaction against fast neutrons compared to SW and DC. The findings reveal significant variations in interaction effectiveness and secondary radiation production across these plants, offering valuable insights for radiation safety and environmental health evaluations.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111534"},"PeriodicalIF":1.6,"publicationDate":"2024-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142339953","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-09-25DOI: 10.1016/j.apradiso.2024.111529
G. Souadi , O. Hakami , U.H. Kaynar , M.B. Coban , H. Aydin , O. Madkhali , T. Zelai , M. Ayvacikli , N. Can
This study investigates the structural and photoluminescence (PL) characteristics of Tb3+-incorporated K3Y(BO2)6 (KYBO) phosphors synthesized via a microwave-assisted sol-gel technique. X-ray diffraction (XRD) and Rietveld refinement confirmed the formation of a pure hexagonal phase, with lattice expansion due to Tb³⁺ doping. PL studies revealed strong green emissions centered at 541 nm, attributed to the ⁵D₄ → ⁷F₅ transitions of Tb³⁺ ions, with the highest intensity observed at 5 wt% Tb³⁺. A decrease in emission was observed at higher concentrations due to concentration quenching. Temperature-dependent PL measurements revealed reverse thermal quenching enhancing PL intensity. Chromaticity analysis based on CIE 1931 coordinates showed stable green emission across all concentrations, with a maximum color purity of 89.74% observed for the KYBO:3 wt% Tb³⁺ sample. The results, along with reverse thermal quenching behavior observed between 470K and 550K, suggest that these phosphors exhibit excellent potential for lighting and display technologies.
{"title":"High temperature photoluminescence dependence and energy migration of Tb3+-Incorporated K3Y(BO2)6 phosphors","authors":"G. Souadi , O. Hakami , U.H. Kaynar , M.B. Coban , H. Aydin , O. Madkhali , T. Zelai , M. Ayvacikli , N. Can","doi":"10.1016/j.apradiso.2024.111529","DOIUrl":"10.1016/j.apradiso.2024.111529","url":null,"abstract":"<div><div>This study investigates the structural and photoluminescence (PL) characteristics of Tb<sup>3+</sup>-incorporated K<sub>3</sub>Y(BO<sub>2</sub>)<sub>6</sub> (KYBO) phosphors synthesized via a microwave-assisted sol-gel technique. X-ray diffraction (XRD) and Rietveld refinement confirmed the formation of a pure hexagonal phase, with lattice expansion due to Tb³⁺ doping. PL studies revealed strong green emissions centered at 541 nm, attributed to the ⁵D₄ → ⁷F₅ transitions of Tb³⁺ ions, with the highest intensity observed at 5 wt% Tb³⁺. A decrease in emission was observed at higher concentrations due to concentration quenching. Temperature-dependent PL measurements revealed reverse thermal quenching enhancing PL intensity. Chromaticity analysis based on CIE 1931 coordinates showed stable green emission across all concentrations, with a maximum color purity of 89.74% observed for the KYBO:3 wt% Tb³⁺ sample. The results, along with reverse thermal quenching behavior observed between 470K and 550K, suggest that these phosphors exhibit excellent potential for lighting and display technologies.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111529"},"PeriodicalIF":1.6,"publicationDate":"2024-09-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142323798","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2024-09-25DOI: 10.1016/j.apradiso.2024.111530
Connor K. Holiski , Aidan A. Bender , Peñafrancia F. Monte , Heather M. Hennkens , Mary F. Embree , Meng-Jen (Vince) Wang , Glenn E. Sjoden , Tara Mastren
Targeted radiotherapy (TRT) is an increasingly prominent area of research in nuclear medicine, particularly in the context of treating cancerous tumors. One radionuclide of considerable interest for TRT is terbium-161 (t1/2 = 6.95 days), which undergoes beta emission and shares similar decay properties as 177Lu (FDA-approved as LUTATHERA® and PLUVICTO®). Besides beta emission, 161Tb also emits a significant number of conversion and Auger electrons further enhancing its therapeutic potential. Terbium-161 can be produced using nuclear reactors through an indirect neutron capture reaction, , from 160Gd targets. However, a key challenge in utilizing 161Tb for TRT lies in effectively separating target and product materials to attain high specific activity for radiolabeling. Here, we detail the production of no-carrier added 161Tb using low flux research reactors (mean thermal (<0.625 eV) neutron flux: ) like the University of Utah TRIGA Reactor, using enriched 160Gd2O3 targets (1.5 ± 0.3 μCi of 161Tb per mg of 160Gd target per hour of irradiation). We also developed a separation technique based on cation exchange and extraction chromatography, suitable for mCi level irradiations with targets exceeding 200 mg. In a simulated full-scale irradiation, 161Tb was successfully isolated from large mass targets using cation exchange (AG 50W-X8, with 2-hydroxyisobutyric acid at 70 mM, pH 4.75) and extraction chromatography (LN Resin, 0.5–0.75 M HNO3) methods. This resulted in high apparent molar activities of [161Tb]Tb-DOTA (113 ± 3 MBq/nmol), demonstrating high purity 161Tb relevant for potential future preclinical applications.
{"title":"The production and separation of 161Tb with high specific activity at the University of Utah","authors":"Connor K. Holiski , Aidan A. Bender , Peñafrancia F. Monte , Heather M. Hennkens , Mary F. Embree , Meng-Jen (Vince) Wang , Glenn E. Sjoden , Tara Mastren","doi":"10.1016/j.apradiso.2024.111530","DOIUrl":"10.1016/j.apradiso.2024.111530","url":null,"abstract":"<div><div>Targeted radiotherapy (TRT) is an increasingly prominent area of research in nuclear medicine, particularly in the context of treating cancerous tumors. One radionuclide of considerable interest for TRT is terbium-161 (t<sub>1/2</sub> = 6.95 days), which undergoes beta emission and shares similar decay properties as <sup>177</sup>Lu (FDA-approved as LUTATHERA® and PLUVICTO®). Besides beta emission, <sup>161</sup>Tb also emits a significant number of conversion and Auger electrons further enhancing its therapeutic potential. Terbium-161 can be produced using nuclear reactors through an indirect neutron capture reaction, <span><math><mmultiscripts><mi>G</mi><mprescripts></mprescripts><mn>64</mn><mn>160</mn></mmultiscripts><mi>d</mi><mfenced><mrow><mi>n</mi><mo>,</mo><mi>γ</mi></mrow></mfenced><mmultiscripts><mi>G</mi><mprescripts></mprescripts><mn>64</mn><mn>161</mn></mmultiscripts><mi>d</mi><mo>→</mo><mfenced><mrow><mn>3.66</mn><mspace></mspace><mi>min</mi><mo>,</mo><msup><mi>β</mi><mo>−</mo></msup></mrow></mfenced><mmultiscripts><mi>T</mi><mprescripts></mprescripts><mn>65</mn><mn>161</mn></mmultiscripts><mi>b</mi></math></span>, from <sup>160</sup>Gd targets. However, a key challenge in utilizing <sup>161</sup>Tb for TRT lies in effectively separating target and product materials to attain high specific activity for radiolabeling. Here, we detail the production of no-carrier added <sup>161</sup>Tb using low flux research reactors (mean thermal (<0.625 eV) neutron flux: <span><math><mrow><mn>1.356</mn><mo>×</mo><msup><mn>10</mn><mn>12</mn></msup><mspace></mspace><mi>n</mi><mo>∙</mo><msup><mtext>cm</mtext><mrow><mo>−</mo><mn>2</mn></mrow></msup><mo>∙</mo><msup><mi>s</mi><mrow><mo>−</mo><mn>1</mn></mrow></msup></mrow></math></span>) like the University of Utah TRIGA Reactor, using enriched <sup>160</sup>Gd<sub>2</sub>O<sub>3</sub> targets (1.5 ± 0.3 μCi of <sup>161</sup>Tb per mg of <sup>160</sup>Gd target per hour of irradiation). We also developed a separation technique based on cation exchange and extraction chromatography, suitable for mCi level irradiations with targets exceeding 200 mg. In a simulated full-scale irradiation, <sup>161</sup>Tb was successfully isolated from large mass targets using cation exchange (AG 50W-X8, with 2-hydroxyisobutyric acid at 70 mM, pH 4.75) and extraction chromatography (LN Resin, 0.5–0.75 M HNO<sub>3</sub>) methods. This resulted in high apparent molar activities of [<sup>161</sup>Tb]Tb-DOTA (113 ± 3 MBq/nmol), demonstrating high purity <sup>161</sup>Tb relevant for potential future preclinical applications.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111530"},"PeriodicalIF":1.6,"publicationDate":"2024-09-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142339954","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Proton therapy is a rapidly progressing modality with a significant impact on lung cancer treatment. However, there are concerns about the subsequent effects of secondary radiation in out-of-field organs. Thus, the present study aimed to evaluate the risk of subsequent secondary cancers within non-target organs during proton therapy for lung cancer. A Monte Carlo model of the International Commission on Radiological Protection (ICRP) 110 male phantom was employed to calculate the absorbed dose associated with secondary photons and neutrons within out-of-field organs for different tumor locations. The risk of induced secondary cancers was then estimated using the Biological Effects of Ionizing Radiation Committee (BEIR) VII and National Council on Radiation Protection and Measurements (NCRP) 116 risk models. Organs close to the tumor, such as the heart, esophagus, thymus, and liver, received the highest equivalent doses. The calculated equivalent doses increased as the tumor depth increased from 4–8 cm to 12–16 cm. The contribution of neutrons to the total equivalent dose was dominant (up to 90%) in most of the organs studied. The calculated risks of secondary cancers were higher in the liver and esophagus compared with other organs when using the BEIR risk model. The maximum risk value was obtained for the left lung when the NCRP 116 risk model was used. Furthermore, the estimated risks of secondary malignancies increased with the tumor depth using both risk models. The calculated risks of radiation-induced secondary cancers were relatively lower than the baseline cancer risks. However, extra attention is warranted to minimize subsequent secondary cancers after proton therapy for lung cancer.
{"title":"Assessment of secondary cancer risks within non-target organs during proton therapy for lung cancer: A Monte Carlo study","authors":"Sayyed Bijan Jia , Reza Shamsabadi , Leili Mogheiseh , Hamid Reza Baghani","doi":"10.1016/j.apradiso.2024.111532","DOIUrl":"10.1016/j.apradiso.2024.111532","url":null,"abstract":"<div><div>Proton therapy is a rapidly progressing modality with a significant impact on lung cancer treatment. However, there are concerns about the subsequent effects of secondary radiation in out-of-field organs. Thus, the present study aimed to evaluate the risk of subsequent secondary cancers within non-target organs during proton therapy for lung cancer. A Monte Carlo model of the International Commission on Radiological Protection (ICRP) 110 male phantom was employed to calculate the absorbed dose associated with secondary photons and neutrons within out-of-field organs for different tumor locations. The risk of induced secondary cancers was then estimated using the Biological Effects of Ionizing Radiation Committee (BEIR) VII and National Council on Radiation Protection and Measurements (NCRP) 116 risk models. Organs close to the tumor, such as the heart, esophagus, thymus, and liver, received the highest equivalent doses. The calculated equivalent doses increased as the tumor depth increased from 4–8 cm to 12–16 cm. The contribution of neutrons to the total equivalent dose was dominant (up to 90%) in most of the organs studied. The calculated risks of secondary cancers were higher in the liver and esophagus compared with other organs when using the BEIR risk model. The maximum risk value was obtained for the left lung when the NCRP 116 risk model was used. Furthermore, the estimated risks of secondary malignancies increased with the tumor depth using both risk models. The calculated risks of radiation-induced secondary cancers were relatively lower than the baseline cancer risks. However, extra attention is warranted to minimize subsequent secondary cancers after proton therapy for lung cancer.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"214 ","pages":"Article 111532"},"PeriodicalIF":1.6,"publicationDate":"2024-09-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142326812","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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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