Pub Date : 2024-11-30DOI: 10.1016/j.apradiso.2024.111615
Ahmad Kurniawan , Isa Mahendra , Muhamad Basit Febrian , Marhendra Satria Utama , Julia Windi Gunadi , Roro Wahyudianingsih , Ronny Lesmana , Iim Halimah , Maula Eka Sriyani , Eva Maria Widyasari , Teguh Hafiz Ambar Wibawa , Asep Rizaludin , Crhisterra Ellen Kusumaningrum , Dani Gustaman Syarif
Photodynamic therapy has been recognized as a viable approach for lung cancer treatment. Some photosensitizer agents are known as X-ray sensitive and could improve radiotherapy efficacy. The use of nanoparticles for drug delivery and as photosensitizer agents offers various advantages because of their rapid cellular accumulation and distribution into target organs. On the other hand, several nanoparticles could trigger adverse effects during cancer treatment. In this article, the biological study of hydroxyapatite zirconium nanoparticles (HApZr) as photosensitizer candidates for X-ray-induced photodynamic therapy has been demonstrated in vitro and in vivo. This nanoparticle increased the intracellular reactive oxygen species (ROS) levels after the delivery of ionizing radiation at 5 Gy to a cancer cell line and showed higher cytotoxicity compared to non-irradiated treatment. In vitro cellular uptake based on cell imaging also indicated a promising intake and an ability to kill cancer cells. Subsequently, an in vivo evaluation using orthotopic lung cancer mouse models also showed their good accumulation in target organs, with lower accumulation in normal lung tissue. Moreover, studies of acute toxicity showed that a dose of 50 μg/mL yielded minor pathological changes on histological evaluations, which were supported by a biochemical analysis. In addition, HApZr nanoparticles also increase TNF-α which enhancing the cytotoxic effect after irradiation. Finally, these findings were important for further investigation of the clinical application of these HApZr nanoparticles for the treatment of patients with lung cancer.
{"title":"Biological evaluation of hydroxyapatite zirconium nanoparticle as a potential radiosensitizer for lung cancer X-ray induced photodynamic therapy","authors":"Ahmad Kurniawan , Isa Mahendra , Muhamad Basit Febrian , Marhendra Satria Utama , Julia Windi Gunadi , Roro Wahyudianingsih , Ronny Lesmana , Iim Halimah , Maula Eka Sriyani , Eva Maria Widyasari , Teguh Hafiz Ambar Wibawa , Asep Rizaludin , Crhisterra Ellen Kusumaningrum , Dani Gustaman Syarif","doi":"10.1016/j.apradiso.2024.111615","DOIUrl":"10.1016/j.apradiso.2024.111615","url":null,"abstract":"<div><div>Photodynamic therapy has been recognized as a viable approach for lung cancer treatment. Some photosensitizer agents are known as X-ray sensitive and could improve radiotherapy efficacy. The use of nanoparticles for drug delivery and as photosensitizer agents offers various advantages because of their rapid cellular accumulation and distribution into target organs. On the other hand, several nanoparticles could trigger adverse effects during cancer treatment. In this article, the biological study of hydroxyapatite zirconium nanoparticles (HApZr) as photosensitizer candidates for X-ray-induced photodynamic therapy has been demonstrated <em>in vitro</em> and <em>in vivo</em>. This nanoparticle increased the intracellular reactive oxygen species (ROS) levels after the delivery of ionizing radiation at 5 Gy to a cancer cell line and showed higher cytotoxicity compared to non-irradiated treatment. <em>In vitro</em> cellular uptake based on cell imaging also indicated a promising intake and an ability to kill cancer cells. Subsequently, an <em>in vivo</em> evaluation using orthotopic lung cancer mouse models also showed their good accumulation in target organs, with lower accumulation in normal lung tissue. Moreover, studies of acute toxicity showed that a dose of 50 μg/mL yielded minor pathological changes on histological evaluations, which were supported by a biochemical analysis. In addition, HApZr nanoparticles also increase TNF-α which enhancing the cytotoxic effect after irradiation. Finally, these findings were important for further investigation of the clinical application of these HApZr nanoparticles for the treatment of patients with lung cancer.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111615"},"PeriodicalIF":1.6,"publicationDate":"2024-11-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142779169","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 : 2024-11-28DOI: 10.1016/j.apradiso.2024.111601
Mostafa A. Mansor , Islam M. Nabil , Ali Y. Ellithi , A.R. Abdulghany , A.F. El Sayed
The radioactivity levels and risk factors have been assessed for twenty-eight positions of Black-Sand (BS) surface deposits along the Mediterranean Sea coast of north Sinai, Egypt. Twenty-eight surface samples were collected from six local cities: El Ressa, Abo Sakl, Ghornata, El Arish, El Masaed, and El Rommana. The activity concentration values of the nuclides of the 226Ra, 232Th, and 40K of the collected samples were measured using a P-type HPGe detector with a relative efficiency of ∼100% where it is defined at 1.33 MeV relative to a standard 3-inch diameter and 3-inch long NaI (TI) scintillator. El Ressa samples have relatively the most significant average values for 226Ra and 232Th, whereas El Rommana samples had the highest for 40K. The radiation hazard calculations for the collected BS samples indicated significantly lower values than the internationally recommended limits. The ambient dose rates of the six areas under study were monitored and found to range from 0.06 to 0.10 μSv.h−1.
{"title":"Risk assessment and natural radionuclide content in black-sand deposits of North Sinai coast, Egypt","authors":"Mostafa A. Mansor , Islam M. Nabil , Ali Y. Ellithi , A.R. Abdulghany , A.F. El Sayed","doi":"10.1016/j.apradiso.2024.111601","DOIUrl":"10.1016/j.apradiso.2024.111601","url":null,"abstract":"<div><div>The radioactivity levels and risk factors have been assessed for twenty-eight positions of Black-Sand (BS) surface deposits along the Mediterranean Sea coast of north Sinai, Egypt. Twenty-eight surface samples were collected from six local cities: El Ressa, Abo Sakl, Ghornata, El Arish, El Masaed, and El Rommana. The activity concentration values of the nuclides of the <sup>226</sup>Ra, <sup>232</sup>Th, and <sup>40</sup>K of the collected samples were measured using a P-type HPGe detector with a relative efficiency of ∼100% where it is defined at 1.33 MeV relative to a standard 3-inch diameter and 3-inch long NaI (TI) scintillator. El Ressa samples have relatively the most significant average values for <sup>226</sup>Ra and <sup>232</sup>Th, whereas El Rommana samples had the highest for <sup>40</sup>K. The radiation hazard calculations for the collected BS samples indicated significantly lower values than the internationally recommended limits. The ambient dose rates of the six areas under study were monitored and found to range from 0.06 to 0.10 μSv.h<sup>−1</sup>.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111601"},"PeriodicalIF":1.6,"publicationDate":"2024-11-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142790954","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 : 2024-11-26DOI: 10.1016/j.apradiso.2024.111605
Ajin Jo , Dongmyoung Hong , Wonho Lee
A 4π-field of view deep-learning-based collimator-less imaging system was designed with the Monte Carlo method and performance of the system was studied to verify the feasibility of system. A 4 × 4 × 4 voxelated single-volume GAGG(Ce) system and 57Co, 133Ba, 22Na, and 137Cs point sources at 2000 positions were modeled using Monte-Carlo N-particle transport code version 6 (MCNP6). Two types of the localized energy deposition acquired with a voxelated detector system with and without energy bins, were calculated. The F6 tally was used to provide the entire energy deposited in each voxel and the F8 tally to provide energy spectrum data for each voxel. This system utilized these energy deposition patterns depending on the source type and position to reconstruct the source distribution image. A fully convolutional network which is advantageous for the prediction of image outputs was used to estimate source distribution. The models utilizing energy deposition patterns generated on total energy deposition and energy spectrum data were trained with labels from 30° to 10 degree of full-width half-maximum (FWHM). As a result of training with single and multiple source data, types of isotopes and source locations were discriminated up to 5 sources when using energy spectral data, and the average image similarity between ground truth images and predicted ones were 0.9936 for total energy deposition model and 0.9966 for divided energy bin model. These results showed the feasibility of a collimator-less imaging system based on deep learning method that requires no filtration of any type of interaction.
{"title":"Feasibility verification of deep-learning based collimator-less imaging system using a voxelated GAGG(Ce) single volume detector: A Monte Carlo simulation","authors":"Ajin Jo , Dongmyoung Hong , Wonho Lee","doi":"10.1016/j.apradiso.2024.111605","DOIUrl":"10.1016/j.apradiso.2024.111605","url":null,"abstract":"<div><div>A 4π-field of view deep-learning-based collimator-less imaging system was designed with the Monte Carlo method and performance of the system was studied to verify the feasibility of system. A 4 × 4 × 4 voxelated single-volume GAGG(Ce) system and <sup>57</sup>Co, <sup>133</sup>Ba, <sup>22</sup>Na, and <sup>137</sup>Cs point sources at 2000 positions were modeled using Monte-Carlo N-particle transport code version 6 (MCNP6). Two types of the localized energy deposition acquired with a voxelated detector system with and without energy bins, were calculated. The F6 tally was used to provide the entire energy deposited in each voxel and the F8 tally to provide energy spectrum data for each voxel. This system utilized these energy deposition patterns depending on the source type and position to reconstruct the source distribution image. A fully convolutional network which is advantageous for the prediction of image outputs was used to estimate source distribution. The models utilizing energy deposition patterns generated on total energy deposition and energy spectrum data were trained with labels from 30° to 10 degree of full-width half-maximum (FWHM). As a result of training with single and multiple source data, types of isotopes and source locations were discriminated up to 5 sources when using energy spectral data, and the average image similarity between ground truth images and predicted ones were 0.9936 for total energy deposition model and 0.9966 for divided energy bin model. These results showed the feasibility of a collimator-less imaging system based on deep learning method that requires no filtration of any type of interaction.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111605"},"PeriodicalIF":1.6,"publicationDate":"2024-11-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142746265","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 : 2024-11-26DOI: 10.1016/j.apradiso.2024.111607
Thalhofer J.L , Silva R.L , Lima T.A , Silva G.R.A , Lima L.S , Hoffmann A , Lobão A.Q , Silva L.B , Orejuela C.O.P , Silva A.X , Lima I , Frota M , Suita J.C , Nunes R.C , Souza E.M , Lopes J.M , Kelecom A
Concern about radiation exposure to non-human biota and the environment has increased since the 1990s, resulting in several publications by UNSCEAR, IAEA, ICRP, among other agencies, which highlighted significant gaps in knowledge regarding non-human biota and resulted in the establishment of Reference Animals and Plants (RAPs). In Brazil, the Atlantic Forest biome has vast biodiversity, but there is a lack of information on the radiometric profile of plant species growing there. Thus, the objective of this study was to evaluate the radiometric profile of Ouratea miersii (Malpighiales), endemic to the Atlantic Rainforest, collected in the State of Rio de Janeiro, city of Niterói, at the Municipal Natural Park (PARNIT), which covers a region of protected Atlantic Rainforest. The specimen was completely collected (root, stem, leaf and soil including organic matter around the root), and each sample analyzed individually by gamma spectrometry using a HPGe detector (Canberra). The calculated activity concentrations (AC) indicated the presence of 40K, 226Ra and 228Ra, with significant AC of 40K in the soil (3901 Bq·kg−1). The 40K soil-plant transfer was 11.6%, being limited by some physiological mechanism and/or osmotic saturation, while the transfer factor for 226Ra was 45.3%. The dose rate in non-human biota due to AC's of 226Ra and 228Ra in soil was estimated by modeling with the ERICA Tool, which indicated the absence of adverse effect on non-human biota due to exposure. The radiological hazard index values (Raeq, ADR, AEDR, and ELCR) obtained from the soil AC collected at PARNIT were significantly higher than those from other locations in Brazil, and about three times the value reported by UNSCEAR (2000) due to a ⁴⁰K anomaly in the soil. For this reason, a more extensive environmental monitoring was necessary in the PARNIT region.
{"title":"Radiometric evaluation of Ouratea miersii (Planch.) Engl. From the Municipal Natural Park of Niterói, Brazilian Atlantic Rainforest remnant","authors":"Thalhofer J.L , Silva R.L , Lima T.A , Silva G.R.A , Lima L.S , Hoffmann A , Lobão A.Q , Silva L.B , Orejuela C.O.P , Silva A.X , Lima I , Frota M , Suita J.C , Nunes R.C , Souza E.M , Lopes J.M , Kelecom A","doi":"10.1016/j.apradiso.2024.111607","DOIUrl":"10.1016/j.apradiso.2024.111607","url":null,"abstract":"<div><div>Concern about radiation exposure to non-human biota and the environment has increased since the 1990s, resulting in several publications by UNSCEAR, IAEA, ICRP, among other agencies, which highlighted significant gaps in knowledge regarding non-human biota and resulted in the establishment of Reference Animals and Plants (RAPs). In Brazil, the Atlantic Forest biome has vast biodiversity, but there is a lack of information on the radiometric profile of plant species growing there. Thus, the objective of this study was to evaluate the radiometric profile of <em>Ouratea miersii</em> (Malpighiales), endemic to the Atlantic Rainforest, collected in the State of Rio de Janeiro, city of Niterói, at the Municipal Natural Park (PARNIT), which covers a region of protected Atlantic Rainforest. The specimen was completely collected (root, stem, leaf and soil including organic matter around the root), and each sample analyzed individually by gamma spectrometry using a HPGe detector (Canberra). The calculated activity concentrations (AC) indicated the presence of <sup>40</sup>K, <sup>226</sup>Ra and <sup>228</sup>Ra, with significant AC of <sup>40</sup>K in the soil (3901 Bq·kg<sup>−1</sup>). The <sup>40</sup>K soil-plant transfer was 11.6%, being limited by some physiological mechanism and/or osmotic saturation, while the transfer factor for <sup>226</sup>Ra was 45.3%. The dose rate in non-human biota due to AC's of <sup>226</sup>Ra and <sup>228</sup>Ra in soil was estimated by modeling with the ERICA Tool, which indicated the absence of adverse effect on non-human biota due to exposure. The radiological hazard index values (Raeq, ADR, AEDR, and ELCR) obtained from the soil AC collected at PARNIT were significantly higher than those from other locations in Brazil, and about three times the value reported by UNSCEAR (2000) due to a ⁴⁰K anomaly in the soil. For this reason, a more extensive environmental monitoring was necessary in the PARNIT region.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111607"},"PeriodicalIF":1.6,"publicationDate":"2024-11-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142746264","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 : 2024-11-26DOI: 10.1016/j.apradiso.2024.111599
F.K. Amanuel
Theoretical investigations were carried out for the production of the medically important 89Zr radionuclide. This radionuclide is produced in the interaction of a proton projectile with 89Y-target, a readily available target with greater purity at ≈ 5–60 MeV. The 89Y (p, n)89Zr production route, a promising avenue in the fields of medical imaging and radiopharmaceutical development, is of significant interest due to its potential to produce 89Zr, a radionuclide with a half-life of 78.41 h, suitable for various applications.
The TALYS-1.95(G) predicted production cross-sections were in very good agreement with the experimental cross-sections. This successful alignment was further confirmed by a strong positive Pearson's correlation between the TALYS-1.95(G) predicted and experimentally measured production cross-sections for 89Zr radionuclide produced via the 89Y (p, n)89Zr route.
Furthermore, the calculations of thick target yields have provided crucial information. It was confirmed that up to ≈38 MBq/μAh maximum production yield of 89Zr radionuclide, free from radio-isotopic impurities, can be achieved in the ≈5–13 MeV energy window. This information is not just essential, but it's profoundly enlightening for understanding the potential production capacity of the 89Y (p, n)89Zr route. It also guides us in planning practical supply options for medical applications using a small-sized cyclotron at proton-energies ≤13 MeV, enhancing our collective knowledge.
{"title":"Theoretical predictions to produce medical 89Zr radionuclide via the 89Y(p, n)89Zr route at ≈ 5–60 MeV: Comparison of experimental and theoretical production data","authors":"F.K. Amanuel","doi":"10.1016/j.apradiso.2024.111599","DOIUrl":"10.1016/j.apradiso.2024.111599","url":null,"abstract":"<div><div>Theoretical investigations were carried out for the production of the medically important <sup>89</sup>Zr radionuclide. This radionuclide is produced in the interaction of a proton projectile with <sup>89</sup>Y-target, a readily available target with greater purity at ≈ 5–60 MeV. The <sup>89</sup>Y (p, n)<sup>89</sup>Zr production route, a promising avenue in the fields of medical imaging and radiopharmaceutical development, is of significant interest due to its potential to produce <sup>89</sup>Zr, a radionuclide with a half-life of 78.41 h, suitable for various applications.</div><div>The TALYS-1.95(G) predicted production cross-sections were in very good agreement with the experimental cross-sections. This successful alignment was further confirmed by a strong positive Pearson's correlation between the TALYS-1.95(G) predicted and experimentally measured production cross-sections for <sup>89</sup>Zr radionuclide produced via the <sup>89</sup>Y (p, n)<sup>89</sup>Zr route.</div><div>Furthermore, the calculations of thick target yields have provided crucial information. It was confirmed that up to ≈38 MBq/μAh maximum production yield of <sup>89</sup>Zr radionuclide, free from radio-isotopic impurities, can be achieved in the ≈5–13 MeV energy window. This information is not just essential, but it's profoundly enlightening for understanding the potential production capacity of the <sup>89</sup>Y (p, n)<sup>89</sup>Zr route. It also guides us in planning practical supply options for medical applications using a small-sized cyclotron at proton-energies ≤13 MeV, enhancing our collective knowledge.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111599"},"PeriodicalIF":1.6,"publicationDate":"2024-11-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142779180","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}
Myxofibrosarcoma, a rare malignant tumor, predominantly affects the extremities of the elderly. Because of its invasive nature amputation is sometimes required, resulting in serious deterioration of quality of life. Therefore, cell lines established from amputated surgical specimens of myxofibrosarcoma in the upper limbs of elderly patients were used to create a myxofibrosarcoma-bearing animal model and to investigate the therapeutic effect of BNCT thereon. The results demonstrated selective destruction of tumor cells, suggesting the anti-tumor efficacy of BNCT on myxofibrosarcoma.
{"title":"Potential of boron neutron capture therapy (BNCT) for myxofibrosarcoma","authors":"Takuya Fujimoto , Tooru Andoh , Tamotsu Sudo , Ikuo Fujita , Yoshinori Sakurai , Takushi Takata , Hiroki Tanaka , Teruya Kawamoto , Shunsuke Yahiro , Shotaro Nakamura , Hitomi Hara , Naomasa Fukase , Toshihiro Akisue , Hideki Ichikawa , Ryosuke Kuroda , Minoru Suzuki","doi":"10.1016/j.apradiso.2024.111603","DOIUrl":"10.1016/j.apradiso.2024.111603","url":null,"abstract":"<div><div>Myxofibrosarcoma, a rare malignant tumor, predominantly affects the extremities of the elderly. Because of its invasive nature amputation is sometimes required, resulting in serious deterioration of quality of life. Therefore, cell lines established from amputated surgical specimens of myxofibrosarcoma in the upper limbs of elderly patients were used to create a myxofibrosarcoma-bearing animal model and to investigate the therapeutic effect of BNCT thereon. The results demonstrated selective destruction of tumor cells<strong>,</strong> suggesting the anti-tumor efficacy of BNCT on myxofibrosarcoma.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111603"},"PeriodicalIF":1.6,"publicationDate":"2024-11-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142779119","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}
The cumulative yield of the fission products within the mass range of 83–117 and 123–153 have been measured in the 6.61and 10.92 MeV quasi-mono-energetic neutron-induced fission of 238U by using an off-line γ-ray spectrometric technique. The neutron beams were obtained from the 7Li(p,n) reactions with the proton energies of 11 and 18.8 MeV. The mass chain yields were obtained from the cumulative yields by using charge distribution correction. The peak-to-valley (P/V) ratio, the average value of light mass (⟨AL⟩), heavy mass (⟨AH⟩) and the average number of neutrons (<ν>) were obtained from the mass yield data. The data in the 238U(n, f) reaction from the present work and literature at various energies were compared with the similar data in the 238U(γ, f) reaction and following observations were obtained. (i) In both the reactions, the mass yield distributions are double humped. (ii) The yield of fission products for A = 133–134, A = 138–139, and A = 143–144 and their complementary products are higher than those of other fission products due to the nuclear structure effect. (iii) The yield of symmetric product increases and thus the peak-to-valley (P/V) ratio decreases with excitation energy. (iv) With the increase of excitation energy, the <ν> vale increases in a similar way in both the reactions. (v) The changing trend of ⟨AL⟩ and ⟨AH⟩ values with the increase of excitation energy are entirely different in between the two reactions.
{"title":"Measurement of fission product yields in the quasi-mono-energetic neutron-induced fission of 238U","authors":"H. Naik , Meghna Karkera , Vibha Vansola , Santhi Sheela Yeraguntla , Mayur Mehta , S.V. Suryanarayana , R. Makwana , S.C. Sharma","doi":"10.1016/j.apradiso.2024.111608","DOIUrl":"10.1016/j.apradiso.2024.111608","url":null,"abstract":"<div><div>The cumulative yield of the fission products within the mass range of 83–117 and 123–153 have been measured in the 6.61and 10.92 MeV quasi-mono-energetic neutron-induced fission of <sup>238</sup>U by using an off-line γ-ray spectrometric technique. The neutron beams were obtained from the <sup>7</sup>Li(p,n) reactions with the proton energies of 11 and 18.8 MeV. The mass chain yields were obtained from the cumulative yields by using charge distribution correction. The peak-to-valley (P/V) ratio, the average value of light mass (⟨A<sub>L</sub>⟩), heavy mass (⟨A<sub>H</sub>⟩) and the average number of neutrons (<ν>) were obtained from the mass yield data. The data in the <sup>238</sup>U(n, f) reaction from the present work and literature at various energies were compared with the similar data in the <sup>238</sup>U(γ, f) reaction and following observations were obtained. (i) In both the reactions, the mass yield distributions are double humped. (ii) The yield of fission products for A = 133–134, A = 138–139, and A = 143–144 and their complementary products are higher than those of other fission products due to the nuclear structure effect. (iii) The yield of symmetric product increases and thus the peak-to-valley (P/V) ratio decreases with excitation energy. (iv) With the increase of excitation energy, the <<em>ν</em>> vale increases in a similar way in both the reactions. (v) The changing trend of ⟨<em>A</em><sub>L</sub>⟩ and ⟨<em>A</em><sub>H</sub>⟩ values with the increase of excitation energy are entirely different in between the two reactions.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111608"},"PeriodicalIF":1.6,"publicationDate":"2024-11-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142756775","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 : 2024-11-24DOI: 10.1016/j.apradiso.2024.111606
A.I. Castro-Campoy , C. Cruz-Vázquez , R. Pérez-Salas , V.M. Castaño , R. Bernal
The non-thermoluminescence afterglow-based dosimetry performance of self-agglomerating pellet-shaped CaSO4:Dy phosphors synthesized through a low-cost, environmentally friendly method is first reported. Thermoluminescence (TL) and afterglow (AG) were analyzed in samples exposed to beta particle irradiation in the dose range from 0.06 to 8.0 Gy. Characteristic TL glow curves consist of an intense TL maximum at 134 °C, a shoulder at 200 °C, and a maximum at 447 °C. CaSO4:Dy exhibits a highly sensitive AG response for 24 h with linear behavior from 0.06 Gy to 8.0 Gy. A remarkable reproducibility of both the TL and the AG response was observed in repeated irradiation–readout cycles with no need for pre-irradiation annealing. The synthesized CaSO4:Dy exhibits promising properties to be used as an AG-based dosimeter for real-time radiation detection and dosimetry. Moreover, this phosphor might be applied as a long persistent phosphor (LPP), being a cost-effective alternative to other available LPPs.
本文首次报道了一种低成本、环境友好的方法合成的自凝聚球团状CaSO4:Dy荧光粉的非热释光余辉剂量学性能。研究了在0.06 ~ 8.0 Gy剂量范围内β粒子辐照样品的热释光(TL)和余辉(AG)。特征TL发光曲线包括134°C时的强烈TL最大值,200°C时的肩部和447°C时的最大值。CaSO4:Dy在0.06 Gy ~ 8.0 Gy范围内表现出高度敏感的24 h AG响应。在不需要辐照前退火的情况下,在重复辐照-读出循环中观察到TL和AG响应的显著再现性。合成的CaSO4:Dy具有良好的性能,可作为基于ag的剂量计用于实时辐射检测和剂量测定。此外,该荧光粉可以作为长持久性荧光粉(LPP)应用,是其他可用的长持久性荧光粉的一种具有成本效益的替代品。
{"title":"Novel non-thermoluminescent CaSO4:Dy dosimeters","authors":"A.I. Castro-Campoy , C. Cruz-Vázquez , R. Pérez-Salas , V.M. Castaño , R. Bernal","doi":"10.1016/j.apradiso.2024.111606","DOIUrl":"10.1016/j.apradiso.2024.111606","url":null,"abstract":"<div><div>The non-thermoluminescence afterglow-based dosimetry performance of self-agglomerating pellet-shaped CaSO<sub>4</sub>:Dy phosphors synthesized through a low-cost, environmentally friendly method is first reported. Thermoluminescence (TL) and afterglow (AG) were analyzed in samples exposed to beta particle irradiation in the dose range from 0.06 to 8.0 Gy. Characteristic TL glow curves consist of an intense TL maximum at 134 °C, a shoulder at 200 °C, and a maximum at 447 °C. CaSO<sub>4</sub>:Dy exhibits a highly sensitive AG response for 24 h with linear behavior from 0.06 Gy to 8.0 Gy. A remarkable reproducibility of both the TL and the AG response was observed in repeated irradiation–readout cycles with no need for pre-irradiation annealing. The synthesized CaSO<sub>4</sub>:Dy exhibits promising properties to be used as an AG-based dosimeter for real-time radiation detection and dosimetry. Moreover, this phosphor might be applied as a long persistent phosphor (LPP), being a cost-effective alternative to other available LPPs.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111606"},"PeriodicalIF":1.6,"publicationDate":"2024-11-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142746261","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}
The combination of experimental measurements and simulations provides valuable insights into the performance and limitations of gamma-ray spectrometry, especially within a specified energy range. This study investigates the impact of cross-section variations on the response of high-purity germanium (HPGe) detectors, focusing on the energy range from 53 keV to 1408 keV.
Monte Carlo simulations using the MCNP5 code with two different cross-section libraries, ENDF/B.VI and JENDL-5, are conducted alongside a semi-empirical method utilizing ANGLE 4.0 software. This approach allows for a comprehensive exploration of how cross-section variations affect HPGe detector response.
The flexibility in library selection highlights the adaptability of MCNP to cater to specific energy requirements. The calculated efficiencies are then compared with experimental data to evaluate accuracy and reliability. The results reveal an agreement within [2–3%] between experimental and simulated values, particularly for energies above 121 keV. Notably, for low-energy ranges (53–121 keV), the ENDF/B.VI library achieves an accuracy within [3–5%], making it effective at capturing low-energy interactions and enhancing prediction precision. This accuracy highlights its suitability for capturing low-energy interactions and enhances prediction precision.
Overall, this study provides valuable insights into detector performance and underscores the significance of library choice in ensuring simulation accuracy.
{"title":"Investigating cross-section effects on HPGe detector response through computational and empirical approaches","authors":"Ghada Mellak , Wassila Boukhenfouf , Fatma Zohra Dehimi , Adnane Messai , Nour Eddine Hebboul","doi":"10.1016/j.apradiso.2024.111596","DOIUrl":"10.1016/j.apradiso.2024.111596","url":null,"abstract":"<div><div>The combination of experimental measurements and simulations provides valuable insights into the performance and limitations of gamma-ray spectrometry, especially within a specified energy range. This study investigates the impact of cross-section variations on the response of high-purity germanium (HPGe) detectors, focusing on the energy range from 53 keV to 1408 keV.</div><div>Monte Carlo simulations using the MCNP5 code with two different cross-section libraries, ENDF/B.VI and JENDL-5, are conducted alongside a semi-empirical method utilizing ANGLE 4.0 software. This approach allows for a comprehensive exploration of how cross-section variations affect HPGe detector response.</div><div>The flexibility in library selection highlights the adaptability of MCNP to cater to specific energy requirements. The calculated efficiencies are then compared with experimental data to evaluate accuracy and reliability. The results reveal an agreement within [2–3%] between experimental and simulated values, particularly for energies above 121 keV. Notably, for low-energy ranges (53–121 keV), the ENDF/B.VI library achieves an accuracy within [3–5%], making it effective at capturing low-energy interactions and enhancing prediction precision. This accuracy highlights its suitability for capturing low-energy interactions and enhances prediction precision.</div><div>Overall, this study provides valuable insights into detector performance and underscores the significance of library choice in ensuring simulation accuracy.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"216 ","pages":"Article 111596"},"PeriodicalIF":1.6,"publicationDate":"2024-11-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142709016","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}
Tritium occurs in nuclear power plants. The energy of beta-rays from tritium is so low that detecting the beta-rays is challenging. Therefore, method of measuring tritium surface contamination is required. Liquid scintillators are generally used to measure the beta-rays. However, this method is complicated to use on-site. To measure tritium surface contamination on-site, we attempted to detect tritium using the GSENSE2020BSI back-illuminated sCMOS imager.
We used a tritium areal radiation source to validate the detection of beta rays from tritium. The beta-rays cause bright spots in images and spread to multipixel. The average number of the pixels by the beta-rays was 4.6 and covered within a 3x3 pixel region. The energy spectrum from 10,000 images with 3x3 binning patterns showed a continuous shape spectrum. The spectra shape was characteristic of beta-ray spectra, demonstrating that the energy spectrum could be obtained with low-energy beta rays from tritium using the back-illuminated sCMOS image sensor. The spectral shape was produced from a radiation simulation using Geant4. From the simulation, the sCMOS sensor was able to measure tritium contamination of 10 becquerels (Bq)/cm2 within 100 s and 4 Bq/cm2 within 480 s.
{"title":"Detection of β-ray from 3H with back illuminated sCMOS imager","authors":"Makoto Sasano , Masateru Hayashi , Nobukazu Teranishi","doi":"10.1016/j.apradiso.2024.111604","DOIUrl":"10.1016/j.apradiso.2024.111604","url":null,"abstract":"<div><div>Tritium occurs in nuclear power plants. The energy of beta-rays from tritium is so low that detecting the beta-rays is challenging. Therefore, method of measuring tritium surface contamination is required. Liquid scintillators are generally used to measure the beta-rays. However, this method is complicated to use on-site. To measure tritium surface contamination on-site, we attempted to detect tritium using the GSENSE2020BSI back-illuminated sCMOS imager.</div><div>We used a tritium areal radiation source to validate the detection of beta rays from tritium. The beta-rays cause bright spots in images and spread to multipixel. The average number of the pixels by the beta-rays was 4.6 and covered within a 3x3 pixel region. The energy spectrum from 10,000 images with 3x3 binning patterns showed a continuous shape spectrum. The spectra shape was characteristic of beta-ray spectra, demonstrating that the energy spectrum could be obtained with low-energy beta rays from tritium using the back-illuminated sCMOS image sensor. The spectral shape was produced from a radiation simulation using Geant4. From the simulation, the sCMOS sensor was able to measure tritium contamination of 10 becquerels (Bq)/cm<sup>2</sup> within 100 s and 4 Bq/cm<sup>2</sup> within 480 s.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111604"},"PeriodicalIF":1.6,"publicationDate":"2024-11-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142746263","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}