{"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}
{"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}
{"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}
A.I. Castro-Campoy , C. Cruz-Vázquez , R. Pérez-Salas , V.M. Castaño , R. Bernal
{"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}
{"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}
{"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}
{"title":"Testing a biexponential kinetic model for the heterogeneous isotopic exchange of phosphate ions on several types of soil","authors":"János Z. Vörös, József Kónya, Noémi M. Nagy","doi":"10.1016/j.apradiso.2024.111602","DOIUrl":"10.1016/j.apradiso.2024.111602","url":null,"abstract":"<div><div>In this study, a new kinetic equation was applied for the heterogeneous isotopic exchange of phosphate ions on soil. Phosphate sorption on chernozem, marshy meadow and meadow soil was studied by P-32 heterogeneous isotopic exchange in steady-state. The soil samples were incubated with 5 different amounts of KH<sub>2</sub>PO<sub>4</sub> for 1, 3, 13, 10, 12 and 22 weeks. Then they were equilibrated with destilled water, and after the equilibrium was reached, H<sub>3</sub><sup>32</sup>PO<sub>4</sub> radiotracer was added to the soil solution. At different times samples were taken from the soil solution, and radioactivities were determined by liquid scintillation (LSC) technique. The concentration of phosphate ions was determined by photometry. The relative radioactivity of soil vs time could be fitted well by the biexponential kinetic equation, which assumes two types of weakly bonded phosphate. From the fitting parameters of the biexponential equation and the phosphate concentration determined by photometry the amounts of the two types of weakly bonded phosphate and their steady-state rates were determined. The amounts of weakly bonded phosphate were plotted vs phosphate concentration – data points could be fitted by a Langmuir-like representation or the S-shape sorption isotherms. The rate orders of the desorption proved to be 1 or 2; rate constants were determined. It can be concluded that in some cases cooperative sorption can occure, which can be due to hydrogen bonding between the hydrogenphosphate ions on the surface.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111602"},"PeriodicalIF":1.6,"publicationDate":"2024-11-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142746262","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}
Jinlong Yong, Yushou Song, Yunlong Zhao, Yingwei Hou, Huilan Liu
{"title":"A matrix effect correction method for fissile nuclear material mass measurement by delayed neutrons","authors":"Jinlong Yong, Yushou Song, Yunlong Zhao, Yingwei Hou, Huilan Liu","doi":"10.1016/j.apradiso.2024.111600","DOIUrl":"10.1016/j.apradiso.2024.111600","url":null,"abstract":"<div><div>Active neutron interrogation (ANI), extensively employed in nuclear safeguards, is sensitive to the presence of special nuclear materials (SNMs). However, the interaction of the matrix material with neutrons weakens the precision of fissile mass measurements by the ANI system. Therefore, it is paramount to ensure that the evaluation of the fissile mass remains unaffected by the matrix and enhances the assay performance of the ANI system. The present work proposes a matrix correction method based on the neutron flux monitor group (NFMG) response to tackle this issue. Based on the varying influence of different matrices on the neutron energies and fluxes, the NFMG response can be used to quantify the matrix effects. This allows the method to enable the identification of matrices already present in the database and has the potential to compensate for unknown matrix effects. To validate the applicability and accuracy of this method, a Shuffler system model and various matrix compositions were developed using the Geant4 toolkit. The results demonstrate that the improved simulated annealing (SA) algorithm exhibits excellent stability when confronted with varying enrichments and distributions of U<sub>3</sub>O<sub>8</sub> materials. When the threshold is set at <span><math><mrow><mi>α</mi></mrow></math></span> ≥ 0.90, the improved SA algorithm achieves a successful identification rate of 90.4% for matrices. Simultaneously, using the response equation, the average relative deviation of the corrected <sup>235</sup>U mass is no more than 7%. For the unknown matrix, the correction capability of this method relies primarily on the construction of the reference database and the response equation. In most cases, the average relative deviation of the corrected <sup>235</sup>U mass is less than 28%.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"216 ","pages":"Article 111600"},"PeriodicalIF":1.6,"publicationDate":"2024-11-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142723537","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}
{"title":"Impact of low dose of gamma irradiation on thin films of Bismuth Tri-iodide","authors":"Alka Garg , Ruby Jindal","doi":"10.1016/j.apradiso.2024.111598","DOIUrl":"10.1016/j.apradiso.2024.111598","url":null,"abstract":"<div><div>Thin films of Bismuth Tri-iodide BiI<sub>3</sub> were synthesized on a glass substrate by the thermal vacuum deposition technique. Films were exposed to gamma radiations of two doses 10 Gy and 50 Gy. Structural and optical properties of films were studied through X-ray Diffraction and UV spectroscopy both before and after the gamma irradiation. The effect of gamma radiations on microstructure parameters i.e. crystallite size and the micro-strain were studied qualitatively and quantitively. The observed increase in crystallite size and decrease in micro-strain is due to localized heating of crystallites which results in the merging of small crystallites and their assembly leading to the formation of larger crystallites as evident from X-ray Diffraction after gamma irradiation. Effect on the optical constants namely refractive index and extinction coefficient for different doses was also enumerated to throw light on the change in optical density of this material on gamma irradiation. It is observed that the refractive index n increases with an increase in the doses of gamma irradiation. The increase in optical density could be attributed either to the displacement of atoms from lattice sites to the interstitial sites or to the self-assembly behavior of the crystallites on irradiation. The absorption coefficient follows Urbach's empirical relation and exhibits exponential dependency on photon energy close to the band edge. Calculating Urbach's energy provides insight into the emergence of localized states at the energy gap's edges.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"216 ","pages":"Article 111598"},"PeriodicalIF":1.6,"publicationDate":"2024-11-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142715225","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}
{"title":"Mapping sensitivity of CVD diamond detector using synchrotron micro-beam","authors":"Mohamed A.E. Abdel-Rahman , Mohamed Y.M. Mohsen , A. Abdelghafar Galahom , Emad Ghandourah , Essam M. Banoqitah , Nicola Tartoni , Annika Lohstroh","doi":"10.1016/j.apradiso.2024.111594","DOIUrl":"10.1016/j.apradiso.2024.111594","url":null,"abstract":"<div><div>In this project, we conducted micro-beam sensitivity mapping using the Diamond Light Source (DLS) synchrotron. We fabricated three samples with distinct metal contacts: Platinum (HPS-Pt) and Aluminium/Platinum (HPS-Al/Pt) on high-quality single crystal CVD diamond, and Platinum (VS-Pt) on lower purity single crystal CVD diamond. Our objective was to identify the most suitable sample for synchrotron measurements, particularly focusing on the lower purity sample due to its unique characteristics, such as thin nitrogen lines and substrate area.</div><div>High spatial resolution sensitivity maps were obtained for the lower purity sample using a micro step displacement of up to 10 μm, revealing detailed nitrogen lines. We observed that bias polarity significantly influenced the photocurrent, with negative bias yielding higher photocurrents, possibly due to polarisation effects. Near nitrogen lines, we noted a slow rise time and an increased stabilization time with bias, alongside a prolonged decay to dark current.</div><div>For the HPS-Al/Pt sample, we found no improvement in current response homogeneity, therefore reliability, with bias; instead, we recorded high dark currents and unstable signals, particularly at negative bias. Conversely, the HPS-Pt sample exhibited a uniform response at both +50V and −50V in the central region of the sensitivity maps. This response became increasingly homogeneous at 100V and further improved up to 200V, suggesting that HPS-Pt is the most suitable candidate for synchrotron measurements.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"216 ","pages":"Article 111594"},"PeriodicalIF":1.6,"publicationDate":"2024-11-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142723536","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}