Radiation Physics and Chemistry最新文献

{"title":"Nuclide identification of radioactive sources from gamma spectra using artificial neural networks","authors":"N.P. Barradas ,&nbsp;A. Vieira ,&nbsp;M. Felizardo ,&nbsp;M. Matos","doi":"10.1016/j.radphyschem.2025.112692","DOIUrl":"10.1016/j.radphyschem.2025.112692","url":null,"abstract":"<div><div>Gamma spectroscopy is commonly used to identify the radionuclides present in samples or materials, by using the existing knowledge on the gamma ray energies and intensities for each radionuclide. However, when dealing with samples where the composition, internal configuration and shielding materials are unknown, as is the case, for instance, in nuclear security applications, the task can become challenging. Furthermore, gamma detection systems in field applications often do not have the high resolution typical of controlled laboratory conditions. In this work, we apply artificial intelligence techniques for automated identification of radioactive sources from gamma spectra obtained with a LaBr₃(Ce) detector with 3.6 % resolution at 662 keV. Combinations of up to 10 sources in each spectrum were used to train and test the artificial neural network developed. We report on the results, which show effective nuclide identification of radioactive sources from gamma spectra using ANNs.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"232 ","pages":"Article 112692"},"PeriodicalIF":2.8,"publicationDate":"2025-03-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143627984","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Performance evaluation of a new dosimetric system for lens dosimetry made using 3D printing","authors":"G.G. Nascimento ,&nbsp;O. Rodrigues Jr ,&nbsp;M. Savi ,&nbsp;D. Villani ,&nbsp;M.P.A. Potiens","doi":"10.1016/j.radphyschem.2025.112701","DOIUrl":"10.1016/j.radphyschem.2025.112701","url":null,"abstract":"<div><div>For some years now, the radiation dose received by the lens of the eye has been the subject of discussion in the field of radiological protection. As a result, dose limits have been reduced, and the lens has come to be considered a critical organ. This concern has become more intense in the interventional radiology environment, where occupational exposure is significant, increasing the likelihood of developing cataracts caused by radiation. The present study aims to evaluate the performance of a new model of dosimeter holder, manufactured by means of 3D printing, designed for lens dosimetry, comparing its performance using a cylinder phantom recommended by ICRU and an anthropomorphic simulator developed by 3D printing.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"232 ","pages":"Article 112701"},"PeriodicalIF":2.8,"publicationDate":"2025-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143627982","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Study of single event effect failure mechanism in P-GaN HEMTs based on experimental and TCAD simulation","authors":"Hao Huang ,&nbsp;Ying Wang ,&nbsp;Xin-Xing Fei ,&nbsp;Biao Sun ,&nbsp;Huolin Huang ,&nbsp;Yanxing Song ,&nbsp;Fei Cao","doi":"10.1016/j.radphyschem.2025.112698","DOIUrl":"10.1016/j.radphyschem.2025.112698","url":null,"abstract":"<div><div>This study systematically investigates the Single Event Burnout (SEB) mechanism of p-GaN gate AlGaN/GaN HEMTs. The experiment used 500 MeV Kr ions to vertically irradiate the device surface, with the 3 × 10³ cm⁻²/s flux and total radiation fluence of 1 × 10⁶ cm⁻². during which a significant increase in both drain current and gate current was observed. As the drain bias increased, devices failed in two scenarios: irreversible drain leakage and catastrophic burnout. Potential burnout mechanisms were explored through Technology Computer-Aided Design (TCAD) simulations. The study suggests that when heavy ions strike the device, electron-hole pairs are generated. Electrons move under a high transverse electric field and are quickly extracted by the drain, causing a significant rise in drain temperature, which leads to permanent damage. Additionally, charge accumulation at the drain edge induces a localized transient high electric field, exceeding the intrinsic breakdown fields of GaN and AlGaN. Although this localized high electric field lasts for only a short duration, it inevitably damages the device. The burnout locations observed under a scanning electron microscope are consistent with the proposed Single-event burnout (SEB) mechanism. This study provides important theoretical and experimental support for assessing the reliability of GaN power devices against high-energy single-event burnout in space applications.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"232 ","pages":"Article 112698"},"PeriodicalIF":2.8,"publicationDate":"2025-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143629511","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Selection of key parameters for the high yield production of 99mTc via 100Mo (p, 2n) 99mTc reaction in a cyclotron","authors":"Yue Yu,&nbsp;Zhi Chen","doi":"10.1016/j.radphyschem.2025.112695","DOIUrl":"10.1016/j.radphyschem.2025.112695","url":null,"abstract":"<div><div>The most common radioisotope in nuclear medicine imaging is ^99mTc. One of the efficient ways to alleviate the instability of the ^99mTc supply chain in recent years is to produce ^99mTc by ¹⁰⁰Mo (p,2n) in a cyclotron. The selection of key parameters in production is crucial for enhancing resource utilization and productivity. The purpose of this study is to examine how specific factors, such as the target parameters (material type, size) and irradiation parameters (proton energy, beam spot size, beam intensity, irradiation time, and cooling time) impact the yield of ^99mTc, to obtain the appropriate technological parameters for producing ^99mTc via ¹⁰⁰Mo (p,2n) ^99mTc in a cyclotron. The ^99mTc yields of enriched targets (¹⁰⁰Mo-1, ¹⁰⁰Mo-2, ¹⁰⁰MoO₃, ¹⁰⁰Mo₂C) and natural targets (Mo-nat, MoO₃-nat) under various irradiation conditions are simulated by using the Monte Carlo software FLUKA, and the obtained results are analyzed and compared. The findings indicate that for enriched targets, the optimal beam energies for maximizing ^99mTc yield is approximately 17.3 MeV, while for natural targets, it is around 13 MeV for a high RNP of ^99mTc. Enriched ¹⁰⁰Mo metal demonstrated superior production capacity, followed by molybdenum carbide to molybdenum oxide, natural molybdenum is not recommended for production but can be used as a test material. Shorter irradiation and cooling periods are preferable. A beam radius that is marginally smaller than the target radius is ideal. The target thickness should be maintained to reduce the incident energy to the reaction threshold. The optimal production parameters corresponding to the specified targets are obtained in this work, which provides valuable guidance for selecting key parameters in the preparation of ^99mTc using a proton accelerator.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"232 ","pages":"Article 112695"},"PeriodicalIF":2.8,"publicationDate":"2025-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143627983","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Prediction of chemical elements in cement using neutron activation analysis and artificial intelligence","authors":"César Marques Salgado ,&nbsp;Roos Sophia de Freitas Dam ,&nbsp;William Luna Salgado ,&nbsp;Claudio de Carvalho Conti ,&nbsp;Julio Cezar Suita","doi":"10.1016/j.radphyschem.2025.112699","DOIUrl":"10.1016/j.radphyschem.2025.112699","url":null,"abstract":"<div><div>This study presents a methodology for predicting the percentages of the key chemical elements (Calcium, Silicon, Aluminum, Iron and Oxygen) in Portland cement Class G samples. The approach integrates prompt gamma neutron activation analysis (PGNAA) and neutron activation analysis (NNA) and with artificial neural network (ANN) to enhance the characterization of these cement samples. A mathematical model was developed using the MCNP6 code to simulate both prompt and delayed gamma-ray emissions resulting from neutron activation in cement samples containing multiple elements. An ²⁴¹Am–Be neutron source was also simulated. To establish a relationship between the gamma radiation spectra from the neutron reactions and the elemental concentrations in the cement samples, a MultiLayer Perceptron (MLP) ANN was employed. This network, consisting of a hidden layer with three independent modules, was trained using the supervised error backpropagation algorithm. The results show exceptional accuracy in predicting the concentrations of the five main elements present in the cement, as well as its density, with an average relative error of less than 5 % for 97.92 % of the Validation test.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"232 ","pages":"Article 112699"},"PeriodicalIF":2.8,"publicationDate":"2025-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143627985","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Proposal of dual-gate oxide layered with HfO2: Comparative results with SiO2-RadFET","authors":"Ercan Yilmaz ,&nbsp;Goran Ristić ,&nbsp;Rasit Turan ,&nbsp;Ozan Yilmaz ,&nbsp;Umutcan Gurer ,&nbsp;Danijel Danković ,&nbsp;Erhan Budak ,&nbsp;Miloš Marjanović ,&nbsp;Sandra Veljković ,&nbsp;Alex Mutale ,&nbsp;Aysegul Kahraman","doi":"10.1016/j.radphyschem.2025.112691","DOIUrl":"10.1016/j.radphyschem.2025.112691","url":null,"abstract":"<div><div>The aim of this study is to develop pMOS dosimeters that can exhibit high performance at high radiation doses compared to traditional SiO₂-based RadFETs, for which a dual-gate oxide-layered sensor is proposed. The sensor chips, consisting of two RadFETs of identical thickness and geometry, were fabricated with sensitive region materials of 100 nm and 300 nm thick SiO₂, as well as 40 nm HfO₂/5 nm SiO₂. The threshold voltages (<span><math><mrow><msub><mi>V</mi><mrow><mi>t</mi><mi>h</mi></mrow></msub></mrow></math></span>) of the sensors were determined based on voltage values corresponding to 10 μA ve 50 μA currents. The initial <span><math><mrow><msub><mi>V</mi><mrow><mi>t</mi><mi>h</mi></mrow></msub></mrow></math></span> values at 10 μA/50 μA of the RadFETs were −2.89 ± 0.01 V/−3.84 ± 0.01 V for 100 nm SiO₂, -4.37 ± 0.02 V/-6.02 ± 0.02 for 300 nm SiO₂, and -1.04±&lt;%0.08 V/-1.507 ± 0.002 V for HfO₂/SiO₂. RadFETs were irradiated under a⁶⁰Co radioactive source within a dose range of 1–20 Gy. The sensitivities of the sensors for a cumulative dose of 20 Gy were calculated as 9.19 ± 0.21/9.81 ± 0.19 mV/Gy for 100 nm-SiO₂-RadFET, 43.72 ± 0.80/45.94 ± 0.68 mV/Gy for 100 nm-SiO₂-RadFET, and 0.83 ± 0.01/0.87 ± 0.02 mV/Gy for DGHK-RadFETs (dual-gate oxide layered with high-k), based on data obtained at 10/50 μA, respectively. No degradation was observed in any of the sensors during the studied dose range, and the DGHK-RadFETs demonstrated particularly stable behavior. Lower error rates in performance parameters, higher stability, more durable in high radiation environments, greater dose storage capability with the lowest fading values, and the ability to reach saturation at higher doses were observed in DGHK-RadFETs compared to SiO₂-RadFETs. All these superior properties compared to traditional structures have been achieved in DGHK-RadFETs with a thinner sensitive region. The DGHK-RadFET prototype is a promising candidate for potential applications in nuclear power plants, space research, high-energy physics laboratories, and defense and security applications.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"232 ","pages":"Article 112691"},"PeriodicalIF":2.8,"publicationDate":"2025-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143620397","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Sensitivity of coaxial prompt gamma-ray monitoring in heterogeneous geometries: A Monte Carlo simulation study","authors":"F. Miguéis ,&nbsp;J.V. Casaña ,&nbsp;D. García-Fernández ,&nbsp;F. Hueso-González ,&nbsp;G. Llosá ,&nbsp;A.F. Prieto ,&nbsp;P.V. Regueiro ,&nbsp;I. García Rivas ,&nbsp;A. Ros ,&nbsp;P. Crespo ,&nbsp;H. Simões","doi":"10.1016/j.radphyschem.2025.112639","DOIUrl":"10.1016/j.radphyschem.2025.112639","url":null,"abstract":"<div><div>Proton beams offer significant advantages over conventional radiotherapy due to their unique interaction with matter. Specifically, the ionization density caused by these beams is higher in a well-defined region (the Bragg peak) with a sharp decline in intensity beyond a specific depth. However, variations in proton range – often caused by changes in patient anatomy and morphology during treatment – can introduce uncertainties in dose distribution. To account for this, clinicians apply conservative margins, which limit the full potential of proton therapy. Efforts have been focused on developing proton range and dose distribution monitoring systems to reduce the need for large safety margins. These systems are based on detecting and analyzing the byproducts that result from the interaction between the proton beams and tissue. In this article, we focused specifically on a system that aims to detect photons called prompt gamma (PG) rays. We conducted Monte Carlo simulations of proton beams interacting with anthropomorphic phantoms of varying densities to simulate morphological changes. A single scintillation detector was positioned coaxially with the beam and behind the phantom to capture the emitted PG rays in each scenario. Our analysis focused on discrepancies in proton range that resulted from irradiating an anthropomorphic head phantom with varying brain tissue densities and detecting secondary particles resulting from these interactions. We observed potential correlations between gamma-ray signatures and variations in proton range and energy deposition, suggesting that this monitoring technique could be effective for real-world clinical applications.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"232 ","pages":"Article 112639"},"PeriodicalIF":2.8,"publicationDate":"2025-03-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143629512","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Neutronic analysis and safety enhancement for small modular reactors using accident tolerant fuel and cladding","authors":"Moustafa Aziz,&nbsp;Hend M. Saad","doi":"10.1016/j.radphyschem.2025.112682","DOIUrl":"10.1016/j.radphyschem.2025.112682","url":null,"abstract":"<div><div>The design and operation of small modular reactors require high levels of nuclear safety and a relatively long fuel cycle. Zirconium cladding have a significant safety risk of hydrogen generation due to strong oxidation and hydrogen release associated with temperature rises and accident conditions in light water moderated reactors. The idea of this research is based on replacement of zirconium with an alternative fuel cladding that does not react with water/steam, such as silicon carbide (SiC) and a steel alloy composed of iron, chromium and aluminum or coating zirconium cladding with a layer of chromium in addition to using another alternative of high density fuel, such as uranium carbide or nitride to increase the fuel cycle and optimize the economic return of the new materials. The results of the present model showed that using chromium-coated zirconium or FeCrAl alloy reduces the fuel cycle by 8.6 % and 34 % respectively, while silicon carbide achieves the same cycle as zirconium. The use of uranium carbide, uranium nitride and molybdenum-doped uranium fuels increases the fuel cycle by 17 %, 34 % and 25.7 % respectively.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"233 ","pages":"Article 112682"},"PeriodicalIF":2.8,"publicationDate":"2025-03-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143636363","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Highly energy gamma-radiation shielding properties of lead-free B2O3+Na2O+BaO+WO3 transparent glass system","authors":"Jamila S. Alzahrani ,&nbsp;Sultan Alomairy ,&nbsp;Z.A. Alrowaili ,&nbsp;I.O. Olarinoye ,&nbsp;Chahkrit Sriwunkum ,&nbsp;M.S. Al-Buriahi","doi":"10.1016/j.radphyschem.2025.112688","DOIUrl":"10.1016/j.radphyschem.2025.112688","url":null,"abstract":"<div><div>The traditional melt-and-quench method was adopted for the synthesis of a range of many component transparent borate glasses having the structural representation: 75B₂O₃ – 5Na₂O – (20-x)BaO – xWO₃ (where x = 0 (BNBW1), 3 (BNBW2), and 10 (BNBW3) mol%). The prepared glasses were characterized for density and gamma-ray interaction prowess using the Archimedes’ technique and the Monte Carlo simulation of narrow gamma-ray beam transmission, respectively. The glass density decreased from 2.94 gcm⁻³ (BNBW1) to 2.53 gcm⁻³ (BNBW3) when WO₃ increased from 0 to 10 mol%. The ranges of mass attenuation coefficient were 0.0265–21.3424 cm²g^-1 for BNBW1, 0.0272–26.5048 cm²g^-1 for BNBW2, and 0.0288–37.5426 cm²g^-1 for BNBW3. Based on the attenuation coefficients and other evaluated attenuation parameters, the addition of WO₃ at the expense of BaO into the glass structure improved the photon interaction cross-section of the glasses. In addition, the interaction of the glasses with photons was likened to that of elements having atomic numbers between 9 and 57, for energies below 15 MeV. At 15 keV and 15 MeV, the mass energy absorption coefficients were 19.9620 and 0.0186 cm²/g for BNBW1, 23.9787 and 0.0189 cm²/g for BNBW2, and 32.5667 and 0.0197 cm²/g for BNBW3. Considering the photon buildup factors, it was concluded that thicker WO₃-rich glasses had higher photon buildup abilities. Compared to existing glass shields, the BNBWx glasses are effective and environmentally friendly alternatives for personnel or public shielding applications in research, medicine, and other fields requiring transparent shields.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"232 ","pages":"Article 112688"},"PeriodicalIF":2.8,"publicationDate":"2025-03-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143610226","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Synthesis and characterization of Dibarium Dibismuth oxide (Ba2Bi2O6) for radiation shielding application","authors":"B.M. Chandrika ,&nbsp;L. Seenappa ,&nbsp;Holaly Chandrashekara Shastry Manjunatha ,&nbsp;R. Munirathnam ,&nbsp;K.N. Sridhar ,&nbsp;A.J. Clement Lourduraj","doi":"10.1016/j.radphyschem.2025.112660","DOIUrl":"10.1016/j.radphyschem.2025.112660","url":null,"abstract":"<div><div>This study investigates Dibarium Dibismuth Oxide (Ba<span><math><msub><mrow></mrow><mrow><mn>2</mn></mrow></msub></math></span>Bi<span><math><msub><mrow></mrow><mrow><mn>2</mn></mrow></msub></math></span>O<span><math><msub><mrow></mrow><mrow><mn>6</mn></mrow></msub></math></span>) nanoparticles as a non-toxic alternative to lead for radiation shielding. Synthesized via a green method using aloe vera extract, Ba<span><math><msub><mrow></mrow><mrow><mn>2</mn></mrow></msub></math></span>Bi<span><math><msub><mrow></mrow><mrow><mn>2</mn></mrow></msub></math></span>O<span><math><msub><mrow></mrow><mrow><mn>6</mn></mrow></msub></math></span> NPs were characterized using standard techniques. PXRD confirmed a highly crystalline cubic phase with a crystallite size of 33–34 nm, while SEM revealed an agglomerated plate-like morphology FTIR confirmed Ba–O and Bi–O bonds at 695 cm⁻¹ and 351 cm⁻¹. UV–Vis analysis showed peaks at 256 nm, 307 nm, and 399 nm, with a band gap of 3.08 eV. The shielding properties were evaluated, revealing strong gamma-ray attenuation and high neutron absorption efficiency, surpassing traditional materials like lead, concrete, and steel. Radiation shielding studies demonstrated a mass attenuation coefficient of 0.394 cm²/g at 0.276 MeV and a Tenth Value Layer (TVL) of 0.302 cm. Neutron shielding efficiency was confirmed by a scattering cross-section of 7.40 barns and an absorption cross-section of 0.034 barns. Ba<span><math><msub><mrow></mrow><mrow><mn>2</mn></mrow></msub></math></span>Bi<span><math><msub><mrow></mrow><mrow><mn>2</mn></mrow></msub></math></span>O<span><math><msub><mrow></mrow><mrow><mn>6</mn></mrow></msub></math></span> exhibits excellent shielding efficiency, making it a promising candidate for radiation shielding in medical and industrial environments, with the added benefit of reduced toxicity.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"232 ","pages":"Article 112660"},"PeriodicalIF":2.8,"publicationDate":"2025-03-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143620384","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}