Applied Radiation and Isotopes最新文献

{"title":"Correlational study of naturally occurring radionuclides with radon and thoron exhalation rates in Pithoragarh district of central Himalayas","authors":"O.P. Nautiyal ,&nbsp;Manish Joshi ,&nbsp;Taufiq Ahamad ,&nbsp;Anita Rawat ,&nbsp;Prakhar Singh ,&nbsp;Sandeep Singh","doi":"10.1016/j.apradiso.2025.111882","DOIUrl":"10.1016/j.apradiso.2025.111882","url":null,"abstract":"<div><div>This study examines radon and thoron emissions from soil samples in Pithoragarh, Uttarakhand, and their correlation with naturally occurring radionuclides (²²⁶Ra, ²³²Th, and ⁴⁰K) in locally used construction materials. Radiological hazard parameters, including radium equivalent activity (Ra_eq), hazard indices (H_in, H_ex), absorbed gamma dose rates (Dout), and annual effective dose equivalents (AEDE_out), were analyzed. Average activity concentrations were 66 ± 11 Bq/kg (²²⁶Ra), 43 ± 8 Bq/kg (²³²Th), and 602 ± 77 Bq/kg (⁴⁰K), showing variability attributed to geological heterogeneity. Radon and thoron exhalation rates highlighted localized hotspots, with Raeq averaging 173 ± 81 Bq/kg and hazard indices mostly below safety limits but with significant deviations. Correlation analysis revealed strong relationships, such as between ²²⁶Ra and ²³²Th, suggesting shared origins, while other parameters reflected diverse environmental influences. These findings emphasize the importance of continuous monitoring, targeted mitigation, and regulatory strategies to manage potential radiological risks and provide a baseline for future regional studies.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"223 ","pages":"Article 111882"},"PeriodicalIF":1.6,"publicationDate":"2025-04-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143912942","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":"Thermoluminescence characteristics of Zn2SiO4/SiO2:Mg nanophosphor under X-ray irradiation","authors":"Mozhgan Naderi ,&nbsp;Mostafa Zahedifar ,&nbsp;Ehsan Sadeghi","doi":"10.1016/j.apradiso.2025.111877","DOIUrl":"10.1016/j.apradiso.2025.111877","url":null,"abstract":"<div><div>In thermoluminescence (TL) dosimetry, the choice of materials and their preparation method are crucial in achieving an efficient dosimeter. Zinc silicate materials have attracted a lot of attention due to their promising luminescence efficiency. However, the luminescence properties of these materials when doped with magnesium have received less attention. In this research, the TL properties of the synthesized <strong>Zn_2-xSiO₄/SiO₂</strong>:Mg_x (ZSMg-x) nanophosphors have been studied for the first time. X-ray diffraction (XRD), scanning electron microscopy (SEM), and energy dispersive X-ray spectroscopy (EDS) analyses were performed to study the crystal structure and morphology of the nanophosphors. The photoluminescence (PL) emission spectrum shows emission bands peaking at wavelengths of 295, 428, 485, 521, and 736 nm. TL glow curves of the fabricated ZSMg-0.5 nanophosphors were analyzed using a computerized glow curve deconvolution program based on the general order Kinetics. Magnesium doping of the Zn₂SiO₄/SiO₂ nanophosphor was found to increase luminescence intensity, resulting in high sensitivity to X-rays. This study showed the effectiveness of ZSMg-0.5 nanophosphor for dosimetry of X-ray radiation.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111877"},"PeriodicalIF":1.6,"publicationDate":"2025-04-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143895838","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":"Simulation and analysis of the medical radioisotope 177Lu production based on a high-intensity DT neutron generator","authors":"Chao Zhou ,&nbsp;Lu Liu ,&nbsp;Jiale Mao ,&nbsp;Ying Qu ,&nbsp;Baoqian Li ,&nbsp;Yiguo Li ,&nbsp;Sanjun He ,&nbsp;Xiaodong Wang ,&nbsp;Bo Zheng ,&nbsp;Song Feng","doi":"10.1016/j.apradiso.2025.111880","DOIUrl":"10.1016/j.apradiso.2025.111880","url":null,"abstract":"<div><div>¹⁷⁷Lu is one of the medical radioisotopes with wide application prospects. To explore the ¹⁷⁷Lu production besides using reactors, a concept of utilizing high-enriched cylindrical ¹⁷⁶Lu based on a high-intensity DT neutron generator via the direct neutron capture reaction has been proposed. The production of ¹⁷⁷Lu in a¹⁷⁶Lu₂O₃ solid shell target has been simulated considering layers of neutron multiplier, moderator, and reflector around itself. Materials used as multipliers, moderators, and reflectors have been investigated and analyzed for neutronics optimization. The combinations and thicknesses of different layers have been calculated using the response surface methodology (RSM), and the three layers were found almost independently for the ¹⁷⁷Lu production. Both the activity and the specific activity of produced ¹⁷⁷Lu were improved significantly using the RSM. According to the calculations, about 13.5 Ci ¹⁷⁷Lu can be produced after 40 days of irradiation with a stable neutron yield of 5 × 10¹¹ n/s.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111880"},"PeriodicalIF":1.6,"publicationDate":"2025-04-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143899908","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 radon concentration in laboratories of the civil engineering course of Federal Technological University of Parana and the contribution of construction materials to dose limits","authors":"Lidiane Fernanda Jochem ,&nbsp;Cézar Augusto Casagrande ,&nbsp;Roman Fediuk ,&nbsp;Caroline Venâncio ,&nbsp;Sergei Anatolyevich Paschuk ,&nbsp;Janine Nicolosi Corrêa","doi":"10.1016/j.apradiso.2025.111879","DOIUrl":"10.1016/j.apradiso.2025.111879","url":null,"abstract":"<div><div>Radon is a radioactive, carcinogenic gas present in nearly the entire Earth's crust, which tends to accumulate indoors. The dose of radon received depends on both its indoor concentration and the duration of exposure. Building materials, which contain elements from the Earth's crust, also contain naturally occurring radioactive materials, typically in small amounts. However, materials of magmatic origin, such as granite, tend to be significant potential sources of radon. To assess the safety of environments where construction materials are handled, it is important to evaluate the physical risks associated with ionizing radiation (such as radon), both in the materials and in the environment. In this study, radon concentrations were measured in indoor environments and construction materials used in civil engineering laboratories (coded as 1, 2, 11, 12, and 16) at the Federal Technological University of Paraná, Ecoville Campus in Curitiba. For this, 50 passive diffusion chambers equipped with CR-39 detectors were placed in 5 laboratories, with 10 detectors per laboratory. Additionally, construction materials frequently used in these laboratories were analyzed using an active detector, AlphaGuard, which measures alpha activity concentrations through an ionization chamber. The results indicated that the construction materials handled in the laboratories have little impact on the indoor radon concentration. The majority of the radon activity concentrations were mainly influenced by the soil beneath the laboratory. Of the diffusion chambers, 14 % showed concentrations between 200 and 400 Bq/m³, a level of concern, and 2 % of the chambers showed concentrations above 400 Bq/m³, indicating the need for monitoring and mitigation actions. However, given that the limits established are conservative and considering the exposure time of users, it was concluded that the indoor environments analyzed do not pose a physical risk from ionizing radiation.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111879"},"PeriodicalIF":1.6,"publicationDate":"2025-04-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143890657","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":"On the spectrum and maximum energy of the first forbidden unique beta decay of 107Pd","authors":"Karsten Kossert ,&nbsp;Marina Faure ,&nbsp;Daniel Deptuck","doi":"10.1016/j.apradiso.2025.111863","DOIUrl":"10.1016/j.apradiso.2025.111863","url":null,"abstract":"<div><div>The activity concentration of a ¹⁰⁷Pd solution was determined by means of liquid scintillation (LS) counting techniques. Initial results revealed discrepancies and gave a first hint that the maximum beta energy could be larger than the currently recommended value (34.0 ± 2.3) keV stated in the Atomic Mass Evaluation AME2020. The finding was confirmed by means of a comprehensive analysis of LS spectra from which the maximum beta energy was determined to be (37.4 ± 1.7) keV.</div><div>Additionally, experimental data obtained by means of a cryogenic micro-calorimeter, which includes a neutron-transmutation-doped (NTD) germanium thermistor, were analyzed. The experiment took place about 30 years ago at Princeton University. The new analysis yields a maximum beta energy of (37.46 ± 0.19) keV. The beta spectrum shape is compared to advanced theoretical computations and good agreement is obtained in a range from about 10 keV to the endpoint. With the new data, the activity concentration was determined with a relative uncertainty of about 1 %, which is an important milestone towards a new ¹⁰⁷Pd half-life determination.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111863"},"PeriodicalIF":1.6,"publicationDate":"2025-04-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143901953","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":"Study of positron emission from 36Cl","authors":"S. Nissim ,&nbsp;O. Aviv ,&nbsp;M. Brandis ,&nbsp;L. Weissman ,&nbsp;Z. Yungrais ,&nbsp;E. Gilad","doi":"10.1016/j.apradiso.2025.111870","DOIUrl":"10.1016/j.apradiso.2025.111870","url":null,"abstract":"<div><div>The absolute intensity of the weak branch for positron emission from ³⁶Cl was evaluated using a β-γ coincidence technique. A liquid sample with known activity of ³⁶Cl was embedded in scintillation cocktail and measured in a 4παβ(LS)-γ(HPGe) system that comprises a Liquid Scintillator (LS) detector and a High-Purity Germanium (HPGe) detector. The LS detector includes a photo-reflector assembly that holds the liquid sample and ensures high efficiency for β particles. The recorded timestamp and energy for β and γ events provided a highly effective mechanism for filtering out events that originated from outside the volume of the measured sample, thereby allowing a clear observation of the 511-keV γ-rays associated with positron emission from ³⁶Cl. Hence, the positron branch intensity can be evaluated directly in a practically background-free environment. The system was calibrated for detecting β particles and γ rays at relevant energies using radioactive sources having identical geometry as employed in the ³⁶Cl sample measurement. The absolute intensity of the positron emission was found to be (1.62 ± 0.15) × 10⁻⁵, in agreement with the values appearing in the literature.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111870"},"PeriodicalIF":1.6,"publicationDate":"2025-04-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143908311","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":"Development of a real-time boron imaging method for BNCT using CdTe-DSD at the JRR-3","authors":"I-Huan Chiu ,&nbsp;Takahito Osawa ,&nbsp;Takehiro Sumita ,&nbsp;Mizuha Ikeda ,&nbsp;Kazuhiko Ninomiya ,&nbsp;Shin’ichiro Takeda ,&nbsp;Takahiro Minami ,&nbsp;Tadayuki Takahashi ,&nbsp;Shin Watanabe","doi":"10.1016/j.apradiso.2025.111845","DOIUrl":"10.1016/j.apradiso.2025.111845","url":null,"abstract":"<div><div>Boron neutron capture therapy (BNCT) is a neutron-based cancer treatment requiring a real-time ¹⁰B dose monitor to optimize effectiveness. We report using of the cadmium telluride double-sided strip detector (CdTe-DSD), distinguished by its high-energy resolution in full width at half maximum (FWHM) of 7.3 keV at 511 keV and a spatial resolution of <span><math><mrow><mn>250</mn><mspace></mspace><mi>μ</mi><mi>m</mi></mrow></math></span> for accurate boron imaging. Employing the CdTe-DSD with a pinhole collimator, our experiment at Japan Research Reactor No. 3 (JRR-3) evaluated the ¹⁰B distribution in a solid sample containing a ¹⁰B concentration of 0.3 mg during neutron exposure. Although measuring the ¹⁰B signal is significantly affected by the background from the <span><math><mi>γ</mi></math></span>-rays of ¹¹³Cd, we successfully obtained a circular projection image with a diameter of 11.5 mm, revealing the precise location of ¹⁰B, with a counting rate of 0.115 cps and SNR of approximately 25.7%. The results reveal the CdTe-DSD’s capability to enhance BNCT by providing detailed insights into the ¹⁰B distribution within the sample with high fidelity.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111845"},"PeriodicalIF":1.6,"publicationDate":"2025-04-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143878905","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":"Commissioning of the H2 neutron irradiation facility at MARIA research reactor, as a part of MARIA Neutron Laboratory","authors":"Edyta Michaś-Majewska ,&nbsp;Katarzyna Tymińska ,&nbsp;Maciej Maciak ,&nbsp;Michał Kuć ,&nbsp;Maciej Wiliński ,&nbsp;Jarosław Grzyb ,&nbsp;Aleksandr Bancer ,&nbsp;Elżbieta Jaworska ,&nbsp;Monika Kopińska ,&nbsp;Martyna Celejowska ,&nbsp;Martyna Araszkiewicz ,&nbsp;Agnieszka Dróżdż ,&nbsp;Kamila Maliszewska-Olejniczak ,&nbsp;Szymon Domański ,&nbsp;Marcin Pietrzak ,&nbsp;Łukasz Krzemiński ,&nbsp;Grzegorz Wojtania ,&nbsp;Krystian Król ,&nbsp;Gabriel Raj ,&nbsp;Piotr Mazerewicz ,&nbsp;Michał A. Gryziński","doi":"10.1016/j.apradiso.2025.111876","DOIUrl":"10.1016/j.apradiso.2025.111876","url":null,"abstract":"<div><div>A new neutron beam infrastructure at the MARIA reactor located at the National Centre for Nuclear Research (NCBJ) has recently become installed. Its primary objective is to generate a neutron beam for Boron Neutron Capture Therapy (BNCT). Additionally, it will be utilized for materials research, radiobiology studies, and the development of neutron dosimetry methods.</div><div>The construction of the facility has been divided into three main stages related to the assembly of the following parts of the stand: the intermediate channel, the beam shutter, and the converter. Currently, the stage two is coming to an end. The assembly of the beam shutter is finalized and the post-assembly tests are finished. Once the facility licensing is completed, the new beamline will be made available for research purposes.</div><div>The shutter is the crucial safety device of the infrastructure. In its closed position, it ensures safe access to the irradiation room during reactor operation at full power. In its open position, it serves as a Beam Shaping Assembly (BSA), collimating the neutron beam. Also, its construction allows for the mounting of a system of filters and moderators to shape the beam spectrum. The completion of the second stage enables the delivery of the thermal neutron beam reaching the flux of 1x10⁹ neutrons/cm²/s. The conclusion of stage three will increase the available range of the neutron energies up to epithermal and fast region.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111876"},"PeriodicalIF":1.6,"publicationDate":"2025-04-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143895836","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":"Enhancement on the charge collection property of the 3D positive ion detector","authors":"R. Hemapriya ,&nbsp;C.S. Sureka ,&nbsp;P. Venkatraman ,&nbsp;P.V. Paramaguru ,&nbsp;Alok J. Verma ,&nbsp;Amol Bhagwat ,&nbsp;R.K. Jeevanram","doi":"10.1016/j.apradiso.2025.111878","DOIUrl":"10.1016/j.apradiso.2025.111878","url":null,"abstract":"<div><div>This study focuses on enhancing the charge collection efficiency of 3D positive ion detector, which plays a vital role in radiation biology, dosimetry, protection, and measurement. Conventionally, highly resistive glass and fluorine doped tin oxide/gold-coated ceramic glass cathodes have been employed, yielding charge collections in the picocoulomb (pC) to nanocoulomb (nC) range. However, the introduction of metal oxide/metal-coated cathodes has significantly improved charge collection, increasing electron counts from 10⁸ to 10¹⁰. Building upon this progress, our research explores the use of oxygen-free high conductivity (OFHC) copper cathode, resulting in a substantial enhancement of charge collection to the microcoulomb (μC) range and electron counts reaching 10¹³. This study also examines the relationship between electron mobility, drift velocity, and charge collection under varying pressure conditions. The results reveal a linear increase in electron mobility with pressure, while drift velocity remains stable, dominated by the applied electric field. The stability of drift velocity and consistent charge collection performance across pressure variations highlight the detector's reliability, offering valuable insights into electron transport behavior in particle detection systems.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111878"},"PeriodicalIF":1.6,"publicationDate":"2025-04-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143886156","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":"Development of LiF-based ceramics for shielding neutron fluxes in boron neutron capture therapy and their performance predictions","authors":"Naoyuki Kitamura ,&nbsp;Takeshi Ikeda ,&nbsp;Tetsuyuki Nakamura ,&nbsp;Hiroaki Kumada","doi":"10.1016/j.apradiso.2025.111871","DOIUrl":"10.1016/j.apradiso.2025.111871","url":null,"abstract":"<div><div>In boron neutron capture therapy (BNCT) facilities, neutron beam-shielding materials are crucial for preventing radiation exposure and adverse events caused by beams leaking around the neutron source and gaps around the irradiation port. Owing to their stability in severe thermal, radiative, and mechanical environments, lithium-fluoride-based ceramics have been developed to shield neutron fluxes in BNCT facilities. Bulk ceramics as large as 15 cm × 15 cm × 5 cm have been successfully developed in ternary LiF-MgF₂-CaF₂ systems. Boron- or gadolinium-added quaternary LiF-MgF₂-CaF₂ systems have also been developed. These ceramics demonstrate high bulk densities of over 95 %. The particle and heavy ion transport code system (PHITS) simulation indicated that some of these ceramic tiles provided better shielding performance than commercially available 50 wt%LiF-polyethylene composite materials. We propose a variable-shaped jig that utilises the developed LiF-based ceramic beads with polyethylene beads to shield the thermal and fast neutron beams, which might leak between the irradiation port and the patient. The shielding performance of some jig models was evaluated by PHITS simulations using the initial free beam profile of the linear-accelerator-type iBNCT001 at Tsukuba. When using both the 100 wt% LiF ceramic and the 70 wt% LiF-based ternary ceramic beads containing small amounts of boron, the expected shielding performance is approximately 1/20 for thermal neutrons and approximately 1/10 for fast neutrons against the initial free beam, while the γ-ray dose rate increases by about two times. Ceramic tiles and jigs are expected to be applicable to various places in BNCT facilities.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"222 ","pages":"Article 111871"},"PeriodicalIF":1.6,"publicationDate":"2025-04-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143895837","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}