Applied Radiation and Isotopes最新文献

{"title":"Neutron relative biological effectiveness factors in boron neutron capture therapy: Estimation of their values from the secondary charged particles and evaluation of weighted kerma factors for a standard tissue","authors":"M. Pedrosa-Rivera ,&nbsp;J. Praena ,&nbsp;C. Ruiz-Ruiz ,&nbsp;M.J. Ruiz-Magaña ,&nbsp;I. Porras","doi":"10.1016/j.apradiso.2025.111722","DOIUrl":"10.1016/j.apradiso.2025.111722","url":null,"abstract":"<div><div>The average Relative Biological effectiveness (RBE) factors for neutron irradiation in the context of a BNCT treatment are studied. This research considers the various interactions and secondary particles of each process and estimates the RBE based on the damage induced in tissues by all of these particles. A novel concept of estimating the biological dose by means of weighted kerma factors is introduced. These weighted kerma factors include the RBE of each energy deposition based on an RBE-LET relationship for secondary charged particles and can be directly incorporated in weighted dose calculations from Monte Carlo simulations. Furthermore, the dependence of the neutron weighting factor on neutron energy for standard soft tissue is discussed.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"219 ","pages":"Article 111722"},"PeriodicalIF":1.6,"publicationDate":"2025-02-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143429468","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":"Parameters of the neutron field at the Prizm-AN stand in the neutronic measurement laboratory","authors":"Sergey V. Bedenko ,&nbsp;Gennady N. Vlaskin ,&nbsp;Sergey D. Polozkov ,&nbsp;Nima Ghal-Eh ,&nbsp;Alexey S. Demin ,&nbsp;Dmitry G. Veretennikov ,&nbsp;Hector Rene Vega–Carrillo","doi":"10.1016/j.apradiso.2025.111729","DOIUrl":"10.1016/j.apradiso.2025.111729","url":null,"abstract":"<div><div>The present study focuses on the development of datasets characterizing the neutron field generated by the collimation channel of the Prizm-AN irradiation stand, which utilizes an internal bounded neutron (IBN) radioisotope capsule as a fast neutron source. It is aimed at supporting the prototyping of the proposed Thermal Neutron Imaging System (TENIS) diagnostics framework, currently in the feasibility assessment phase. To this end, comprehensive calculations of the radiation fields and dose characteristics associated with the Prizm-AN system—tailored to the operational specifics of the TENIS equipment—are presented. These insights will be valuable for developers in the preparatory stages leading to the creation of a demonstration version of the system. Additionally, the study explores the potential application of detection technologies for the real-time monitoring and control of parameters related to leaking deuterium-tritium (d−t) plasma.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"219 ","pages":"Article 111729"},"PeriodicalIF":1.6,"publicationDate":"2025-02-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143420797","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":"Non-photocatalytic electricity generation and thermoluminescence in natural hematite: Application in hydroelectric cell and dosimeter","authors":"Pragya Pandit ,&nbsp;Yatish R. Parauha ,&nbsp;Singarayan Michelraj ,&nbsp;S.J. Dhoble ,&nbsp;V. Ganesh ,&nbsp;Sanjeev Kimothi ,&nbsp;A.K. Singh","doi":"10.1016/j.apradiso.2025.111727","DOIUrl":"10.1016/j.apradiso.2025.111727","url":null,"abstract":"<div><div>Environmentally friendly hydroelectric power cells (HEC) and thermoluminescence dosimeters (TL) were manufactured using natural hematite. Scanning electron microscopy (SEM), transmission electron microscopy (TEM) and X-ray diffraction (XRD) studies confirmed multimodal particle size range of 30–90 nm for natural hematite. Brunauer-Emmett-Teller (BET) analysis confirmed mesoporous and nanoporous structure with average pore size of 30 nm. X-ray Photoelectron Spectroscopy, photoluminescence, ultraviolet–visible spectral analyses confirmed the presence of oxygen vacancies on the surface of hematite. Surface area of natural hematite was considerable (33.48 m²/g), band gap was small (1.7 eV), and porosity was high (31%). A square hematite hydroelectric power cell with an area of 4.84 cm² generated electricity by redox reaction and produced an open circuit voltage of 0.98 V, a stable short circuit current of 7.0 mA, and open circuit power of 6.86 mW. The TL annealing curve is recorded using a hematite sample annealed at different temperatures (100 °C–700 °C) and irradiated with a⁶⁰Co gamma source with different radiation doses (100 Gy, 15 kGy). Deconvolution analysis of the TL glow curve reveals a prominent single emission band at 178 °C and high linearity in the dose range from 2 kGy to 9 kGy for sample annealed at 400 °C. Oxygen vacancies, which function as luminous traps, are thought to be the cause of the cause of the observed behaviour. Chen's peak method and initial rise method are used to calculate trapping factors such as activation energy, frequency factor and order of kinetics.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"219 ","pages":"Article 111727"},"PeriodicalIF":1.6,"publicationDate":"2025-02-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143420902","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":"A new boron-doped gas microdosimeter for clinical Boron Neutron Capture Therapy","authors":"A. Selva ,&nbsp;A. Bianchi ,&nbsp;M. Rossignoli ,&nbsp;S. Bortolussi ,&nbsp;I. Postuma ,&nbsp;A. Pisent ,&nbsp;V. Vercesi ,&nbsp;V. Conte","doi":"10.1016/j.apradiso.2025.111721","DOIUrl":"10.1016/j.apradiso.2025.111721","url":null,"abstract":"<div><div>The Next Generation EU project ANTHEM (AdvaNced Technologies for Human-centrEd Medicine) aims at building a new accelerator-based BNCT facility in Caserta, Italy. In this framework, a new miniaturized Tissue-Equivalent Proportional Counter (mini-TEPC) with boron-doped cathode walls was designed and constructed, specifically developed to be used in BNCT clinical centres. The size of its sensitive cavity is only 1 mm to cope with the high intensity of BNCT neutron fields. The new detector was tested in reference fields where the thermal neutron component is negligible (photons, protons and fast neutrons), showing the same response as another mini-TEPC with identical design but for the boron doping. First tests were then performed at the thermal neutron column of the research reactor of the Laboratory for Applied Nuclear Energy in Pavia, Italy, with both detectors. Measured microdosimetric spectra were consistent with previous data taken at other thermal neutron sources. This paper presents the design of the new mini-TEPC and discusses the results of these first tests.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"220 ","pages":"Article 111721"},"PeriodicalIF":1.6,"publicationDate":"2025-02-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143479058","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":"Annual effective dose assessment of radon concentration in spring and ground water for the population of Devprayag region in Uttarakhand Garhwal Himalayas","authors":"Sandeep Singh ,&nbsp;O.P. Nautiyal ,&nbsp;Prakhar Singh ,&nbsp;Ankur Kumar ,&nbsp;Devender Singh","doi":"10.1016/j.apradiso.2025.111728","DOIUrl":"10.1016/j.apradiso.2025.111728","url":null,"abstract":"<div><div>Radon measurement in the Himalayan region is crucial due to the unique geological composition that may lead to elevated radon levels in water sources, posing potential health risks to the local population. This study focuses on radon concentration in drinking water collected from 13 spring water samples and 13 groundwater samples (via hand pumps) across various locations in the Devprayag region. Radon levels were assessed using the SMART RnDuo continuous radon monitor. The concentration in spring water varied between 0.7 Bq/L and 64.4 Bq/L, while groundwater levels ranged from 0.6 Bq/L to 79.5 Bq/L. Although the radon levels in the samples fell within the safe limits set by the World Health Organization (WHO), the estimated annual effective dose from radon ingestion and inhalation surpassed the WHO's safety threshold of 100 μSv/year in several areas. These results highlight the necessity of ongoing radon monitoring in the region to reduce long-term health risks and guide safety standards for drinking water.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"219 ","pages":"Article 111728"},"PeriodicalIF":1.6,"publicationDate":"2025-02-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143420901","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":"Boron neutron capture therapy (BNCT) for left axillary lymph node metastasis of recurrent breast cancer","authors":"Takuya Fujimoto ,&nbsp;Yoko Maekawa ,&nbsp;Shinichi Hori ,&nbsp;Atsushi Oguro ,&nbsp;Atsushi Hori ,&nbsp;Ikuo Fujita ,&nbsp;Yoshinori Sakurai ,&nbsp;Hiroki Tanaka ,&nbsp;Tatsuya Ito ,&nbsp;Shunsuke Yahiro ,&nbsp;Toshiko Sakuma ,&nbsp;Minoru Suzuki","doi":"10.1016/j.apradiso.2025.111715","DOIUrl":"10.1016/j.apradiso.2025.111715","url":null,"abstract":"<div><div>Here described for the first time is the efficacy of <em>p</em>-boronophenylalanine (BPA)-based BNCT in the clinical treatment of metastatic breast cancer. The patient was diagnosed with left axillary lymph node metastasis from breast cancer with comorbidity of neuropathy. Although several treatment strategies for suppressing the progression of the cancer were unavailing, BPA-based BNCT impeded the progression. This clinical case suggests the applicability of this new method of treatment to not only metastatic but also primary breast cancer.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"219 ","pages":"Article 111715"},"PeriodicalIF":1.6,"publicationDate":"2025-02-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143429469","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":"Evaluation of 18F-FDG absorbed dose ratios in percent in adult and pediatric reference phantoms using DoseCalcs Monte Carlo platform","authors":"Tarik El Ghalbzouri ,&nbsp;Tarek El Bardouni ,&nbsp;Jaafar El Bakkali ,&nbsp;Hicham Satti ,&nbsp;Abdelhamid Nouayti ,&nbsp;Iman Berriban ,&nbsp;Randa Yerrou ,&nbsp;Assia Arectout ,&nbsp;Maryam Hadouachi","doi":"10.1016/j.apradiso.2025.111705","DOIUrl":"10.1016/j.apradiso.2025.111705","url":null,"abstract":"<div><div>This study investigates the field of radiation exposure in nuclear medicine, which might have implications for exposure to ionizing radiation in pediatric cases. To demonstrate the difference in radiosensitivity between younger patients and adults and to highlight the need for individualized radiation protection procedures when investigating medical imaging and therapy, this study examines the absorbed dose ratios in percent (ADR%) for ¹⁸F-FDG. This parameter is an important indicator, illustrating the percentage of radiation dose absorbed by specific organs/tissues concerning the emitted radiation from different body regions.</div><div>The methodology involves calculating ADR% in twelve voxel-based models for adults, children, and newborns, as referenced by International Commission on Radiological Protection (ICRP) Publications 110 and 143. The simulations used the ¹⁸F positron spectrum from ICRP Publication 107 and Livermore models. These simulations were performed using the DoseCalcs Monte Carlo platform.</div><div>We have calculated the S-values and ADR% using the DoseCalcs simulations of the ¹⁸F positrons and provided a comprehensive dataset of ADR% results. This dataset evaluates the impact of anatomical variation on absorbed dose in target regions. It consists of 141 target regions and 8 different source regions.</div><div>Significant differences in radiosensitivity were observed in ADR% values among various source–target combinations for each age and sex group. The self-irradiation ADR% reaches up to 95%, while the cross-irradiation ADR% varies, ranging approximately from 0.1% to 12%, depending on the mass of the target organ, the distance between it and the source organ, and the chemical composition of these organs. Also, the variations observed across different age and sex phantoms highlight the importance of personalized internal dosimetry, especially for pediatric cases with heightened radiosensitivity. Healthcare practitioners can use the dataset of ADR% values as the first stage to illustrate variability and optimize nuclear medicine imaging with ¹⁸F-FDG while reducing radiation risks.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"218 ","pages":"Article 111705"},"PeriodicalIF":1.6,"publicationDate":"2025-02-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143369802","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":"Predicting (n,3n) nuclear reaction cross-sections using XGBoost and Leave-One-Out Cross-Validation","authors":"Yiğit Ali Üncü ,&nbsp;Taner Danışman ,&nbsp;Hasan Özdoğan","doi":"10.1016/j.apradiso.2025.111714","DOIUrl":"10.1016/j.apradiso.2025.111714","url":null,"abstract":"<div><div>Accurately predicting nuclear reaction cross-sections is crucial for advancing various fields, including nuclear medicine, energy production, and materials science. This study aims to address the challenges associated with predicting (n <span><math><mrow><mo>,</mo><mn>3</mn><mi>n</mi></mrow></math></span>) nuclear reaction cross-sections by developing a robust machine learning (ML) model based on the XGBoost (eXtreme Gradient Boosting) algorithm. By leveraging a comprehensive dataset of experimental cross-sectional values, the study demonstrates the potential of ML to overcome limitations in existing theoretical and empirical approaches. LOOCV (Leave-One-Out Cross-Validation) was employed for feature selection and hyperparameter optimization to ensure the reliability of the model. The dataset was meticulously prepared by normalizing values and addressing missing data, which contributed to robust model training. XGBoost's ability to handle complex, non-linear relationships enabled it to provide accurate predictions that closely align with experimental data, as evaluated through key metrics such as Mean Squared Error (MSE) and Mean Absolute Error (MAE), and reduced Chi-Square. To validate the model's accuracy, its predictions were compared with calculations from the TALYS 1.95 nuclear reaction code, TENDL and phenological model. The results highlight the efficacy of XGBoost in improving prediction accuracy, offering a novel approach to solving complex challenges in nuclear data analysis.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"219 ","pages":"Article 111714"},"PeriodicalIF":1.6,"publicationDate":"2025-02-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143395767","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":"A methodology study for sodium quantification in bone and soft tissue based on in vivo neutron activation analysis using a two-compartment model","authors":"Song Yue ,&nbsp;Mychaela Coyne ,&nbsp;Connie M. Weaver ,&nbsp;Cheryl AM. Anderson ,&nbsp;Linda H. Nie","doi":"10.1016/j.apradiso.2025.111712","DOIUrl":"10.1016/j.apradiso.2025.111712","url":null,"abstract":"<div><div>Sodium (Na) is an essential mineral for human health regulation and in excess has been associated with many diseases. Its storage has been found in rapidly (soft tissue) and slowly exchangeable pools (bone) in human body. However, Na concentration and metabolism information in human bone and soft tissue cannot be determined using conventional biological urine and blood samples. The aim of this study was to apply a transportable neutron generator based <em>in vivo</em> neutron activation analysis technique to separately quantify Na in bone and soft tissue. Two pigs were fed with low and high Na diet to investigate the effects of dietary Na intake on Na storage and metabolism. The emitted gamma rays from Na activated by thermal neutron capture reaction in pig leg were collected using a high purity germanium detector. A biokinetic model based on internal dosimetry theorem was developed to obtain the bone and soft tissue Na concentration, as well as half-life of Na retention in the two compartments. The results show that soft tissue Na concentration was significantly higher in the pig that received a high Na diet <span><math><mrow><mo>(</mo><mrow><mn>1057.08</mn><mspace></mspace><mo>±</mo><mn>43.62</mn><mspace></mspace><mi>p</mi><mi>p</mi><mi>m</mi><mspace></mspace><mi>v</mi><mi>s</mi><mspace></mspace><mn>704.46</mn><mspace></mspace><mo>±</mo><mn>45.60</mn><mspace></mspace><mi>p</mi><mi>p</mi><mi>m</mi><mo>,</mo><mi>p</mi><mo>=</mo><mn>0.007</mn></mrow><mo>)</mo></mrow></math></span>. In contrast, the bone sodium concentration was not affected by dietary intervention <span><math><mrow><mo>(</mo><mrow><mn>856.45</mn><mo>±</mo><mn>78.48</mn><mspace></mspace><mi>p</mi><mi>p</mi><mi>m</mi><mspace></mspace><mi>v</mi><mi>s</mi><mspace></mspace><mn>803.30</mn><mo>±</mo><mn>48.98</mn><mspace></mspace><mi>p</mi><mi>p</mi><mi>m</mi><mo>,</mo><mi>p</mi><mo>=</mo><mn>0.107</mn></mrow><mo>)</mo></mrow></math></span>. The developed methodology is capable of effectively measuring altered Na levels resulting from dietary Na consumption, with great potential in exploring the association between Na intake and health outcomes such as hypertension.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"218 ","pages":"Article 111712"},"PeriodicalIF":1.6,"publicationDate":"2025-02-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143369801","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":"Produced radioactive isotopes, ambient dose equivalent in TrueBeam room with flattening filter (FF) and Flattening Filter Free (FFF) modes: Monte Carlo simulation","authors":"Soai Dang Quoc ,&nbsp;Toshioh Fujibuchi ,&nbsp;Hiroyuki Arakawa ,&nbsp;Keisuke Hamada ,&nbsp;DongHee Han","doi":"10.1016/j.apradiso.2025.111704","DOIUrl":"10.1016/j.apradiso.2025.111704","url":null,"abstract":"<div><h3>Background</h3><div>High-energy linear accelerators used in radiotherapy produce unexpected neutrons that can activate materials in the treatment room.</div></div><div><h3>Materials and methods</h3><div>The research group used PHITS code to simulate TrueBeam Linac head with 10 MV photons. Then, PHITS codes connected Dchain code to calculate the variation of the induced radioactivity, the ambient dose equivalent during TrueBeam radiation 4 Gy with dose rate 400 MU (Monitor Unit)/minute in FF mode, 24 Gy with dose rate 2400 MU/minute in FFF mode, and cooling time (14 min).</div></div><div><h3>Results</h3><div>One minute of beam-on TrueBeam with 10 MV photon energy produced six mainly produced nuclides (183 mW, 24mNa, 185 mW, 28Al, 24mNa, and 187W). FFF mode had more activity of the produced isotopes than those in FF mode (1.60 × 1014 Bq compared with 1.57 × 1014 Bq—corresponding to ∼1.71% higher). The differences in the activity of isotopes and ambient dose between FF and FFF mode were mostly less than a few percent; however, considering that the MU per beam current is six times higher in the FFF mode than in the FF mode, the induced activities per MU can be reduced by roughly six times when using the FFF mode instead of the FF mode.</div></div><div><h3>Conclusion</h3><div>The isotope activities of the produced isotopes in the FF and FFF modes are essentially equivalent when normalized per beam current.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"219 ","pages":"Article 111704"},"PeriodicalIF":1.6,"publicationDate":"2025-02-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143420905","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}