Radiation Physics and Chemistry最新文献

{"title":"ZnO-enhanced borotellurite glasses: A comparative investigation of radiation shielding via experiment and simulation approaches","authors":"M.I. Sayyed ,&nbsp;Chaitali V. More ,&nbsp;K.A. Mahmoud ,&nbsp;M.U. Khandaker ,&nbsp;S.E. Lam","doi":"10.1016/j.radphyschem.2025.112812","DOIUrl":"10.1016/j.radphyschem.2025.112812","url":null,"abstract":"<div><div>A lead-free glass series was fabricated according to the chemical formula of (40-x) B₂O₃+20 TeO₂ + (20 + x + y) ZnO + (20 - y) CaO, where x = 0, 2, 4, and 6 mol% and y = 0, 3, 6, and 9 mol%. The role of substitution of ZnO for B₂O₃ and CaO compounds on the physical and radiation shielding properties of the prepared series was investigated. The density of prepared glasses was examined according to the Archimedes method. The increase in the ZnO across the concentration of 20–35 mol% increases the density of prepared glasses throughout 3.945–4.241 g/cm³. Furthermore, the radiation shielding capacities of the prepared glasses were examined through the experimental measurements using an NaI (Tl) detector and some radioactive sources, including Na-22, Ba-133, Co-60, and Cs-137. The data obtained from the experimental measurements was confirmed using Monte Carlo simulation and XCOM that depend on two various nuclear databases. The experiment, simulation, and XCOM calculations confirmed that the increase in the ZnO concentration throughout 20–35 mol% increases the linear attenuation coefficient throughout 0.352–0.367 cm⁻¹ (at 0.511 MeV), 0.297–0.318 cm⁻¹ (at 0.662 MeV), and 0.210–0.224 cm⁻¹ (at 1.275 MeV), respectively. This increase in the linear attenuation coefficient improves the shielding capacity of prepared glasses, which reach 31.45 % (for the TeZn20 glass), 32.22 % (for the TeZn25 glass), 32.87 % (for the TeZn30 glass), and 33.65 % (for the TeZn35 glass) of the shielding capacity of pure lead at 0.662 MeV.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"234 ","pages":"Article 112812"},"PeriodicalIF":2.8,"publicationDate":"2025-04-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143824375","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":"Evaluating impact of detector arrangement and position resolution effect on a fast neutron-based range verification system for proton therapy","authors":"Lena M. Setterdahl ,&nbsp;William R.B. Lionheart ,&nbsp;Danny Lathouwers ,&nbsp;Hunter N. Ratliff ,&nbsp;Kyrre Skjerdal ,&nbsp;Ilker Meric","doi":"10.1016/j.radphyschem.2025.112793","DOIUrl":"10.1016/j.radphyschem.2025.112793","url":null,"abstract":"<div><div>Real-time proton therapy range verification is a technique that can potentially reduce uncertainty margins around the treatment volume and enable prompt corrections during treatment, making proton therapy a safer cancer treatment modality. Imaging secondary particles resulting from proton-beam nuclear interactions with tissue serves as a means of range verification. The <u>NOV</u>O project recently (2023) presented a <u>co</u>mpact <u>d</u>etector <u>a</u>rray (NOVCoDA) range verification system designed to image secondary prompt-gamma rays (PGs) and fast neutrons (FNs). The position resolution and arrangement of detector elements within the NOVCoDA influences the reconstructed particle distributions and in turn the system’s range shift detection capabilities. Through Monte-Carlo simulations, we investigate the effects of four different detector element arrangements and the utilization of optically segmented scintillator volumes within detector elements, for improved position resolution, on NOVCoDA’s range shift determination capability for proton therapy. We limit our study to the detection of FNs produced by an 85-MeV proton beam interacting within a homogeneous water phantom. Results indicate that a parallel array with detector elements oriented perpendicular to the proton beam axis and line-of-sight direction yields the highest double FN scattering efficiency, on order of <span><math><mrow><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mo>−</mo><mn>6</mn></mrow></msup></mrow></math></span> per proton. Furthermore, optically segmented detector elements resulted in improved minimum detectable range shift, reducing required proton intensity by 30%–60% to discern a 1 mm shift.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"234 ","pages":"Article 112793"},"PeriodicalIF":2.8,"publicationDate":"2025-04-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143826286","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":"Development of metal/metal oxide enriched polymer composites for radiation shielding of low-energy photons","authors":"Linas Kudrevičius,&nbsp;Jurgita Laurikaitienė,&nbsp;Gustė Laurikaitytė,&nbsp;Diana Adlienė","doi":"10.1016/j.radphyschem.2025.112807","DOIUrl":"10.1016/j.radphyschem.2025.112807","url":null,"abstract":"<div><div>Increasing applications of ionizing radiation in medical and industrial processes indicate a growing demand for effective radiation shielding materials that are non-toxic and recyclable. Specific radiation–resistant, lead-free, lightweight shielding materials are required to protect personnel and patients against medical radiation since lead toxicity poses significant environmental and health risks and problems with lead utilization.</div><div>In this study 1.0 mm thick PVA polymer composite films containing 50 V/V% of different fillers (Tungsten (VI) oxide (WO₃), Tantalum (V) oxide (Ta₂O₅), Tin (Sn), and Bismuth (Bi)) were fabricated and tested for radiation attenuation performance using Multimeter Barracuda with R100B detector (RTI Electronics AB, Sweden). Irradiation of films with low energy photons was performed in X-ray therapy unit GULMAY D3225 (UK). Irradiation of samples in Leksell Gamma Knife® Icon™ (Elekta, Sweden), and linear accelerator Varian Trilogy™ (California, USA) providing MeV range photons was performed additionally for the assessment of correlations between experimental data and modeling results in the broad energy range.</div><div>Photon attenuation and shielding efficiency of fabricated experimental samples: single-filled (PVA-WO₃, PVA-Ta₂O₅, PVA-Sn, and PVA-Bi) and dual-filled (PVA-Bi-WO₃, PVA-Ta₂O₅-WO₃, PVA-Sn-WO₃, PVA-Bi-Ta₂O₅, PVA-Sn-Ta₂O₅, PVA-Bi-Sn) polymer composites were assessed using experimental measurements data. Experimental results were verified against simulation data obtained using open-access software Phy-X/PSD and compared with the data corresponding to 0.25 and 0.5 mmPb lead equivalent as reference of required medical radiation shielding equipment.</div><div>It was shown that single filler PVA-Bi and dual-filler with WO₃–Bi composites exhibited the highest radiation shielding efficiency in the low energy range and at certain energies were performing better than 0.25 mm Pb equivalency, indicating composites‘ potential to be explored in lead-free, lightweight, low-toxicity medical radiation shielding equipment.</div><div>Obtained results suggest that PVA-metal/metal oxide composites, especially those with bismuth and tungsten, are promising candidates for environmentally sustainable radiation shielding.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"234 ","pages":"Article 112807"},"PeriodicalIF":2.8,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143820239","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":"Alpha particle induced reactions on 153Eu as possible routes for 152Tb and 155Tb production","authors":"E.S. Kormazeva ,&nbsp;A.K. Ilyuschenko ,&nbsp;V.I. Novikov ,&nbsp;A.N. Moiseeva ,&nbsp;I.A. Khomenko ,&nbsp;D.V. Shpuntov ,&nbsp;N.V. Aksenov ,&nbsp;M.G. Voronuk ,&nbsp;R.A. Aliev","doi":"10.1016/j.radphyschem.2025.112809","DOIUrl":"10.1016/j.radphyschem.2025.112809","url":null,"abstract":"<div><div>Cross-sections for the ¹⁵³Eu(α,x)^151-156Tb,¹⁵³Gd reactions were measured by using the stacked foil technique within alpha-particle energy range of 60.0 to 19.8 MeV. All of the data were obtained for the first time. Experimental data were compared with theoretical values from the TENDL-2023 database. Thick target yields of activation products were calculated. The reactions ¹⁵³Eu(α,2n)¹⁵⁵Tb and ¹⁵³Eu(α,5n) ^152g Tb were compared with other ¹⁵⁵Tb and ¹⁵²Tb production routes. The reaction allows producing up to 2.17 MBq/(μA·h) of ¹⁵⁵Tb with the minimum possible ¹⁵⁶Tb content of 2.1 % within the energy range of 30.2 to 27.5 MeV.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"234 ","pages":"Article 112809"},"PeriodicalIF":2.8,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143826460","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":"Effectiveness of radiation protectors to reduce occupational radiation dose of medical staff when performing radioligand therapy with 177Lu","authors":"Saya Inoue ,&nbsp;Takashi Asahara ,&nbsp;Daisuke Hasegawa ,&nbsp;Keisuke Yoshitomi ,&nbsp;Sota Goto ,&nbsp;Hiroaki Hayashi ,&nbsp;Toshihiro Iguchi","doi":"10.1016/j.radphyschem.2025.112808","DOIUrl":"10.1016/j.radphyschem.2025.112808","url":null,"abstract":"<div><div>Recently, the radioactive nuclide ¹⁷⁷Lu has been applied to clinical radioligand therapy. The β-rays emitted from ¹⁷⁷Lu are used for radiation therapy. Although this nuclide also emits γ-rays that can be used to image radioactive isotope distributions, it causes an exposure dose risk to medical staff who operate the radioligand therapy. This study investigates the radiation-shielding effectiveness of lead protectors during ¹⁷⁷Lu radioligand therapy, based on γ-ray spectra. Both simulations and experimental measurements were conducted to obtain spectra of γ-rays penetrating lead shields. The corresponding air kerma values were calculated from the obtained γ-ray spectra, and the dose reduction factor (<em>DRF</em>) was evaluated. The study found that a lead thickness of 2.0 mm achieves a <em>DRF</em> of 90 %. However, ¹⁷⁷Lu also contains several low-energy γ-ray components (e.g., 57 keV and 113 keV), suggesting that thinner lead could be effective for shielding them. We then found that even thicknesses in the range of 0.07 mm–0.75 mm, which have been used as actual protectors, were effective. More specifically, a <em>DRF</em> of 50–55 % was obtained with a protector having a lead-equivalent thickness of 0.50 mm. In conclusion, we propose the use of lead protectors for occupational dose reduction when performing radioligand therapy with ¹⁷⁷Lu.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"235 ","pages":"Article 112808"},"PeriodicalIF":2.8,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143835077","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":"Characterization of intraoral digital detectors: Comparative analysis in spatial and reciprocal domains across two different beam qualities","authors":"S.I. Allen ,&nbsp;P.C. Watanabe ,&nbsp;M.E. Poletti","doi":"10.1016/j.radphyschem.2025.112805","DOIUrl":"10.1016/j.radphyschem.2025.112805","url":null,"abstract":"<div><div>The transition from analog to digital systems in dental radiography is primarily driven by the technological advancements offered by digital detectors. This study evaluates the performance of three commercially available intraoral digital detectors—Eagle Digital Sensor, RVG 5200 Carestream Dental, and Schick Fona CDRelite—under two beam qualities: the standard RQA 5 quality (70 kVp, 21 mm Al) and a new proposed quality in this work (70 kVp, 12 mm Al) more applicable to dental practices. Detector air kerma (DAK) levels ranged from 10 to 500 μGy. The assessment included metrics in both spatial and reciprocal domains, measuring response linearity, noise spatial invariance, noise component analysis, Modulation Transfer Function (MTF), Normalized Noise Power Spectrum (NNPS), and Detective Quantum Efficiency (DQE). All detectors displayed linearity across beam qualities, though the fitting coefficients varied. Quantum noise was predominant across almost the entire DAK range studied, and MTF showed minimal variation across beam qualities. The spatial frequency for MTF 10 % was 11 lp/mm for the RVG 5200 and 10.5 lp/mm for the Eagle, while the Schick CDRelite reached this point at 5.5 lp/mm. In all systems, an expected decrease in NNPS values with increasing DAK was observed. The newly proposed beam quality slightly favored DQE values at comparable DAK levels. For the DQE at 5 lp/mm, the Eagle detector increased from 0.056 to 0.065, the RVG 5200 from 0.164 to 0.170, and the Schick CDRelite from 0.026 to 0.033. The optimal exposure conditions for all studied detectors were determined through DQE analysis.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"235 ","pages":"Article 112805"},"PeriodicalIF":2.8,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143828240","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":"Assessment of suspended particulate matter in school environments in the city of Rio de Janeiro (Brazil) using X-ray fluorescence","authors":"Julien L. Pereira ,&nbsp;Marcelino J. dos Anjos ,&nbsp;Joaquin T. Assis ,&nbsp;Roberta G. Leitão ,&nbsp;Catarine Canellas ,&nbsp;Fábio T.S. Tsuyama ,&nbsp;Hamilton S.G. Filho","doi":"10.1016/j.radphyschem.2025.112804","DOIUrl":"10.1016/j.radphyschem.2025.112804","url":null,"abstract":"","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"235 ","pages":"Article 112804"},"PeriodicalIF":2.8,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143834973","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":"Assessment of various polymer materials for enhanced radiation protection in X-ray imaging modalities: A comprehensive Monte Carlo simulation study","authors":"Sofiene Mansouri","doi":"10.1016/j.radphyschem.2025.112806","DOIUrl":"10.1016/j.radphyschem.2025.112806","url":null,"abstract":"<div><div>Radiation protection is essential in X-ray imaging modalities to mitigate the potential health risks associated with exposure to ionizing radiation. This study, for the first time, focuses on evaluating the effects of 28 different pragmatic polymers used in polymer-based nanocomposites for radiation shielding in X-ray imaging. Using a Monte Carlo (MC) simulation-based approach, the shielding performance was assessed through key parameters such as the linear attenuation coefficient (μ), mass attenuation coefficient (μm), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), and effective atomic number (Z_eff), across photon energies ranging from 80 keV to 120 keV. Specifically, the study aims to evaluate the X-ray shielding properties of 28 different polymers using the Geant4 MC code. Among the polymers analyzed, PVDC demonstrated superior X-ray attenuation characteristics at 60, 80, 100, and 120 kVp. In terms of performance comparison, the polymers can be ranked as follows: PVDC &gt; CPVC &gt; PTFCE &gt; PVC for μ, and PVDC &gt; CPVC &gt; PVC &gt; PTFCE for μ_m. Notably, the polymers NR and PPy exhibited lower μ and μm values relative to the other polymers analyzed. Notably, the polymers NR and PPy exhibited the lowest μ and μm values among those studied. Furthermore, unlike the trends observed for μ and μm, the MFP, HVL, and TVL values for all polymers increased with rising incident photon energy.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"234 ","pages":"Article 112806"},"PeriodicalIF":2.8,"publicationDate":"2025-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143820241","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":"Development of the low-dose radiotherapy machine for Osteoarthritis based on Monte Carlo simulation","authors":"Hyojun Park ,&nbsp;Minjae Choi ,&nbsp;Ju Yeol Shin ,&nbsp;Jung-In Kim ,&nbsp;Chang Heon Choi","doi":"10.1016/j.radphyschem.2025.112803","DOIUrl":"10.1016/j.radphyschem.2025.112803","url":null,"abstract":"<div><h3>Purpose</h3><div>This study investigated the design of a machine for low-dose radiotherapy of knee osteoarthritis (OA), focusing on its maintenance efficiency and treatment effectiveness.</div></div><div><h3>Methods</h3><div>Monte Carlo simulations were performed to compare dose distributions according to machine geometries. The machine comprises a radioisotope source, tungsten collimator, and housing. It delivers a uniform dose to the inflammatory lesions by rotating the source around the knee. The source geometry was optimized in terms of diameter and height. Thicknesses of the collimator and housing were determined by evaluating the gamma-ray transmission rate through tungstens of various thicknesses. Subsequently, the dose distributions in the cylindrical water phantom were calculated according to the source rotation and translation intervals.</div></div><div><h3>Results</h3><div>⁶⁰Co was defined as the most appropriate for knee OA treatment among the nominates, considering its gamma emission properties. The diameter and height of the source were determined as 27 and 1 mm, respectively. The thickness of the collimator and housing was decided to be in a range of 3.5–4 cm, which is expected to limit the gamma ray transmission and surface dose less to than 5 % and 2 mSv/hr, respectively. The dose distributions were uniform within 10 % variation when the source rotation interval was less than 60° and the source translation interval was 10 mm.</div></div><div><h3>Conclusion</h3><div>The results of this study proposed feasibility of effective knee OA treatment with the dedicated machine. This study is expected to contribute to the effective treatment of OA with fewer side effects compared to the conventional treatment methods.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"234 ","pages":"Article 112803"},"PeriodicalIF":2.8,"publicationDate":"2025-04-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143820240","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":"Computational evaluation of a two-source neutron irradiator for low-flux neutron activation applications","authors":"Jayms S. Sagana ,&nbsp;Emerald G. Ramos ,&nbsp;Cheri Anne M. Dingle ,&nbsp;Alvie Asuncion-Astronomo","doi":"10.1016/j.radphyschem.2025.112791","DOIUrl":"10.1016/j.radphyschem.2025.112791","url":null,"abstract":"<div><div><em>The viability of a neutron irradiator facility (NIF) with two legacy plutonium-239 beryllium (</em>^<em>239</em><em>PuBe) neutron sources that are housed polyethylene moderator blocks was evaluated for neutron activation analysis (NAA) applications using Particle and Heavy Ion Transport Code System (PHITS) simulation</em>. <em>Calculations show that the NIF design with</em> 6 cm <em>thick irradiator volume provides the optimal thermal neutron flux of</em> <span><math><mrow><mn>6.57</mn><mo>×</mo><msup><mn>10</mn><mn>3</mn></msup></mrow></math></span> <em>n/cm</em>^<em>2</em><em>s, which corresponds to 60</em> <em>% of the total flux. The study also identified 20 optimal elements for low-flux NAA, of which, Eu-151 was found to have the highest sensitivity (</em><span><math><mrow><mn>6.28</mn><mo>×</mo><msup><mn>10</mn><mn>2</mn></msup></mrow></math></span> per <em>unit flux and volume), while I-127 has the lowest (</em><span><math><mrow><mn>1.09</mn><mo>×</mo><msup><mn>10</mn><mrow><mo>−</mo><mn>2</mn></mrow></msup></mrow></math></span> per <em>unit neutron flux and volume). Finally, the induced activity of the selected nuclides after 24-h irradiation was calculated</em>. <em>Among the 20 optimal nuclides, Au-198 has the highest saturation activity of</em> <span><math><mrow><mn>2.32</mn><mo>×</mo><msup><mn>10</mn><mn>4</mn></msup></mrow></math></span> <em>Bq while the lowest saturation activity is obtained by Er-171 with</em> <span><math><mrow><mn>1.84</mn><mo>×</mo><msup><mn>10</mn><mn>2</mn></msup></mrow></math></span> <em>Bq. This study serves as a foundation for guiding the practical application of NAA using the NIF being developed by Philippine Nuclear Research Insitute (PNRI) and highlighting areas for further validation and refinement.</em></div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"235 ","pages":"Article 112791"},"PeriodicalIF":2.8,"publicationDate":"2025-04-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143850763","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}