Nuclear Engineering and Technology最新文献

{"title":"Exploration on high-energy and high-dose rate X-ray detection with Bridgman-grown CsPbBr3 single crystal","authors":"Ahreum Park ,&nbsp;Beomjun Park ,&nbsp;Jichul Seo ,&nbsp;Jangwon Byun ,&nbsp;Sung-Jun Park ,&nbsp;Sung-Pil Yoon ,&nbsp;Juyoung Ko ,&nbsp;Jeongho Kim ,&nbsp;Wonho Lee ,&nbsp;Man-Jong Lee","doi":"10.1016/j.net.2025.103799","DOIUrl":"10.1016/j.net.2025.103799","url":null,"abstract":"<div><div>Perovskite-based semiconductors have emerged as promising candidates for next-generation radiation detectors due to their balanced carrier transport, high effective atomic number, and tunable electronic properties. In this study, we investigate the feasibility of Bridgman-grown CsPbBr₃ (CPB) single crystals for X-ray detection, particularly under high-energy and high-dose-rate conditions. Two types of planar devices, Au/CPB/Au and Ga/CPB/Au, were fabricated and evaluated. The asymmetric Ga/CPB/Au configuration, incorporating a low work function metal, exhibited significantly suppressed dark current and enhanced stability, attributed to Schottky barrier formation. Electrical characterization revealed comparable trap densities between both devices, confirming that performance differences resulted from electrode-induced interface effects rather than fabrication-causing effect such as thermal damage during deposition. The Ga/CPB/Au device demonstrated superior performance across a wide range of X-ray conditions from low dose-rate to diagnostic exposures, with high signal-to-noise ratio (SNR), high sensitivity, and low limit-of-detection (LoD). Notably, the device maintained stable photocurrent and high sensitivity even under harsh X-ray exposures (6 MeV and &gt;1 Gy), validating its robustness and applicability for high energy X-ray dosimeter. This study demonstrates that CPB devices incorporating low work function electrodes are viable candidates for reliable and sensitive X-ray detection across a broad energy and dose range.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103799"},"PeriodicalIF":2.6,"publicationDate":"2025-07-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144661986","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":"Probabilistic Model Chain Methodology for evaluating radiological consequences of accidents in High-Temperature Gas-Cooled Reactor","authors":"Piotr Kopka ,&nbsp;Michał Spirzewski ,&nbsp;Piotr Darnowski","doi":"10.1016/j.net.2025.103779","DOIUrl":"10.1016/j.net.2025.103779","url":null,"abstract":"<div><div>Dose consequence analysis models are pivotal in Nuclear Safety Analysis, particularly for assessing radiological consequences following nuclear accidents. As many new reactor designs, including High-Temperature Gas-Cooled Reactors (HTGRs), are expected to be located closer to populated areas and propose significantly smaller Emergency Planning Zones (EPZs), accurate consequence analysis becomes increasingly vital. This paper presents a novel Probabilistic Model Chain Methodology (PMCM), beginning with core state estimation using SERPENT2, followed by source term characterization through the Idaho National Laboratory Model, and culminating in the generation of weather scenarios based on empirical models. These data are produced probabilistically, leading to simulations of radionuclide transport and dose assessment using the JRODOS system. The methodology is illustrated using the HTGR TeResa <span><math><mrow><mn>40</mn><mi>M</mi><msub><mrow><mi>W</mi></mrow><mrow><mi>t</mi><mi>h</mi></mrow></msub></mrow></math></span> design and a Depressurized Loss of Forced Cooling accident scenario for the reactor’s location at the National Centre for Nuclear Research in Poland. The resulting dose spatial results are compared with dose limits, as well as dose values across distances from the site, highlighting the highest dose maps. This is achieved through integrated uncertainty across several models, enhancing potential modularity and applicability of the methodology to other reactor types and accident scenarios.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103779"},"PeriodicalIF":2.6,"publicationDate":"2025-07-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144656184","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":"Design of 200 MHz CW He2+ APF-DTLs for 211At production","authors":"LiangZhou Yao ,&nbsp;CanYu Wang ,&nbsp;ZhengMao Zhang ,&nbsp;Wei Ma ,&nbsp;Liping Zou ,&nbsp;Zhen Yang ,&nbsp;Jinghe Yang ,&nbsp;Liang Lu","doi":"10.1016/j.net.2025.103795","DOIUrl":"10.1016/j.net.2025.103795","url":null,"abstract":"<div><div>Targeted Alpha-particle Therapy (TAT) has become a significant therapeutic way for cancer, as it can reduce relapsed refractory cancer. ²¹¹At is one of the most promising alpha-emitting radionuclides. To boost its production and facilitate applications, we designed 200 MHz drift tube linacs (DTL) operating in continuous wave (CW) mode, which accelerates a 3 mA He²⁺ beam from 6.4 MeV to 28 MeV for ²¹¹At production. Using the alternative phase focusing (APF) beam dynamics to get a compact structure. To ensure high acceleration efficiency, we limit the total cavity length to 2.5 m. The cavity design maintains the gap voltage distribution in close alignment with the beam dynamics, with a maximum deviation of under 1 %. The design achieves 99.98 % beam transmission efficiency. The cavity employs an interdigital H-mode (IH) structure, achieving an unloaded quality factor of 13,635 and a Kilpatrick (Kp) factor of 1.59 in DTL-1, while DTL-2 reaches 14,894 and 1.53 respectively. To ensure stable CW operation, the cooling system has been designed to effectively manage the thermal load during operation, ensuring the system remains within safe limits. This paper presents the detailed design and results of the nuclear medicine linac, including beam dynamics, RF design, and cooling system analysis.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103795"},"PeriodicalIF":2.6,"publicationDate":"2025-07-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144656182","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":"Design of a 200 MHz CW He2+ RFQ for 211At production","authors":"Z.M. Zhang ,&nbsp;X.W. Liu ,&nbsp;L.Z. Yao ,&nbsp;Z.Y. Zhang ,&nbsp;L.P. Zou ,&nbsp;Z. Yang ,&nbsp;C. Zhang ,&nbsp;W. Ma ,&nbsp;L. Lu","doi":"10.1016/j.net.2025.103794","DOIUrl":"10.1016/j.net.2025.103794","url":null,"abstract":"<div><div>Short-lived alpha-emitting radiopharmaceuticals are promising for targeted cancer therapy, providing high linear energy transfer and localized cytotoxic effects while minimizing damage to healthy tissues. To ensure a stable and high-purity supply of these isotopes, a dedicated radiopharmaceutical injector is required, integrating advanced accelerator technology for efficient isotope production. This study presents the design and analysis of a 200 MHz CW He²⁺ RFQ accelerator as a key component of such an injector for ²¹¹At production, ensuring high transmission efficiency (99.5 %) and minimal emittance growth. A four-vane structure with optimized cooling channels was adopted, achieving a stable temperature profile. The implementation of Pi-mode stabilizing loops (PISLs) improved mode separation (7.9 MHz), reducing dipole mode interference. The undercut design ensured a longitudinal field flatness deviation of less than 3 %. Sixty tuners were designed, providing a tuning range of [-1.5 MHz, +2 MHz], sufficient to compensate for frequency shifts caused by machining and assembly errors. Multi-physics analysis showed that thermal deformation of the cavity resulted in a frequency shift of +20 kHz, while the maximum cavity stress was 38.2 MPa, well below the copper material limit of 70 MPa. These results confirm the feasibility of using CW RFQs for high-current alpha radiopharmaceutical production.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103794"},"PeriodicalIF":2.6,"publicationDate":"2025-07-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144656183","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":"Nuclide inventory analysis and fission product monitoring for nuclear safeguards in molten chloride fast reactors","authors":"Saehyun Choi ,&nbsp;Jeongwon Seo ,&nbsp;Wonseok Yang ,&nbsp;Jihun Kim ,&nbsp;Taehoon Park ,&nbsp;Sujeong Lee ,&nbsp;Sungyeol Choi","doi":"10.1016/j.net.2025.103793","DOIUrl":"10.1016/j.net.2025.103793","url":null,"abstract":"<div><div>Fission product analysis offers a powerful means to real-time monitoring of fissile material evolution and sudden alterations in Molten Chloride Fast Reactors, where conventional safeguards techniques are challenged by continuously circulating fuel. In this study, time-dependent depletion simulations were employed using SCALE 6.3.1 with TRITON-Shift and ORIGEN to quantify fission product under varied operational scenarios, including once-through and breed-and-burn modes. The results demonstrate that Nd and Sm in the fuel salt serve as delayed indicators of shifting ²³⁵U/²³⁹Pu ratios, while Kr in the off-gas stream rapidly reflects changes in fissile isotope composition. Additionally, Xe proves effective for tracking overall reactor power despite its weaker dependence on specific isotopes. These findings establish that targeted fission product monitoring can capture both gradual compositional evolutions and rapid perturbations such as plutonium diversion, thereby offering enhanced operational awareness and safeguards confidence in advanced molten salt reactors.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103793"},"PeriodicalIF":2.6,"publicationDate":"2025-07-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144634526","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":"Effect analysis of power density distribution & temperature dependent thermo-physical properties along MSR fuel channels applying neutronic and thermal hydraulic approach","authors":"Mohammad Khan,&nbsp;Nayeem bin Zahid,&nbsp;Saad Islam,&nbsp;Ali Mahdi","doi":"10.1016/j.net.2025.103791","DOIUrl":"10.1016/j.net.2025.103791","url":null,"abstract":"<div><div>One of the potential Generation IV reactors is MSR for its several advantages including actinides burning, production of hydrogen, and fissile breeding. The distinct feature that sets the MSR apart from other reactors is the mixing of fissile material with molten halide salt, playing the vital role of both the heat transferring coolant and heat generating fuel. This dual-function fluid circulates through a graphite moderator matrix, forming a complex system that poses significant computational challenges, particularly for coupled neutronic-thermal hydraulic simulations. To address these challenges, simplified assumptions—such as sinusoidal power distributions and temperature-independent material properties—are often employed. In this study, a single MSR fuel channel is analysed under varying power density distribution assumptions, with and without incorporating the temperature dependence of material properties, using a decoupled neutronic and thermal-hydraulic modelling approach. To determine the power distribution via neutron flux profiles, a probabilistic approach was employed using the Monte Carlo particle transport code <em>OpenMC</em>. For the thermal-hydraulic analysis, the Reynolds-Averaged Navier–Stokes (RANS) equations with the <em>k–ε</em> turbulence model were utilized and implemented using the state-of-the-art commercial computational fluid dynamics software, <em>ANSYS Fluent</em>. The results were compared to analytical solutions available in the literature, as well as to results obtained through fully coupled neutronic-thermal hydraulic simulations. The study revealed that assuming uniform heat generation in the MSR channel significantly affects the temperature profile along the channel. It also indicated that axial variations in heat generation are the most influential factor affecting the temperature distribution. Additionally, other flow properties such as velocity profiles and Nusselt number distributions were examined.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103791"},"PeriodicalIF":2.6,"publicationDate":"2025-07-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144656180","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":"Numerical simulation of oxygen mass transfer dynamics in liquid lead-bismuth eutectic alloy in solid-phase active control system","authors":"Yuqi Zhu,&nbsp;Hao Wu,&nbsp;Fenglei Niu,&nbsp;Yang Liu","doi":"10.1016/j.net.2025.103790","DOIUrl":"10.1016/j.net.2025.103790","url":null,"abstract":"<div><div>In lead-bismuth eutectic (LBE) cooled nuclear reactors, the solid-phase oxygen control technique enables rapid adjustment of oxygen concentration in liquid LBE by controlling the dissolution of solid lead oxide, thereby significantly reducing the excessive slag formation. A numerical particle-resolved mass transfer model was developed to investigate the oxygen concentration dynamics within an LBE solid-phase oxygen control loop. The results indicate that the Sherwood number increases greatly with the Peclet number and the predictions show good agreement with the previous correlations. The turbulent diffusion of oxygen in LBE is much greater than its laminar diffusion. At varying temperature, due to the combined effect of dissolution and diffusion, the oxygen mass transfer coefficient reaches the peak at approximately 500 °C. In the mass exchanger with binary particle packing, the dissolution rate of the bed with 8 mm and 10 mm spheres, in which the pressure drop is lower, is comparable to that of 6 mm spheres and higher than other sizes. In the cases involving the prolate and oblate ellipsoids, with higher mass transfer area, dissolution rate is higher at lower aspect ratios. The turbulence contribution of the bed with oblates is greater and the performance of the solid-phase oxygen control is improved.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103790"},"PeriodicalIF":2.6,"publicationDate":"2025-07-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144656185","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 and structural characterization of crystalline alkali strontium borates","authors":"Nabil El-Faramawy ,&nbsp;E.M. Abou Hussein ,&nbsp;Mohamed El-Kinawy","doi":"10.1016/j.net.2025.103782","DOIUrl":"10.1016/j.net.2025.103782","url":null,"abstract":"<div><div>A strontium borate glass system was prepared by the melt-quenching method and the corresponding glass ceramic derivatives were produced by applying heat treatment (HT) on glass samples at 600 °C for different periods. FTIR analysis was carried out for the prepared and thermally treated samples. The specific volume (Vs) displayed a slight increase with HT while the oxygen packing density (OPD) revealed a slight decrease, correlating with the nature of host former, inserted modifier and rate of thermal process. The thermoluminescence (TL) properties, namely, dose response linearity, reusability, minimum detectable dose, and thermal fading, of the samples treated for 8 h were investigated. The kinetic parameters of the TL glow peaks were determined using computational and experimental methods. The dependence of the displayed glow curves/peaks on the TL measurement heating rate was investigated and quantified.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103782"},"PeriodicalIF":2.6,"publicationDate":"2025-07-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144570992","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":"Atmospheric neutron inducing single event effects on AI chips manufacturing with 8 nm FinFET","authors":"Yonghong Li ,&nbsp;Jianan Tong ,&nbsp;Weitao Yang ,&nbsp;Zhiliang Hu ,&nbsp;Lihua Mo ,&nbsp;Tianjiao Liang ,&nbsp;Chaohui He ,&nbsp;Jinghui Lan","doi":"10.1016/j.net.2025.103785","DOIUrl":"10.1016/j.net.2025.103785","url":null,"abstract":"<div><div><strong><em>Abstract--</em></strong>With the rapid advancement of artificial intelligence (AI) chips in diverse applications, single event effects (SEE) caused by high energy particles in ambient environment have emerged as a critical concern. Among these, static random access memory (SRAM) cells integrated into AI chips exhibit heightened sensitivity to SEEs due to their high density bit cell architectures. This study investigates the SEE susceptibility of SRAM cells fabricated using an 8 nm FinFET technology integrated into the AI chip, leveraging the atmospheric neutron irradiation spectrometer (ANIS) at the China spallation neutron source (CSNS) as the irradiation platform. During the irradiation, comprehensive SEE tests were conducted under varying operational conditions, with results systematically compared to those from 14 nm to 28 nm process nodes. The findings reveal that as semiconductor technology scales from 14 nm to 8 nm, the single event upset (SEU) cross section per bit decreases while the non-single bit upset proportion goes up. During the experiments, multiple cell upsets (MCUs) were detected with a maximum cluster size of seven. While the 8 nm FinFET architecture enhances intrinsic resistance to SEUs by narrowing the charge collection region, the reduced technology node may paradoxically exacerbate MCU susceptibility, leading to a higher effective MCU ratio. Consequently, the SEE exhibits a non-monotonic relationship with process scaling, highlighting the need for advanced error mitigation strategies in advanced AI chips.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103785"},"PeriodicalIF":2.6,"publicationDate":"2025-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144634148","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":"InChaP: A simple software for computation of charged particle interaction parameters","authors":"Ali Çiçi ,&nbsp;Berk Morkoç ,&nbsp;Hüseyin Dağ ,&nbsp;Levent Aydınbakar ,&nbsp;M.I. Sayyed ,&nbsp;Mehmet Büyükyıldız","doi":"10.1016/j.net.2025.103789","DOIUrl":"10.1016/j.net.2025.103789","url":null,"abstract":"<div><div>A new, user-friendly software called <strong>I</strong>nteraction of <strong>C</strong>harged <strong>P</strong>article has been developed to simulate ion interactions across various applications. Designed with robust physical formulations and computational techniques using Python packages, InChaP operates within a broad energy range of 0.01–1000 MeV. InChaP calculates mass stopping power, stopping cross-section, relative stopping power, effective atomic number, and electron density for any chemical compound or composite using a logarithmic interpolation procedure across a wide range of ion energies. It also generates parameters for a specific ion of energy within the working range, and users can obtain the results in common spreadsheet formats. The software is freely available to all researchers. Good agreements were obtained in the effective atomic number between <strong>I</strong>n<strong>C</strong>ha<strong>P</strong> and some possible results from literature. These agreements were <span><math><mrow><mi>d</mi><mi>i</mi><mi>f</mi><mi>f</mi><mo>.</mo><mo>%</mo><mo>≤</mo><mn>11.44</mn></mrow></math></span> and <span><math><mrow><mi>d</mi><mi>i</mi><mi>f</mi><mi>f</mi><mo>.</mo><mo>%</mo><mo>≤</mo><mn>1.94</mn></mrow></math></span> for He ion interaction and for electron interaction in calculation of effective atomic number for spleen at 1 MeV.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103789"},"PeriodicalIF":2.6,"publicationDate":"2025-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144634149","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}