Nuclear Engineering and Technology最新文献

{"title":"Assessment of pressurizer dynamic performance for nuclear hybrid energy system modelling: Comparison between equilibrium and 1D non-equilibrium approaches","authors":"Guido Carlo Masotti ,&nbsp;Antonio Cammi ,&nbsp;Stefano Lorenzi","doi":"10.1016/j.net.2025.103761","DOIUrl":"10.1016/j.net.2025.103761","url":null,"abstract":"<div><div>The importance of the pressurizer for the control and safe operation of pressurized water reactors translates into the need to develop accurate dynamic models to simulate the response of this component in various scenarios. This study compares two modelling paradigms, classified into equilibrium and non-equilibrium approaches, implemented in the Modelica language. Specifically, the non-equilibrium version adopts a 1D modelling approach with a user-defined number of control volumes. The objective is to assess the prediction accuracy by comparing simulation results with experimental data. The analysis identifies the models’ applicability limits as well a relevant phenomena affecting the outcomes. Additionally, the investigation is extended to a Small Modular Reactor (SMR) pressurizer architecture, exploring the impact of its features and different control strategies to mitigate pressure fluctuations. The latter analysis represents an initial step towards the development of a SMR-driven integrated energy system simulator, which will encompass the most suitable pressurizer model. The outcomes of this work indicate that the equilibrium model is able to capture overall system dynamics despite its strong simplifying assumptions. As for the SMR pressurizer, the distinctive geometry affects the system’s response to the considered transients, resulting in the requirement of designing control strategies tailored to its characteristics.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103761"},"PeriodicalIF":2.6,"publicationDate":"2025-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144557623","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":"Dissolution of low burn-up (33 GWd·t−1) spent nuclear fuel at alkaline and hyperalkaline pH","authors":"Jakub Kokinda ,&nbsp;Daniel Serrano-Purroy ,&nbsp;Albert Martínez-Torrents ,&nbsp;Joan de Pablo ,&nbsp;Frederic Clarens ,&nbsp;Alejandro Kinbaum ,&nbsp;Sonia García-Gómez ,&nbsp;Javier Giménez","doi":"10.1016/j.net.2025.103783","DOIUrl":"10.1016/j.net.2025.103783","url":null,"abstract":"<div><div>The release of some key radionuclides during the dissolution of a low burnup spent nuclear fuel (33 GWd·t⁻¹) was measured in two leaching experiments under oxidizing conditions and in alkaline to hyperalkaline pH. The results were compared to the ones obtained in a previous experiment with the same fuel but with a higher burnup (63 GWd·t⁻¹). Uranium, plutonium and neptunium had a faster release at low burnup, caesium a slower release and the release of molybdenum and technetium did not almost depend on burnup. The experiment at pH = 13.5 showed a possible precipitation of uranium, plutonium and neptunium and much higher molybdenum and technetium release than at alkaline pH, pointing to a higher dissolution of the ε-particles at high pH.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103783"},"PeriodicalIF":2.6,"publicationDate":"2025-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144656181","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":"Analytical solutions for thermal-hydraulic-mechanical-chemical modeling of smectite illitization in bentonite buffers for nuclear waste disposal","authors":"Lotanna Ohazuruike ,&nbsp;Kyung Jae Lee ,&nbsp;Jin-Seop Kim","doi":"10.1016/j.net.2025.103778","DOIUrl":"10.1016/j.net.2025.103778","url":null,"abstract":"<div><div>Nuclear waste is stored in canisters within underground repositories, surrounded by a buffer material like bentonite, which ensures isolation from the host rock due to its low hydraulic conductivity and high swelling potential. However, at high potassium ion concentrations and temperatures above 100 °C, bentonite transforms into illite, a low-swelling mineral. Many studies have addressed this phenomenon in different bentonites using numerical simulators. None has analytically modeled the phenomena of illitization and how changes in reactive surface area during drying cycles could influence the process. Furthermore, no analytical solutions address the impact of illitization and clay swelling on the transport of heat and chemical species such as K⁺ in diffusion-dominant or advection-dominant systems. This study develops analytical models to predict temperature, water saturation, and potassium ion concentration evolution in the bentonite buffer and their effects on the smectite-to-illite transformation process. The developed models are the first to incorporate the effects of illitization and clay swelling on the heat and species transport in an engineered barrier system under various boundary conditions. The models are based on mass and energy balance principles, validated against existing temperature solutions, experimental and numerical simulation illitization data. Preliminary validation shows that incorporating the effect of declining reactive surface area improves illitization predictions by accounting for the reduction of interlayer smectite regions, which slows the illitization process. The models are then used to simulate multi-physics behavior in a nuclear repository, and their results are compared to numerical simulations conducted using TOUGHREACT-FLAC. Porosity reduction due to both mineral transformation and swelling affects not only fluid transport but also thermal dissipation in the buffer. Under limited K⁺ availability, illitization becomes self-limiting, highlighting the potential buffering capacity of smectite-rich host rocks. When continuous K⁺ supply is modeled (e.g., via feldspar dissolution), illitization proceeds for extended durations, indicating a need to evaluate mineral assemblages and groundwater chemistry during repository design. The findings highlight the models' effectiveness in predicting the evolution of temperature, potassium ion concentration, water saturation, and smectite content in the bentonite buffer, demonstrating their utility in understanding and predicting behavior in nuclear waste repositories.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103778"},"PeriodicalIF":2.6,"publicationDate":"2025-07-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144572377","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":"Robust dosimetric evaluation of FLASH proton beams using plane-parallel ionization chambers and EBT-XD films for pre-clinical studies","authors":"Heesoon Sheen ,&nbsp;Sunghwan Ahn ,&nbsp;Chanil Jeon ,&nbsp;Youngyih Han ,&nbsp;Changhoon Choi ,&nbsp;Hee Chul Park ,&nbsp;Daizo Amano ,&nbsp;Nagaaki Kamiguchi ,&nbsp;Sungkoo Cho","doi":"10.1016/j.net.2025.103749","DOIUrl":"10.1016/j.net.2025.103749","url":null,"abstract":"<div><div>This study established a robust methodology to evaluate the beam quality and dosimetric characteristics of FLASH-Proton beams. Dose plans were formulated for delivery of 3, 6, and 9 Gy at rates of 40 Gy/s and 70 Gy/s. The dosimetric evaluation employed two plane-parallel ionization chambers (ICs)—PPC-05 and Advanced Markus chamber—alongside EBT-XD film. Key parameters such as recombination and polarity effects of the ICs were measured, and the determined dose was quantified at predefined depths. Beam characteristics were further investigated using the EBT-XD film to corroborate IC findings. Polarity correction factors calculated for PPC-05 were 0.997 and 0.996 at 40 Gy/s and 70 Gy/s, respectively, with corresponding values for the Advanced Markus chamber of 1.0 and 0.999. The mean dose rates, derived from log files, were 52.3 Gy/s and 72.8 Gy/s for nominal rates of 40 Gy/s and 70 Gy/s, respectively. Depth dose profiles from the EBT-XD were analyzed at seven points and compared with measurements from PPC-05, revealing relative dose differences within ±5 % upon application of linear energy transfer correction. The established methodology is validated for routine clinical quality assurance.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103749"},"PeriodicalIF":2.6,"publicationDate":"2025-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144518891","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":"Radiological hazards and environmental impact of natural radioactivity and heavy metals in by-product and topsoil around a Malaysian coal-fired thermal power plant","authors":"Eli Syafiqah Aziman ,&nbsp;Mohd-Syukri Yahya ,&nbsp;Shamsul Amri Sulaiman ,&nbsp;Muhammad Asyraf Redzuan ,&nbsp;Kamalia Rasyidah Sufyan ,&nbsp;Rogemah Ramli ,&nbsp;Mohd Idzat Idris ,&nbsp;Aznan Fazli Ismail ,&nbsp;Alif Imran Mohd Shuhaimi ,&nbsp;Rully Hidayatullah","doi":"10.1016/j.net.2025.103770","DOIUrl":"10.1016/j.net.2025.103770","url":null,"abstract":"<div><div>This study assessed radiological and heavy metal (HM) contamination in coal, bottom ash (BA), fly ash (FA), and topsoil within a 5 km radius of a coal-fired power plant (CFPP) in Malaysia. The ²²⁶Ra(²³⁸U), ²³²Th, and ⁴⁰K levels in coal, BA, and FA were within regulatory limits, though the FA sample's average ⁴⁰K concentration (632.4 Bq/kg) exceeded typical Malaysian soil levels. Some topsoil samples outside the plant showed ²³²Th and ⁴⁰K levels higher than usual but remained compliant. Most HM levels in coal were below Dutch/Malaysian standards, except for Cd. BA samples had Cr and Cd above target levels by factors of 1 and 4. FA showed As, Cu, Zn, and Cd concentrations 2–10 times higher than targets. Topsoil exhibited As levels 1–4 times over target values, with Cr, Cu, and Zn also exceeding standards. ANOVA results showed no ²²⁶Ra(²³⁸U), ²³²Th, ⁴⁰K, or HM accumulation in topsoil due to FA or BA from the CFPP. Elevated radionuclide and HM levels in topsoil beyond the plant were likely linked to other industries. Annual effective dose (AEDE) was slightly over 1 mSv/y. Pollution indices indicated significant contamination in FA and some topsoil, with As as a major contributor.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103770"},"PeriodicalIF":2.6,"publicationDate":"2025-06-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144513737","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":"Micro-scale molten salt and metal reactor for space applications","authors":"Jaehyun Ryu,&nbsp;Yonghee Kim","doi":"10.1016/j.net.2025.103776","DOIUrl":"10.1016/j.net.2025.103776","url":null,"abstract":"<div><div>This paper introduces a novel reactor concept called Molten Salt Metal Reactor (MSMR), specifically designed for space applications. This innovative reactor leverages a uranium alloy liquid metal as fuel, integrating the advantages of traditional Molten Salt Reactors (MSRs) while achieving criticality in a compact size and enabling long operational lifespans without the need for refueling. To adapt the MSMR for extra-terrestrial use, we employed high-assay low-enriched uranium (HALEU) and heat pipes, followed by comprehensive optimizations to ensure a compact reactor design that delivers both high power and longevity. Our study focuses on assessing the feasibility of the proposed MSMR design through detailed neutronic and thermal-hydraulic analyses. Utilizing the Monte Carlo code Serpent 2 for neutronics and COMSOL 6.2 for thermal-hydraulics, we evaluated the reactor's performance under a 500kW_th condition. The results show that the reactor achieves an operational lifetime of approximately 36 years. Safety evaluation confirms a negative fuel temperature coefficient (−3 pcm/K), an excess reactivity of less than 1$, and a shutdown margin exceeding 7100 pcm under cold conditions. Our findings suggest that the MSMR is a promising candidate for space applications, combining long life, structural simplicity, and superior safety features inherent to MSRs.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103776"},"PeriodicalIF":2.6,"publicationDate":"2025-06-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144580391","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":"Analytical solution for three-dimensional heat conduction in a nuclear waste repository with adiabatic boundaries","authors":"Xun Xu ,&nbsp;Liangfu Xie ,&nbsp;De'an Sun ,&nbsp;Luqiang He","doi":"10.1016/j.net.2025.103781","DOIUrl":"10.1016/j.net.2025.103781","url":null,"abstract":"<div><div>Near-field temperature is a critical indicator in evaluating the safe operation of a nuclear waste repository. Analytical solutions are common methods for analyzing the thermal performance. The existing analytical solutions for temperatures from a single nuclear waste canister in a repository include compound line heat source solutions, semi-analytical solutions, and fully-analytical solutions. However, given that a repository contains thousands of canisters, existing analytical solutions are unable to accurately determine the temperature around the target canister, which is surrounded by numerous adjacent canisters. To this end, the thermal problem at the repository-scale is first transformed into an equivalent problem within a cuboid unit. This unit consists of an individual waste canister encapsulated in buffer material and wrapped in rock under specified boundary conditions. By applying Duhamel's theorem and finite Fourier sine transform, a fully-analytical solution for the temperature field of a single canister under adiabatic boundary conditions was derived. These solutions allow for a convenient and straightforward visualization of temperature evolutions and distributions at a repository-scale through explicit expressions. Furthermore, a formula for calculating the radius of the cylindrical calculation domain was developed, enabling an accurate transformation of the temperature field problem from a cuboid domain to a cylindrical domain.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103781"},"PeriodicalIF":2.6,"publicationDate":"2025-06-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144570993","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":"Fast prediction of the flow induced vibration of wire-wrapped fuel rod in a lead-bismuth reactor based on improved DMD and LSTM network","authors":"Yu Zhang,&nbsp;Pengzhou Li,&nbsp;Hongwei Qiao","doi":"10.1016/j.net.2025.103780","DOIUrl":"10.1016/j.net.2025.103780","url":null,"abstract":"<div><div>Flow induced vibration of wire-wrapped fuel rod in lead-bismuth reactor has become an increasing concern due to its significant influence on cladding fretting wear and reactor operation. In this study, we proposed a reduced order model to expedite the prediction of wire-wrapped fuel rod vibration. Firstly, the predefined structural motion is implemented in the fluid solver using a user defined function, while the fluid forces are computed. Subsequently, both the motion and fluid forces are decomposed into mode functions and time coefficients by dynamic mode decomposition. A long short-term memory network is then trained to bridge the time coefficients of motion and fluid forces. Finally, the vibration response of wire-wrapped fuel rod under different conditions is efficiently calculated using the Newmark integration scheme. The results demonstrate that 18 modes are sufficient to reconstruct the fluid forces, significantly reducing computation complexity, while the long short-term memory network provides reasonable fit to the original data. In addition, the study reveals that the motion of wire-wrapped fuel rod can be chaotic when the axial flow velocity exceeds 2.0 m/s. The mechanism of chaos is attributed to period-doubling bifurcation, a phenomenon not observed in prior simulations. Moreover, the asymmetric geometry of wire-wrapped fuel rod consistently leads to ‘elliptic’ trajectory, and the root mean square values of vibration amplitude can be fitted by the power function with respect to axial flow velocity. The proposed method offers a valuable and convenient tool to study the flow induced vibration of wire-wrapped fuel rod with significant efficiency improvement.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103780"},"PeriodicalIF":2.6,"publicationDate":"2025-06-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144522776","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":"The role of small modular reactors (SMRs) in achieving Net-Zero emissions by an approach to climate actions","authors":"Yun Il Kim ,&nbsp;Tae Ho Woo","doi":"10.1016/j.net.2025.103774","DOIUrl":"10.1016/j.net.2025.103774","url":null,"abstract":"<div><div>As the energy sector is a major driver of atmospheric change, the solution to reduce CO₂ emissions from the combustion of fossil fuels, including oil and coal, is sought in nuclear energy. In this study, we apply the inherent low-carbon emission characteristics of small modular reactors (SMRs) to climate change mitigation. Modeling using the system dynamics (SD) method, a complexity analysis algorithm, shows that the climate mitigation effect in the context of SMR deployment shows a gradual and progressive trajectory over time, which is in contrast to other technologies where the benefits appear particularly abruptly after a certain operational threshold (e.g., 90 months of operation).</div><div>The inherent uncertainty associated with carbon-related variables in the Net-Zero World scenario increases variability, as evidenced by the higher standard deviation, where the standard deviation for the Net-Zero World is over 5.0, while that for SMRs is below 1.0. As a result, a society with net-zero carbon emissions must consider significant uncertainties arising from a variety of factors. Small nuclear reactors have the potential to provide a stable and consistent energy supply even under adverse weather conditions, thereby enhancing energy security and grid resilience.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103774"},"PeriodicalIF":2.6,"publicationDate":"2025-06-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144522774","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 high intensity radio frequency quadrupole accelerator for Suzhou neutron source","authors":"X.W. Liu ,&nbsp;Z.M. Zhang ,&nbsp;L.S. Long ,&nbsp;Z.Y. Zhang ,&nbsp;G.X. Chen ,&nbsp;L.P. Zou ,&nbsp;Z. Yang ,&nbsp;B.W. Zhou ,&nbsp;J.D. Long ,&nbsp;L. Lu ,&nbsp;W. Ma","doi":"10.1016/j.net.2025.103773","DOIUrl":"10.1016/j.net.2025.103773","url":null,"abstract":"<div><div>Neutrons are essential for material structure analysis and scientific research. The neutron source at Suzhou Laboratory employs a proton linear accelerator, with its low-energy section comprising two pulsed RFQ accelerators. In the beam dynamics design, operating at 324 MHz, two RFQs accelerate proton and negative hydrogen beams from 50 keV to 3 MeV, achieving a 98.3 % transmission efficiency over a 3.385 m electrode length. In the radio frequency (RF) design, a four-vane structure with Dipole Stabilizer Rods (DSRs) was adopted to mitigate mode mixing. Thirty-six tuners provide a ±2 MHz frequency tuning range, while optimized undercuts ensure field uniformity. Simulation of the entire cavity shows an eigenmode frequency of 323.95 MHz and a peak power loss of 203 kW. Multi-physics analysis indicates a cavity frequency shift of 20 kHz due to thermal deformation. This study presents the beam dynamics, RF structure, and multi-physics analysis, confirming that the RFQ design meets operational requirements.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103773"},"PeriodicalIF":2.6,"publicationDate":"2025-06-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144522775","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}