Nuclear Engineering and Design最新文献

{"title":"Numerical investigation on the irradiation-induced mechanics behavior in U3Si2/Al dispersion fuel using RVE model","authors":"Wenwen Zhang ,&nbsp;Wenli Guo ,&nbsp;Wentao Hao ,&nbsp;Ding She ,&nbsp;Wei Li","doi":"10.1016/j.nucengdes.2025.114270","DOIUrl":"10.1016/j.nucengdes.2025.114270","url":null,"abstract":"<div><div>A representative volume element (RVE) model was developed to investigate the thermo-mechanical behavior of U₃Si₂/Al dispersion fuel under irradiation. The study focused on the evolution of thermal expansion, elastic properties, creep, and irradiation-induced swelling across varying irradiation conditions. RVE models with different uranium densities were constructed using Voronoi tessellation to approximate the irregular geometry of fuel particles. A phase-field approach was employed to simulate the growth of the interaction layer. Coupled with the finite element method (FEM), a series of detailed simulations were conducted. The simulations revealed that increasing interaction layer thickness (from 0 μm to 20 μm) significantly reduces the thermal expansion coefficient by up to 28 % while increasing stiffness. Higher fission density and fuel particle volume fraction lead to greater swelling strain. The effect of interaction layer thickness on equivalent swelling strain exhibits a dual behavior. The creep behavior is affected by both the interaction layer volume fraction and the applied stress, and can be effectively described by a polynomial-based constitutive model. Compared to traditional homogenization methods, the RVE approach offers improved accuracy in capturing the effects of microstructural heterogeneity on macroscopic fuel performance. These results demonstrate the model applicability for evaluating and optimizing dispersion fuel behavior under irradiation.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"442 ","pages":"Article 114270"},"PeriodicalIF":1.9,"publicationDate":"2025-06-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144502317","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":"Innovative thorium-based fuel assemblies for LW-SMR: In-depth assembly-level neutronic analysis and safety considerations in solid and annular configurations","authors":"Hanan Rifai ,&nbsp;Ouadie Kabach ,&nbsp;Zouhair Sadoune ,&nbsp;El Mahjoub Chakir ,&nbsp;Sinem Uzun ,&nbsp;Hamid Amsil ,&nbsp;Fadi El Banni","doi":"10.1016/j.nucengdes.2025.114274","DOIUrl":"10.1016/j.nucengdes.2025.114274","url":null,"abstract":"<div><div>This study presents a comprehensive neutronic and safety evaluation of different thorium-based fuel compositions (Th-²³⁵U)O₂, (Th-²³³U)O₂, and a new proposed composition, namely, (Th-²³³U-²³⁵U)O₂ fuel, compared to conventional UO₂ in solid and dual-cooled annular assembly configurations in the context of Small Modular Reactors (SMR) applications. Results demonstrate that (Th-²³³U)O₂ achieves the highest cycle length in both solid configurations, significantly exceeding UO₂ performance. The proposed, however, (Th-²³³U-²³⁵U)O₂ composition exhibits favorable safety characteristics, including enhanced negative temperature reactivity coefficients and favorable kinetic parameters. Annular fuel configurations also demonstrate superior thermal performance with centerline temperature reductions of approximately 50 °C compared to solid configurations and consistently lower power peaking factors throughout burnup. The findings indicate that thorium-based fuels, particularly (Th-²³³U-²³⁵U)O₂ in dual-cooled annular configuration, offer compelling advantages for SMR applications, including extended fuel cycles, improved safety characteristics, enhanced proliferation resistance, and superior thermal performance, supporting their viability as sustainable alternatives to conventional uranium-based fuels.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"442 ","pages":"Article 114274"},"PeriodicalIF":1.9,"publicationDate":"2025-06-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144489845","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":"Thermal-hydraulic optimization of a closed-jet trans-critical hydrogen moderator with non-uniform heat sources using machine learning and multi-objective algorithms","authors":"Jiahui Chen ,&nbsp;Jianfei Tong ,&nbsp;Youlian Lu ,&nbsp;Chaoju Yu ,&nbsp;Yu Zhen ,&nbsp;Songlin Wang ,&nbsp;Bin Zhou ,&nbsp;Congju Yao ,&nbsp;Tianjiao Liang ,&nbsp;Wen Yin ,&nbsp;Jian Wen","doi":"10.1016/j.nucengdes.2025.114242","DOIUrl":"10.1016/j.nucengdes.2025.114242","url":null,"abstract":"<div><div>The optimization of heat transfer in transcritical hydrogen moderators, such as the Decoupled Poisoned Hydrogen Moderator (DPHM) at the China Spallation Neutron Source (CSNS), is critical for enhancing neutron flux and ensuring the safe operation of spallation neutron sources. This study addresses the unique thermal–hydraulic challenges posed by closed-jet impingement and non-uniform internal heat sources in transcritical hydrogen systems, which are essential for maintaining efficient neutron moderation and thermal stability. A three-dimensional computational model is developed to investigate the effects of key design parameters, including the flow baffle offset (<em>L</em>), inlet jet height (<em>H</em>), and hydrogen mass flow rate (<em>m</em>), on heat transfer and flow dynamics. Leveraging a genetic algorithm-optimized backpropagation (BP) neural network, this work introduces an innovative predictive framework to capture the complex nonlinear relationships between these parameters and system performance. Furthermore, a multi-objective optimization approach combining NSGA-III and TOPSIS is employed to identify optimal operating conditions that balance cooling efficiency and flow velocity constraints. The results demonstrate the critical role of jet impingement in mitigating thermal stratification and improving heat transfer, offering significant insights for the design and optimization of hydrogen moderators in advanced nuclear systems. This study not only advances the understanding of transcritical hydrogen behavior under non-uniform heat sources but also provides a practical, machine learning-enhanced methodology for optimizing thermal–hydraulic performance in spallation neutron sources.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"442 ","pages":"Article 114242"},"PeriodicalIF":1.9,"publicationDate":"2025-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144480838","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":"Feasibility of small modular reactors for decarbonizing district heating systems: a case study of the Helsinki metropolitan area","authors":"Jussi-Pekka Ikonen,&nbsp;Tomi J. Lindroos,&nbsp;Pauli Hiltunen","doi":"10.1016/j.nucengdes.2025.114262","DOIUrl":"10.1016/j.nucengdes.2025.114262","url":null,"abstract":"<div><div>This study explores the feasibility of integrating small modular reactors (SMRs) into the district heating (DH) and cooling system of the Helsinki metropolitan area, Finland. The objectives of the study are to evaluate the economic and operational aspects of two SMR technologies, the academic concept E-SMR (155 MWelectric/50 MW_DH) and the VTT-developed LDR-50 (50 MW_DH), as well as their environmental impact on the DH and cooling system using the Backbone modeling framework. Despite investments in biomass-fired DH generation and large heat pumps, Helsinki remains heavily dependent on fossil fuels. SMRs could potentially offer a reliable and continuous supply of carbon-free energy.</div><div>Results indicate that while both SMR designs reduce CO2 emissions and enhance electricity supply, E-SMR is not a profitable investment, whereas LDR-50 is. The fluctuating energy demand and low electricity prices in the studied area presented challenges for the larger E-SMR. Heat production capabilities are highly valued in the studied system, which was reflected in LDR-50′s profitability and the sensitivity study of E-SMR’s heat extraction rate.</div><div>Sensitivity analyses highlighted the influence of economic factors such as investment costs, discount rates, and operating expenses on the profitability of both SMRs. Additionally, energy market conditions play a crucial role in determining the financial viability of SMRs, suggesting that their profitability can vary significantly under different market scenarios. Integrating SMRs into future energy systems, such as electrolyzers, could enhance their feasibility, warranting further research. Moreover, the economic viability of different fuel strategies should be investigated to explore their potential benefits for SMRs.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"442 ","pages":"Article 114262"},"PeriodicalIF":1.9,"publicationDate":"2025-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144489844","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":"Photonuclear treatment for spent fuel radiotoxicity reduction: a case study investigation on minor actinides","authors":"Antonio Cammi ,&nbsp;Lorenzo Loi ,&nbsp;Andrea Missaglia ,&nbsp;Ludovica Tumminelli ,&nbsp;Francesca Giacobbo ,&nbsp;Enrico Padovani","doi":"10.1016/j.nucengdes.2025.114204","DOIUrl":"10.1016/j.nucengdes.2025.114204","url":null,"abstract":"<div><div>The management of Spent Nuclear Fuel (SNF) is one of the main challenges in the decommissioning of nuclear power plants. Thermal reactors, such as Light Water Reactors (LWRs), produce significant amounts of minor actinides (MAs) such as Americium, Curium, and Neptunium, which are key contributors to the long-term radiotoxicity and decay heat in SNF. Currently, the long term widely accepted solution is the geological disposal. At the same time, advanced technologies like Partitioning and Transmutation (P&amp;T) offer promising solutions to reduce SNF long-term radiotoxicity. While most transmutation strategies rely on neutron fluxes, in this study the adoption of photon beam to induce photonuclear reactions in SNF is investigated, without depending on neutron based systems. In particular, the study focuses on the probability of inducing transmutations and fissions on MAs, by leveraging the Giant Dipole Resonance (GDR) region of photonuclear interactions. In the presented case study, the aim was to investigate the effect of a photon driven transmutation of minor actinides present in a spent fuel from SMR technology. The focus was mainly put on studying the physics of the system, analysing the feasibility of reducing the inventory and radiotoxicity of the system by this method, without considering technological aspects and limitations.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"442 ","pages":"Article 114204"},"PeriodicalIF":1.9,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144470199","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 tail-oriented multi-normal model method for partially correlated seismic fragilities in probabilistic risk assessment","authors":"Mohamed M. Talaat ,&nbsp;Abhinav Anup","doi":"10.1016/j.nucengdes.2025.114217","DOIUrl":"10.1016/j.nucengdes.2025.114217","url":null,"abstract":"&lt;div&gt;&lt;div&gt;Many seismic-induced failures are due to shaking effects in response to common ground motions. Since the effects of shaking are propagated to equipment with varying configurations located at the same or different locations, there is often a degree of partial correlation between these failures. Common practice in seismic probabilistic risk assessment (SPRA) of nuclear facilities typically idealizes this partial correlation as either perfect correlation or full independence. Recent studies indicate that refining this practice for structures or components with considerable risk contributions can lead to significant effects on the SPRA outcome. Methods and techniques to incorporate the modelling of partial correlation in SPRA models have received increasing research attention in recent years, and a few recent SPRAs explicitly modelled it for risk-significant contributors. While applicable to single-unit (SU) SPRA, explicit modelling of seismic fragility partial correlation may be even more impactful for multi-unit (MU) SPRA.&lt;/div&gt;&lt;div&gt;Several methods with various degrees of rigor exist in the literature for explicitly modelling partial correlation between seismic fragilities in a probabilistic risk quantification. The available rigorous methods typically involve the use of numerical simulation or computationally intensive numerical analysis, which are not practical for inclusion in SPRA qualification. This article discusses the tail-oriented multi-normal model (TMM) method, a robust technique for explicitly modelling partial correlation between seismic fragilities in SPRA applications. The TMM method is based on the Separation of Independent and Common Variables (SICV) concept and is superior to other SICV-based techniques in that it uses an efficient closed-form formulation. This analytical solution is premised on the lognormal probability distribution being a valid representation of seismic-induced failure fragilities, which is commonly accepted in SPRA.&lt;/div&gt;&lt;div&gt;This article is divided into an introduction and four sections. The introduction reviews available relevant literature on the topic, presents relevant technical background elements, and summarizes specific current technical challenges. The first section introduces the TMM method formulation, and implementation steps. The second section presents validation examples. The third section discusses the determination of partial correlation factors and the sensitivity of the TMM method results to the accuracy of the partial correlation factors. The fourth section discusses the use of the TMM method in SPRA models.&lt;/div&gt;&lt;div&gt;The performance of the TMM method is found to be more favourable than the widely used Reed-McCann method both computationally (processing time) and analytically (solution accuracy). The TMM method results are found to be weakly sensitive to fragility analyst judgement in quantifying partial correlation, making it robust against potential bias in such judgements. Furt","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"442 ","pages":"Article 114217"},"PeriodicalIF":1.9,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144470666","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 applications and prospects of BEPU methodology in Generation III nuclear reactors","authors":"Mengyan Hu ,&nbsp;Chengcheng Deng ,&nbsp;Shizhen Yu ,&nbsp;Xueyan Zhang ,&nbsp;Jun Yang","doi":"10.1016/j.nucengdes.2025.114205","DOIUrl":"10.1016/j.nucengdes.2025.114205","url":null,"abstract":"<div><div>The Best Estimate Plus Uncertainty (BEPU) methodology has been developed over decades and it has been validated in the safety assessment of nuclear reactors. The endorsement of BEPU by regulatory bodies signifies a substantial progression for its implementation. Numerous innovations have been suggested to enhance the efficiency and quality of the BEPU procedure to facilitate its deployment. Generation III/III+ reactors, as the predominant technology in contemporary commercial nuclear power, have undergone analysis, evaluation, and licensing with the use of BEPU techniques to varying degrees. The overview of BEPU applications employing thermal-hydraulic system codes under various scenarios was illustrated, and the characteristics of the calculated results were summarized and analyzed, including the uncertainty parameters selection and the methods of uncertainty quantification and sensitivity analysis. Surrogate model analysis scheme with qualified accuracy was proposed seeking to lower anthropogenic effects. The current effort is expected to provide an insightful summary and vision for the method optimization and further implementation of BEPU methodology.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"442 ","pages":"Article 114205"},"PeriodicalIF":1.9,"publicationDate":"2025-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144470662","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Development of a steady-state single-channel model of the BAEC 3MWt TRIGA mark-II research reactor for thermal and hydrodynamic analysis","authors":"Saad Islam ,&nbsp;Ali Mahdi ,&nbsp;Mohammad Khan ,&nbsp;Mohammad Abdul Motalab","doi":"10.1016/j.nucengdes.2025.114218","DOIUrl":"10.1016/j.nucengdes.2025.114218","url":null,"abstract":"<div><div>The Bangladesh Atomic Energy Commission (BAEC) operates the 3 MWt TRIGA MARK II research reactor (BTRR), the only research reactor in Bangladesh, located at the Atomic Energy Research Establishment (AERE) in Savar. Since its commissioning in 1986, the reactor has served multipurpose roles, including training, education, radioisotope production, and various research activities in neutron activation analysis, neutron scattering, and neutron radiography. This study focuses on the development and application of a single-channel model for the BTRR core, providing the capability to analyze the steady-state thermal and hydrodynamic behavior of the reactor under both forced convection and natural circulation cooling modes of operation. An iterative strategy was adopted with external coupling between Monte Carlo neutronics (OpenMC) and the developed single-channel model. The coupled approach captures the feedback between temperature-dependent cross-sections, control rod position, and reactor thermal behavior, enabling more accurate predictions of critical parameters. The model is used with multiple correlations developed by McAdams et al., Bernath, Labuntsov, Mirshak et al., Lund, and the 2006 Groeneveld look-up table (LUT), to determine critical heat flux (CHF) and departure from nucleate boiling ratio (DNBR) for the hottest channel at different power levels under operational conditions. The Bernath correlation, traditionally used for TRIGA reactors, provided conservative CHF estimates, while the 2006 Groeneveld LUT offered higher safety margins. Comparisons with other correlations highlighted variations in CHF predictions, emphasizing the need for a comprehensive approach using multiple correlations to enhance reactor performance and safety. This analysis shows verification of the model against previous code-based calculations and provides detailed insights into predicting critical thermal margins, including CHF and DNBR characteristics of the reactor. The developed model provides a basis for safety predictions and highlights the potential for enhancing reactor performance, including future upgrades to the BTRR core configuration.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"442 ","pages":"Article 114218"},"PeriodicalIF":1.9,"publicationDate":"2025-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144470198","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":"Fire modelling of a glove box for use in a two-zone fire model","authors":"W. Plumecocq,&nbsp;M. Coutin,&nbsp;J.P. Joret,&nbsp;F. Lamare","doi":"10.1016/j.nucengdes.2025.114256","DOIUrl":"10.1016/j.nucengdes.2025.114256","url":null,"abstract":"<div><div>Accidental fires in nuclear fuel manufacturing and reprocessing plants can cause the glove box containment to rupture with a risk of dispersion of radioactive materials within the installation. Fire safety analyses require an assessment of the resulting radiological consequences to reinforce the appropriate prevention and protection measures in these installations. Since 2019, a research project named FIGARO aims at reducing the uncertainties related to the assessment of the airborne release fraction of plutonium involved in glove box fires. As part of this project, a semi-mechanistic model of glove box fire was developed and implemented in the two-zone code SYLVIA. Modelling glove box fires is a challenging task due to complex phenomena occurring in the glove box during its combustion. No theory has yet been put forward on how to model all aspects of the problem, even for simple, open atmosphere conditions. This model separates the combustion of the polycarbonate containment walls of the glove box from that of the biological protection panels, by modelling a glove box as a set of horizontal and vertical walls. A validation of this model was performed on two large-scale glove box fire tests carried out in a confined and mechanically ventilated enclosure (BAG_CSS experiments). Note that some parameters of the glove box model have been calibrated on the glove box qualification test carried out in an open atmosphere, under a calorimetric hood. Considering this preliminary calibration, the fire heat release rate is well reproduced by the model for both experiments.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"442 ","pages":"Article 114256"},"PeriodicalIF":1.9,"publicationDate":"2025-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144365513","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":"Solidification of tributyl phosphate/dodecane waste using metakaolin-based potassium geopolymers","authors":"Abdelaziz Hasnaoui ,&nbsp;Jess McWilliams ,&nbsp;Charles Reeb ,&nbsp;Martin Hayes ,&nbsp;Catherine A. Davy ,&nbsp;John L. Provis ,&nbsp;David Lambertin","doi":"10.1016/j.nucengdes.2025.114251","DOIUrl":"10.1016/j.nucengdes.2025.114251","url":null,"abstract":"<div><div>The conditioning of radioactive tributyl phosphate/dodecane (TBP/dodecane) wastes represents a real challenge in the nuclear industry. In fact, TBP/dodecane mix is one of the radioactive liquid organic wastes for which no adequate or industrially mature solutions are currently available for its treatment. To address this issue, the potential of metakaolin (MK)-based potassium geopolymer for the solidification of TBP/dodecane was investigated in the present study. This requires the addition of a surfactant to enable production of a wasteform with the desired rheological, mechanical and microstructural properties.</div><div>Three surfactants were tested and Brij O10 was found to be the most efficient in terms of emulsification and initial fresh stability. The obtained results show that the use of a MK-based potassium geopolymer binder combined with Brij O10 is a potentially feasible solution for the conditioning of this TBP/dodecane mix, by providing good emulsion workability and a stable monolithic composite before and after hardening. Furthermore, in terms of mechanical properties (which have to remain above 8 MPa to achieve industrial storage specifications), this study confirms that MK-based potassium geopolymers can safely be used for the solidification of TBP/dodecane wastes.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"442 ","pages":"Article 114251"},"PeriodicalIF":1.9,"publicationDate":"2025-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144365514","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}