Nuclear Engineering and Design最新文献

{"title":"Enhancing small modular reactor adoption for sustainable energy transition: a Fermatean fuzzy ISM-MICMAC framework for analyzing challenges","authors":"Ismail Erol ,&nbsp;Ahmet Oztel ,&nbsp;Ihsan Tolga Medeni ,&nbsp;Ilker Murat Ar","doi":"10.1016/j.nucengdes.2026.114805","DOIUrl":"10.1016/j.nucengdes.2026.114805","url":null,"abstract":"<div><div>Small modular reactors (SMRs) promise reduced upfront costs, faster construction, and enhanced safety compared to traditional reactors. However, widespread adoption is hindered by challenges such as high capital costs, regulatory delays, supply chain inefficiencies, cybersecurity risks, nuclear waste management, and public skepticism. Despite qualitative studies highlighting these barriers, quantitative analyses remain scarce, necessitating systematic frameworks to model interdependencies and guide solutions. The goal of this study is to scrutinize SMR adoption challenges using a novel multi-criteria decision-making (MCDM) approach. Drawing on a literature review from Web of Science, Scopus, and various reports from international institutions, 13 key challenges were identified. A panel of 58 experts—academics, government officials, and cybersecurity specialists—provided inputs via pairwise comparisons. The methodology used in this study integrates Fermatean Fuzzy Interpretive Structural Modeling (FFISM) with the cross-impact matrix multiplication applied to classification (MICMAC) analysis. Fermatean fuzzy sets extend traditional ISM by accommodating higher uncertainty in expert judgments through expanded membership/non-membership degrees. Validation involved 10,000 simulations comparing FFISM to conventional fuzzy ISM. Results reveal a six-level hierarchy: licensing/regulatory constraints and lack of proven technology/FOAK units as top challenges, influencing linkage challenges such as supply chain effectiveness, cybersecurity risks, and waste management. Dependent challenges include perceived investment risk, cost estimation, and public opinion. Policy recommendations include risk-informed licensing to cut timelines, blockchain for traceability addressing fuel availability, and public-private partnerships with green bonds to mitigate risks. This research provides actionable strategies for policymakers and stakeholders to accelerate SMR deployment, strengthening nuclear energy's role in global decarbonization.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"450 ","pages":"Article 114805"},"PeriodicalIF":2.1,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146190729","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 foreign object retrieval robot for the internal lower head of a nuclear power plant pressurizer","authors":"Fenghan Ran ,&nbsp;Shiqi Chen ,&nbsp;Shuai Huang ,&nbsp;Xingli Zhu","doi":"10.1016/j.nucengdes.2026.114785","DOIUrl":"10.1016/j.nucengdes.2026.114785","url":null,"abstract":"<div><div>Manual extraction of foreign objects from the lower head of a pressurizer poses significant challenges, including high personnel radiation exposure and operational complexity. This paper offers a comprehensive overview of the design and structure of a foreign object extraction robot for the lower head. It delves into the specific designs of key components like the clamping mechanism, waist and wrist rotating joints, shoulder and elbow swinging joints, and foreign object extraction actuators. Additionally, it provides an in-depth analysis of the robot's reliability. By enabling remote-controlled operation, the robot can extract foreign objects from the lower head without requiring personnel to enter the pressurizer. The findings of this study hold great significance for addressing similar foreign objects related incidents in pressurizers at other power plants.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"449 ","pages":"Article 114785"},"PeriodicalIF":2.1,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145981785","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 and pilot production of Fully Ceramic Microencapsulated (FCM®) fuels fabricated by sintering","authors":"Cameron Hilliard ,&nbsp;Ethan Deters ,&nbsp;Mason Phillips ,&nbsp;Caen Ang","doi":"10.1016/j.nucengdes.2025.114745","DOIUrl":"10.1016/j.nucengdes.2025.114745","url":null,"abstract":"<div><div>Fully Ceramic Microencapsulated (FCM®) fuels produced by sintering has been demonstrated in a method that does not damage fuel particles, due to assembling particles into layers. Pilot manufacturing data (<em>N</em> = 32) of the designed fuel is presented. Screening of SiC powders indicated that sintered densities are a function of powder size and compaction pressure. Abiding particles are postulated to prevent interparticle infiltration of powder. Image analysis of X-ray Computed Tomography (XCT) and optical microscopy cross-sections show a trend of decreasing matrix density between particles, and density is underestimated by metallographic methods. Interparticle porosity was always observed, limiting matrix density (86–97 %). Appropriate green forming can ensure all fired porosity is closed against He, water, and O₂ penetration. TRISO packing fractions were between 36 and 38 % and the packing has room for improvement. For industry adoption, development of radiation-stable, pressureless sintering of SiC is recommended.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"449 ","pages":"Article 114745"},"PeriodicalIF":2.1,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146036025","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":"On the reactor physics implications of the use of UB2 as an additive within UN","authors":"Olga Negri,&nbsp;Tim Abram,&nbsp;Joel Turner","doi":"10.1016/j.nucengdes.2026.114800","DOIUrl":"10.1016/j.nucengdes.2026.114800","url":null,"abstract":"<div><div>The addition of UB₂ to UN fuel raises the onset temperature of its reaction with high-temperature steam. Natural boron contains 19.9% B-10, a strong neutron absorber that decays to Li-7 and He-4 upon neutron capture. This study explores the reactor physics implications of UN-UB₂ (10% UB₂) fuel with varying B-10 concentrations. Depletion analysis of an infinite lattice has shown that UN-UB₂ with 0–2% B-10 maintained cycle lengths similar to UN at equivalent U-235 enrichment and exhibited reduced reactivity swings. At 1500 effective full power days (EFPD), noble gas production in UN-UB₂ (1% B-10) was comparable to UO₂, with helium levels similar to krypton. The fuel temperature coefficient (FTC) was consistently negative across all materials, depletion levels, and temperatures. These results indicate that UN-UB₂ (1% B-10) offers comparable performance to UO₂ with benefits in enrichment, thermal conductivity, manageable helium generation, and effective reactivity control for LWRs.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"450 ","pages":"Article 114800"},"PeriodicalIF":2.1,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146190257","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 conjugate heat transfer coupling model for supercritical water flowing in 2 × 2 ballooning ATF rod bundles","authors":"Chengrui Zhang ,&nbsp;Juan Chen","doi":"10.1016/j.nucengdes.2026.114782","DOIUrl":"10.1016/j.nucengdes.2026.114782","url":null,"abstract":"<div><div>The conjugate heat transfer characteristics of ballooning accident-tolerant fuel (ATF) rods in supercritical water were systematically investigated. A two-dimensional numerical multi-physics conjugate heat transfer program was developed for a 2 × 2 rod bundle with blocking sleeve and spacer grids, based on a comprehensive review of experimental and simulation studies on blocked flow, with particular emphasis on correlations for the friction coefficient and convective heat transfer coefficient. The program integrates a two-dimensional thermal conductivity model for ballooning fuel rod, solved by the finite difference method, with the simulation of convective heat transfer between the deformed cladding and coolant using various heat transfer coefficient correlations. Flow distribution between blocked and unblocked channels containing spacer grids is also simulated under supercritical pressure conditions, also employing the finite difference method with different friction coefficient correlations applied. Validation against SWAMUP experimental data shows that the relative error of the calculated axial cladding surface temperature remains within 1.6 %. Subsequently, the effects of blockage ratio, heat flux, and system pressure on heat transfer performance were analyzed. Key findings include: 1) the convective heat transfer coefficient downstream of the blockage region generally increases owing to enhanced turbulence, particularly at low swelling ratio. 2) When the swelling ratio exceeds 55 %, friction pressure drop contributes up to 87.1 % of the total pressure drop, leading to heat transfer deterioration. 3) Higher system pressures result in a greater total pressure drop and more uniform flow distribution between blocked and unblocked channels. 4) Heat transfer deterioration can occur when the inlet temperature approaches the pseudo-critical temperature. This research provides theoretical support for the design optimization and safe operation of SCWR.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"449 ","pages":"Article 114782"},"PeriodicalIF":2.1,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146036055","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":"Scaling sensitivity and data applicability analysis of small-scale integral test to the ESBWR small break loss-of-coolant accidents","authors":"Xueyan Zhang,&nbsp;Yixuan Zhang,&nbsp;Jun Yang","doi":"10.1016/j.nucengdes.2026.114788","DOIUrl":"10.1016/j.nucengdes.2026.114788","url":null,"abstract":"<div><div>Employing system-code simulations, the study investigates scaling effects on transient simulations, uncertainty and sensitivity quantification, and data applicability analysis between the Purdue University Multi-Dimensional Integral Test Assembly and the Economic Simplified Boiling Water Reactor. The analysis focuses on refining Best Estimate Plus Uncertainty methodologies for nuclear reactor safety by evaluating the impact of scaling between test facilities and their prototypes. Transient simulation results highlight the importance of precise scaling in replicating system behaviours during small break loss-of-coolant accidents, with particular emphasis on the discrepancies in dynamic responses. In uncertainty and sensitivity quantification, variations due to scaling notably influence the magnitude and correlation of critical parameters such as the Depressurization Valve discharge coefficient and core thermal hydraulic diameter, underscoring the necessity for accurate model scaling in safety assessments. Furthermore, data applicability analysis, bolstered by dimensionless number evaluations, reveals essential insights into the extent to which scaled experimental data can mirror prototype phenomena, thereby emphasizing the pivotal role of scaling in experimental setups for nuclear safety analysis. Collectively, these findings advance the accuracy of predictive safety evaluations and contribute significantly to the enhancement of nuclear safety standards and methodologies.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"449 ","pages":"Article 114788"},"PeriodicalIF":2.1,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146036027","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 validation of fission response function neutron transport code FLASH in AP1000 reactor core","authors":"Honglong Li ,&nbsp;Xinxiang Long ,&nbsp;Yunxin Zhang ,&nbsp;Donghao He ,&nbsp;Xiaojing Liu","doi":"10.1016/j.nucengdes.2026.114759","DOIUrl":"10.1016/j.nucengdes.2026.114759","url":null,"abstract":"<div><div>FLASH, based on the fission response function (FRF) theory, is a high-fidelity and low-cost adaptive neutronics code. In this study, FLASH is validated in the AP1000 pressurized water reactor whole-core problem at hot zero power condition. It features a highly heterogeneous core arrangement with enrichment zoning, WABA and IFBA utilization. To accurately simulate the reactor core, an FRF database comprising 20 distinct assembly types was developed, and environmental factors were employed to account for local effects. Compared with Monte Carlo reference calculation, the FLASH AP1000-3D whole-core calculation yielded a <span><math><msub><mrow><mi>k</mi></mrow><mrow><mi>e</mi><mi>f</mi><mi>f</mi></mrow></msub></math></span> error of 236 pcm and a RMS error in the pin-wise fission rate distribution of 0.99%. The entire core calculation was completed in less than 2 min.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"449 ","pages":"Article 114759"},"PeriodicalIF":2.1,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146036029","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":"Corrigendum to \"Verification of PWR-Core power distribution based on precisely calculated SPND response currents\" <[ Nuclear Engineering and Design 448 (2026) 114726]>","authors":"Sipeng Du,&nbsp;Yunzhao Li,&nbsp;Hangqi Zhang,&nbsp;Ruizhi Shao,&nbsp;Liangzhi Cao","doi":"10.1016/j.nucengdes.2026.114804","DOIUrl":"10.1016/j.nucengdes.2026.114804","url":null,"abstract":"","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"449 ","pages":"Article 114804"},"PeriodicalIF":2.1,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146189362","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":"Corrigendum to “Development of robustness assessment methodology for passive safety system against potential performance issue” [Nucl. Eng. Des. 449 (2026) 114755]","authors":"Jehee Lee ,&nbsp;Seong-Su Jeon ,&nbsp;Ju-Yeop Park ,&nbsp;Hyoung Kyu Cho","doi":"10.1016/j.nucengdes.2026.114794","DOIUrl":"10.1016/j.nucengdes.2026.114794","url":null,"abstract":"","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"449 ","pages":"Article 114794"},"PeriodicalIF":2.1,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146189365","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":"Experimental study of decontamination factor in pool scrubbing with two-phase flow evolution","authors":"Taizo Kanai ,&nbsp;Miki Saito","doi":"10.1016/j.nucengdes.2026.114771","DOIUrl":"10.1016/j.nucengdes.2026.114771","url":null,"abstract":"<div><div>Pool scrubbing is a key mitigation process in nuclear severe accidents (SAs), in which aerosols and gaseous fission products (FPs) are injected into water and removed through gas–liquid interactions. Although the decontamination factor (DF) depends strongly on particle size and hydrodynamic conditions, systematic DF datasets obtained under high-flow, non-condensing conditions—together with corresponding detailed two-phase flow-field measurements—remain scarce. This study addresses this gap by providing a high-accuracy, size-resolved DF dataset consistent with independently measured flow-field data. A 0.5-m-diameter, 8-m-high test facility was used to reproduce the characteristic severe-accident flow evolution from large globules to bubble breakup and the formation of a fine-bubble swarm. Using Welas, SMPS, and ELPI+, size-resolved DF values for soluble CsI aerosols were obtained over a wide aerodynamic-diameter range (sub-0.05 μm to 10 μm). The mixture water level was varied continuously from 0 to approximately 5 m, enabling DF measurements across evolving flow structures. The DF exhibited clear dependencies on both particle size and water level, and the transition from the injection/breakup region to the swarm region was directly reflected in the DF behavior. These trends were consistent with detailed axial bubble-size evolution measured previously in the same facility.</div><div>An empirical DF correlation was developed as a function of mixture water level and aerodynamic diameter. Comparison of this correlation with the DF measurements, flow-field data, and the mechanistic MELCOR/SPARC90 model showed that, while the major hydrodynamic transitions were consistent with the model, the experimentally observed particle-size dependence and gas-flow-rate independence revealed characteristics associated with strongly turbulent, multidimensional bubble motion in the swarm region. Furthermore, SMPS measurements demonstrated a pronounced DF increase for ultrafine particles (&lt;0.05 μm) due to Brownian diffusion—providing new experimental evidence in a particle-size range for which reliable DF data have been largely unavailable.</div><div>A comparison with insoluble BaSO₄ aerosols generated under identical conditions showed consistently lower DF values for BaSO₄ despite nearly identical particle density, indicating that aerosol solubility has a significant influence on removal efficiency.</div><div>The systematic DF dataset obtained in this study elucidates the governing mechanisms of particle-size-dependent aerosol removal under realistic pool-scrubbing flow regimes. Combined with detailed flow-field measurements from the same facility, these results provide a robust benchmark for improving mechanistic DF models, particularly under high-flow conditions relevant to severe-accident source-term assessments.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"449 ","pages":"Article 114771"},"PeriodicalIF":2.1,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145981784","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}