Nuclear Engineering and Technology最新文献

{"title":"Enhancing structural stability and mechanical performance of Pmmn-phase U2Mo alloy through V and Ti Doping: Insights from density functional theory","authors":"Shuaiyi Shui,&nbsp;Xinyu Zhang,&nbsp;Jia Song,&nbsp;Dezhong Wang,&nbsp;Wentao Zhou","doi":"10.1016/j.net.2025.103758","DOIUrl":"10.1016/j.net.2025.103758","url":null,"abstract":"<div><div>Given the urgent demand for high-performance nuclear fuels driven by advanced reactor technologies, in-depth investigations into uranium-based alloys have garnered significant attention. This study employs density functional theory (DFT) to systematically investigate the effects of vanadium (V) and titanium (Ti) doping on the structural stability, electronic properties, mechanical characteristics, and thermodynamic behaviors of <em>Pmmn</em>-phase U2Mo alloys. Through structural optimization and phonon spectrum analysis, dynamically stable doped configurations were successfully constructed. These doped systems exhibit enhanced thermodynamic stability compared to the pristine U4Mo2 matrix. Density of states (DOS) analysis reveals intensified hybridization of V-4d orbitals above the Fermi level. Mechanically, U4VMo demonstrates substantial improvements, including enhanced shear modulus (<em>G</em>) and Young's modulus (<em>E</em>), along with an 11 % increase in tensile strength along the [100] crystallographic direction. Thermodynamic evaluations underscore superior high temperature performance, with U4MoTi displaying an increase in thermal expansion coefficient at 950 K relative to the matrix. Volumetric expansion analysis identifies lattice distortion relaxation induced by Ti/V doping, resulting in a 15–18 % elevation in <em>ΔL/L</em>_<em>0</em> ratios. These findings establish a theoretical foundation for optimizing uranium-molybdenum nuclear fuels through transition metal doping, offering critical insights for advanced nuclear fuel design and application.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103758"},"PeriodicalIF":2.6,"publicationDate":"2025-06-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144480763","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 test task for coupled neutronic and thermal-hydraulic analysis of LFR fuel cell","authors":"Maksim Chubarov,&nbsp;Mikhail Zakharov,&nbsp;Ekaterina Bogdanova,&nbsp;Anton Smirnov,&nbsp;Deniel Ouen,&nbsp;Georgy Tikhomirov","doi":"10.1016/j.net.2025.103763","DOIUrl":"10.1016/j.net.2025.103763","url":null,"abstract":"<div><div>In the absence of operational experience with Generation IV reactors and limited experimental data, developing test tasks is crucial for ensuring the safety and reliability of novel reactor designs. This study presents a test task for coupled neutronic and thermal-hydraulic analysis of a lead-cooled fast reactor (LFR) fuel unit cell in the BREST-OD-300 core. Neutronic simulations using the Monte Carlo-based MCU-FR code identified an optimal axial discretization of 44 layers to reduce uncertainties in power density distribution. The resulting axial power density profiles were used in CFD thermal-hydraulic modeling with LOGOS software to assess the impact of different turbulent Prandtl number correlations on axial temperature profiles. The study shows that the choice of turbulent Prandtl number introduces up to 1% model-uncertainty in temperature predictions due to differences in turbulence modeling assumptions. In addition, the application of fully coupled neutronic and thermal-hydraulic feedback results in a deviation of above 2% in average fuel temperature compared to the non-coupled solution. This test task is aimed at enhancing the accuracy of reactor simulations and safety assessments while contributing to the development of a benchmark suite for LFR reactors, supporting cross-verification of computational tools and methods.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103763"},"PeriodicalIF":2.6,"publicationDate":"2025-06-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144513604","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":"Capabilities of simple calculation models for the analysis of power reactors","authors":"Mohamed A. Gaheen","doi":"10.1016/j.net.2025.103762","DOIUrl":"10.1016/j.net.2025.103762","url":null,"abstract":"<div><div>A simple model was developed for the calculation of the coupled kinetics and thermal-hydraulics response of power reactor cores. The developed model was used for the analysis of the Special Power Excursion Reactor Test III (SPERT-III) E-Core and Loss of Fluid Test (LOFT) Experiment L9-3. The model prediction results were compared with the experimental data for the reactivity insertion and loss of secondary feed water transients without scram. The comparison showed that the model predictions are accurate enough to confirm the capabilities and adequacy of the model. It can be concluded that the model results provide confidence in the application of simple calculation models to the analysis of power transients.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103762"},"PeriodicalIF":2.6,"publicationDate":"2025-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144570991","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":"Dual-purpose borate based glasses: optical features and Monte Carlo simulations of gamma radiation shielding","authors":"M.I. Sayyed ,&nbsp;K.A. Mahmoud ,&nbsp;Shrikant Biradar ,&nbsp;U. Rilwan ,&nbsp;Laith Ahmed Najam","doi":"10.1016/j.net.2025.103752","DOIUrl":"10.1016/j.net.2025.103752","url":null,"abstract":"<div><div>The study uses the melt quenching method for fabrication of a new series of borate based glasses according to the chemical formula of (9+x) PbO₂+20 BaO+11 CaO+ (60-x-y-z) B₂O₃+y Eu₂O₃+z Pr₆O₁₁; x = 0, 3, 6, and 9 mol% and y = z = 0.25, 0.5, 0.75, and 1 mol%. The aforementioned borate-based glass series is being fabricated with the dual purpose of serving as radiation shielding and optical materials. The substitution of PbO₂, Eu₂O₃, and Pr₆O₁₁ for the B₂O₃ enhances the density of fabricated glasses (4.023–4.680 g/cm³) when the PbO₂+Eu₂O₃+Pr₆O₁₁ raised from concentrations of 9.5 mol% to 20 mol%. Increase in concentration of PbO₂+Eu₂O₃+Pr₆O₁₁ (9.5–20 mol.%) causes decrease in the energy band gap (direct transition) from 3.080 to 2.964 eV. The refractive index was enhanced (2.486–2.529) when the doping compounds were raised within the prepared glasses. The Monte Carlo simulation results over energy interval of 0.015–15 MeV showed that, increase in concentration of PbO₂+Eu₂O₃+Pr₆O₁₁ (9.5–20 mol%) enhances the LAC values from 6.899 to 9.690 cm⁻¹ (at 0.08 MeV), 0.248–0.293 cm⁻¹ (at 1 MeV), and 0.134–0.178 cm⁻¹ (at 15 MeV).</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103752"},"PeriodicalIF":2.6,"publicationDate":"2025-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144322604","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":"To compare the image quality of high resolution CT scan of temporal bone reconstructed using novel adaptive statistical iterative reconstruction-v technique with conventional filter back projection reconstruction technique","authors":"V. Ruth Monica ,&nbsp;P. Preethi","doi":"10.1016/j.net.2025.103766","DOIUrl":"10.1016/j.net.2025.103766","url":null,"abstract":"<div><div>To compare the image quality of high resolution CT scan of temporal bone reconstruction using a novel adaptive iterative reconstruction-V (IR) technique with conventional filter back projection technique. The objective (mean image noise, contrast-to-noise ratio (CNR) for the temporal bone and the mean attenuation value of soft tissue) and subjective image parameters (image noise, image contrast, overall visibility of temporal bone/soft issue visibility of small structures and overall diagnostic confidence) were assessed. Eighteen patient underwent standard protocol of CT temporal bone at our institution. The same raw data were reconstructed using FBP and ASIR 20 %, ASIR 40 %, ASIR 60 %, ASIR 80 %.result shows that image measurements revealed significantly less noise in the soft tissue than bone attenuation value for the ASIR (p-value&lt;0.05). Used Wilcoxon signed rank test. Filter back projection and ASIR Bone with various percentages but there no significant difference in two methods (p &lt; 0.05). Comparing Filter back projection Soft Tissue and ASIR Soft Tissue, there is significant with in ASIR-Soft Tissue percentages various percentages and also it is better than FBP (p &lt; 0.05). Note Data are indicated Median and IQR=Interquartile range (25th and 75th percentile). It is statistically significant difference of increasing percentage of ASIR percentage of soft tissue. This study concluded that ASIR shows superior reduction of noise and improved image quality (both objective and subjective analysis) compared with ASIR and FBP CT Temporal bone examination.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103766"},"PeriodicalIF":2.6,"publicationDate":"2025-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144471206","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":"Scenario analysis of radon attenuation efficacy of earthen cover for uranium mill tailings impoundment driven by dry and wet cycles","authors":"Changshou Hong,&nbsp;Fubing Li,&nbsp;Kaiqi Liang,&nbsp;Chengyu Zhang,&nbsp;Shengyang Feng,&nbsp;Hong Wang,&nbsp;De Huang,&nbsp;Caiwu Luo","doi":"10.1016/j.net.2025.103755","DOIUrl":"10.1016/j.net.2025.103755","url":null,"abstract":"<div><div>The stability and reliability of earthen cover (EC) are crucial for radon treatment of uranium mill tailings (UMTs), and radon attenuation efficacy (RAE) typically serves as the key parameter for performance evolution analysis of the EC. The EC is generally exposed to a periodic meteorological environment with the characteristic of significant dry-wet cycles, therefore the evolution of RAE exhibits apparent uncertainty and unpredictability. In this study, the method of scenario analysis, on the basis of previous research findings and logical reasoning, was utilized to assess the RAE of EC evolution of a typical UMTs impoundment in China. Specifically, a scenario-based degradation model for RAE was developed by defining three core dimensions: dry and wet meteorological environments, intrinsic characteristics of EC, management practices of UMTs impoundment. The critical factors influencing the RAE were identified, and the scenario model was further validated via indoor accelerated degradation experiments. This study can provide a scientific foundation for the optimal design of EC for UMTs impoundment, as well as ensure the UMTs impoundment within effective and long-term radon attenuation performance.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103755"},"PeriodicalIF":2.6,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144481399","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":"An intelligent fault detection method for PWR-type nuclear power plants using neuro-encoder binary cells","authors":"Furqan Arshad ,&nbsp;Minjun Peng ,&nbsp;Fazle Haseeb ,&nbsp;Wasiq Ali","doi":"10.1016/j.net.2025.103735","DOIUrl":"10.1016/j.net.2025.103735","url":null,"abstract":"<div><div>In this study, a comprehensive model has been presented which is capable of fault detection and classification in the feed water heaters system of a pressurized water reactor nuclear power plant. Along with the known faults detection, this model is also capable of detecting and segregating unknown faults. In addition to this, it also has the potential for accurate classification of those fault extents which are not part of its training. This model has been developed through the combined use of auto-encoders and neural networks, called neuro-encoder binary cells, by arranging them in a cascaded manner. In total, ten different fault types have been used for its training, while ten unknown fault extents as well as five unknown fault types have been utilized for its independent testing. Additionally, this model has also been evaluated against the noisy data in order to verify its robustness. A comparison has also been presented between the performance of proposed model and other commonly used classification and anomaly detection methods.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103735"},"PeriodicalIF":2.6,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144513735","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 profiling of modern building materials: A case study of natural radionuclides in vitrified tiles from Tamil Nadu, India and their health implications","authors":"A. Chandrasekaran ,&nbsp;Ismail M.M. Rahman","doi":"10.1016/j.net.2025.103754","DOIUrl":"10.1016/j.net.2025.103754","url":null,"abstract":"<div><div>The activity concentrations of naturally occurring radioactive materials (NORM), specifically radium-226 (²²⁶Ra), thorium-232(²³²Th), and potassium-40 (⁴⁰K), in vitrified tiles widely used as modern building materials in Tamil Nadu, India, have been investigated. Since the global concern regarding radiation exposure from construction materials is increasing, a comprehensive radiological assessment was conducted to evaluate potential health hazards associated with these tiles. The analysis revealed mean activity concentrations of 68 ± 5 Bq kg⁻¹ for ²²⁶Ra, 116 ± 8 Bq kg⁻¹ for ²³²Th, and 540 ± 40 Bq kg⁻¹ for ⁴⁰K. These concentrations are notably higher than the corresponding world average values of 50 Bq kg⁻¹ for ²²⁶Ra, 50 Bq kg⁻¹ for ²³²Th, and 500 Bq kg⁻¹ for ⁴⁰K reported by UNSCEAR. Consequently, the calculated average indoor gamma absorbed dose rate of 124 nGy h⁻¹ and the estimated excess lifetime cancer risk of 2.13 × 10⁻³ mSv y⁻¹ associated with these tiles slightly exceed the global average values proposed by UNSCEAR. While the overall radiological hazard for most indices remains within acceptable international limits, these observed elevations in specific parameters highlight the importance of continued vigilance. To further understand the distribution patterns and interrelationships of these radionuclides, multivariate statistical analyses, including Pearson's correlation, hierarchical cluster analysis, and principal component analysis/factor analysis, were performed. These analyses consistently demonstrated that ²²⁶Ra and ²³²Th are the primary contributors to the calculated radiological hazard indices, as evidenced by their strong positive correlations with parameters such as radium equivalent activity, absorbed gamma dose rate, and excess lifetime cancer risk. In contrast, ⁴⁰K exhibited a distinct behavior, contributing less significantly to the potential health hazards associated with these tiles. The research findings highlight the need for region-specific radiological assessments of building materials and suggest the potential need for regulatory guidance in selecting and using raw materials for tile manufacturing to ensure public radiation safety.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103754"},"PeriodicalIF":2.6,"publicationDate":"2025-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144513586","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":"Accuracy improving research on the calibration methods of organic scintillator detectors","authors":"Linjun Hou ,&nbsp;Peng Xu ,&nbsp;Zhimeng Hu ,&nbsp;Wangtao Yu","doi":"10.1016/j.net.2025.103757","DOIUrl":"10.1016/j.net.2025.103757","url":null,"abstract":"<div><div>The calibration accuracy of the response matrix has a critical effect on the accuracy and stability of the unfolded spectra of organic scintillator neutron spectrometers. In this paper, based on the calibration of an EJ-301 liquid scintillation detector, several optimization methods were proposed to improve the calibration accuracy. For gamma calibration, the influence of different coincidence components on the peak energies of the coincidence spectra was studied using Monte Carlo simulation, and the errors introduced by treating coincidence spectra as peaks of monoenergetic electrons in traditional methods were corrected by a well-designed iterative comparison method; the effect of electronic response nonlinearity on the Monte Carlo iterative calibration method was studied and then taken into account to further improve the calibration accuracy, reducing the relative deviation of the response to 4.438 MeV γ-rays from 3.31 % to 0.61 %. For neutron calibration, the calibration method based on isotope neutron sources and the time-of-flight technique was optimized under low-count conditions using an ionization quenching model. Finally, the calibration effect was validated using a DT neutron generator, and the results demonstrated that the methods proposed in this paper can significantly improve the calibration accuracy.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103757"},"PeriodicalIF":2.6,"publicationDate":"2025-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144501262","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":"Modelling of the Compton neutron detector Hf emitter burn-up in the core of WWER-1000","authors":"Vladimir Gann ,&nbsp;Pylyp Kuznietsov ,&nbsp;Alexander Ulybkin","doi":"10.1016/j.net.2025.103756","DOIUrl":"10.1016/j.net.2025.103756","url":null,"abstract":"<div><div>The Compton emission detectors with a Hf metal emitters were examined in this study. MCNPX software was used to simulate the behavior of emitter material during 4 fuel cycles in the core of the WWER-1000 reactor. The study considered 7 detectors located along the height of the core at the positions of the standard Rh detectors currently in use. Through the simulation for 7 SPDs, it was obtained the following sets of data: detailed nuclide composition; rates of (n, γ)-reaction for main nuclides; specific neutron losses; n- and γ-fluxes distribution; the emissive current from the Hf emitter.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103756"},"PeriodicalIF":2.6,"publicationDate":"2025-06-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144491746","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}