Article
Nuclear Science & Technology
Yuqi Huang, Jiejin Cai
Summary: In this paper, the authors used OpenFOAM to simulate the MATiS-H benchmark and evaluate the ability of different solvers and turbulence models to predict turbulence intensities. The results showed that the modified solver improved the predictions of downstream turbulence intensities compared to previous research.
PROGRESS IN NUCLEAR ENERGY
(2022)
Article
Engineering, Marine
Xiumao Du, Peng Yuan, Junzhe Tan, Xiancai Si, Yonghui Liu, Shujie Wang, Xianpeng Lang
Summary: This study analyzes the influence of the support structure design on the performance of a diffuser-augmented hydrodynamic turbine. Blade-resolved Computational Fluid Dynamics (CFD) numerical simulations are used to analyze the effects of parameters such as support distance, the number of columns, and the aspect ratio of the support structure. The results show that support structures can significantly reduce the acceleration ratio and power coefficient of the turbine.
Article
Nuclear Science & Technology
Hongyang Wei, Victor Quintanilla, Yitung Chen, Peiyao Qi, Xing Li, Shouxu Qiao, Sichao Tan
Summary: This research conducted numerical simulation and analysis of flow behavior in a 5 x 5 fuel rod bundle with consideration of spacer grid. The findings showed that the spacer grid can cause complex flow behavior in the fuel rod bundle.
ANNALS OF NUCLEAR ENERGY
(2021)
Review
Nuclear Science & Technology
Gaurav Kumar, Raj Kumar Singh
Summary: This review article provides a comprehensive understanding of the heat transfer features of supercritical water in tubes with wire-wrapped rod bundles. It discusses the effects of supercritical pressure, thermo-physical properties of water, and relevant parametric effects on heat transfer performance. The challenges of turbulence models and the simulation of buoyancy and turbulent heat flux are highlighted.
PROGRESS IN NUCLEAR ENERGY
(2023)
Article
Engineering, Marine
Sen Qu, Huilong Ren, Shengnan Liu, Shuzheng Sun, Muk Chen Ong
Summary: The numerical study of breaking waves interaction with two tandem cylinders using CFD software reveals the impact of transverse inclined angles and separation distances on breaking wave loads and free surface elevations. The VOF method is used to capture the air-water interface and the SST k - omega turbulence model is employed to solve the RANS equations.
SHIPS AND OFFSHORE STRUCTURES
(2022)
Article
Thermodynamics
S. Kumar Saha, N. Nandi
Summary: The study simulated the turbulent flow characteristics through a 90 degrees pipe bend using a numerical method and found that turbulent intensity is larger on the inner wall curvature side. The position of guide vane and bend curvature ratio significantly affect turbulence characteristics, while wall shear stress at the bend outlet is more dependent on circumferential angle and curvature ratio rather than Reynolds number and guide vane positions.
JOURNAL OF APPLIED FLUID MECHANICS
(2021)
Article
Mechanics
Craig Menezes, Trevor Melsheimer, Yassin A. A. Hassan
Summary: This study investigates flow phenomena in a liquid metal fast reactor fuel assembly using 3D printed asymmetric honeycomb spacer grids. Time-resolved particle image velocimetry was employed to obtain non-intrusive velocity measurements and statistical analysis of flow dynamics. The results are crucial for reactor design, geometry optimization, and validation of computational fluid dynamics and reduced-order flow models.
Article
Nuclear Science & Technology
Peiyao Qi, Chuangao Han, Chen Ma, Ruixiang Zhang, Feng Liu, Sichao Tan
Summary: Using the PIV technique, this study examines the flow field and turbulence statistics in a 5x5 rod bundle across different Reynolds numbers. The results show that the relative velocity distribution becomes more uniform as the Reynolds number increases. The turbulence intensity is higher in the gap subchannel compared to the inner subchannel, indicating that tightly arranged rods generate higher turbulence intensity.
ANNALS OF NUCLEAR ENERGY
(2023)
Article
Thermodynamics
Nishchay Tiwari, Pawel Flaszynski, Thanushree Suresh, Oskar Szulc
Summary: The effects of rod-type and vane-type vortex generators on wind turbine applications are investigated and compared. Computational fluid dynamics (CFD) is used to assess the benefits of using rod-type vortex generators to control flow separation on wind turbine airfoils. The comparison shows that rod-type vortex generators can be an alternative to conventional vane-type vortex generators for boundary layer separation control on wind turbine blades.
INTERNATIONAL JOURNAL OF NUMERICAL METHODS FOR HEAT & FLUID FLOW
(2023)
Article
Thermodynamics
Quan-Yao Ren, Liang-Ming Pan, Zengping Pu, Fawen Zhu, Hui He
Summary: Experimental study shows that the mixing vane spacer grid has a significant impact on the phase distribution and parameters of two-group air-water flow in rod bundle channel, exhibiting specific void fraction profiles and influencing regions.
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
(2021)
Article
Computer Science, Interdisciplinary Applications
Pratikkumar Raje, Krishnendu Sinha
Summary: The article discusses the limitations of the Menter SST k-omega turbulence model and proposes the SUQ-SST model as an improvement. The new model significantly improves predicting Reynolds stress anisotropy, flow separation, and surface properties.
COMPUTERS & FLUIDS
(2021)
Article
Engineering, Civil
Antonio J. Alvarez, Nelix Nieto, Kenny K. C. S. Kwok, Santiago Hernandez
Summary: A 2D URANS approach was used to numerically simulate the effects of free stream turbulence on bluff bodies, and the results showed good agreement with experimental data. This method can be used affordably to study aerodynamics problems related to free stream turbulence in wind engineering.
JOURNAL OF WIND ENGINEERING AND INDUSTRIAL AERODYNAMICS
(2023)
Article
Nuclear Science & Technology
Bin Han, Xiaoliang Zhu, Bao-Wen Yang, Aiguo Liu, Yanyan Xi, Lei Liu, Shenghui Liu, Junlin Huang
Summary: This paper introduces the importance of Mixing Vane Grid (MVG) in fuel assembly and how to evaluate its mixing performance. The CFD method was used for TDC analysis, and the effects of boundary conditions and geometric factors on mixing performance were studied.
NUCLEAR ENGINEERING AND TECHNOLOGY
(2023)
Article
Mechanics
Veeresh Tekure, K. Venkatasubbaiah
Summary: Numerical study of conjugate heat transfer in supersonic turbulent flow over a flat plate with finite thickness shows lower interface temperature and fluid temperature variation compared to non-conjugate heat transfer analysis. Results indicate significant increase in interface temperature for low thermal conductivity plate materials, and negligible effect of plate thickness on flow field temperature variation. Additionally, the maximum interface temperature increases with plate thickness.
EUROPEAN JOURNAL OF MECHANICS B-FLUIDS
(2021)
Article
Engineering, Multidisciplinary
Guang Yin, Muk Chen Ong, Puyang Zhang
Summary: Flow conditioners are used in pipeline systems for the offshore and subsea oil and gas industry to improve flow rate measurement accuracy. However, there is a lack of knowledge about the influence of these conditioners on flow inside a bend pipe due to measurement inaccuracy caused by complex geometries. In this study, numerical simulations are performed to investigate flow characteristics inside a double bend pipe and the performance of a conditioner with a bundle of 19 tubes. The results show that helical flow structures behind the double bend can be effectively eliminated by the flow conditioner. The performance of the conditioner is evaluated based on axial flow velocity profiles, swirl intensities, and deviation from flow in a straight pipe, and the effects of Reynolds numbers and tube bundle lengths on flow downstream the conditioner are discussed.
ENGINEERING APPLICATIONS OF COMPUTATIONAL FLUID MECHANICS
(2023)
Article
Nuclear Science & Technology
T. J. Chuang, Y. M. Ferng
ANNALS OF NUCLEAR ENERGY
(2016)
Article
Thermodynamics
C. H. Lin, M. S. Chen, Y. M. Ferng
APPLIED THERMAL ENGINEERING
(2016)
Article
Thermodynamics
G. Y. Chuang, Y. M. Ferng
INTERNATIONAL JOURNAL OF THERMAL SCIENCES
(2018)
Article
Thermodynamics
Y. Wang, Y. M. Ferng, L. X. Sun
APPLIED THERMAL ENGINEERING
(2019)
Article
Thermodynamics
Y. H. Chang, Y. M. Ferng
APPLIED THERMAL ENGINEERING
(2019)
Article
Engineering, Multidisciplinary
Pin-Chiun Huang, Hsoung-Wei Chou, Yuh-Ming Ferng, Chin-Hsiang Kang
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING
(2020)
Article
Thermodynamics
T. J. Chuang, Y. H. Chang, Y. M. Ferng
APPLIED THERMAL ENGINEERING
(2019)
Article
Agriculture, Multidisciplinary
Yu Xie, YuhMing Ferng, J. Miao, Jinbo Ren, Xiang Zhang
COMPUTERS AND ELECTRONICS IN AGRICULTURE
(2020)
Article
Nuclear Science & Technology
Hsoung-Wei Chou, Chin-Cheng Huang, Pin-Chiun Huang, Yuh-Ming Ferng
NUCLEAR TECHNOLOGY
(2020)
Article
Nuclear Science & Technology
Hsoung-Wei Chou, Pin-Chiun Huang, Yuh-Ming Ferng
Summary: The study utilizes Bayesian inference to develop posterior vessel-specific flaw distributions for RPVs, and investigates how updated flaw models impact the fracture probability assessment through PFM analysis. By considering updated flaws based on inspection data, the PFM analysis results could provide a more realistic prediction of fracture risks for RPVs during operation.
NUCLEAR TECHNOLOGY
(2021)
Article
Nuclear Science & Technology
J. R. Wang, P. C. Huang, Y. M. Ferng
ANNALS OF NUCLEAR ENERGY
(2020)
Article
Nuclear Science & Technology
C. Y. Hsu, Y. M. Ferng
Summary: This study experimentally investigated the bubble characteristics for a bubbly upflow in an annular channel, including void fraction, interfacial area concentration, and bubble size. A simplified two-phase frictional pressure-drop model was proposed and showed good agreement with the measured data, with a deviation within 40%. The study provides insights into bubble dynamics and can help develop and assess CFD two-phase models.
ANNALS OF NUCLEAR ENERGY
(2021)
Proceedings Paper
Engineering, Manufacturing
Pin-Chiun Huang, Hsoung-Wei Chou, Yuh-Ming Ferng
PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 6A
(2019)
Article
Thermodynamics
G. Y. Chuang, Y. M. Ferng
APPLIED THERMAL ENGINEERING
(2017)
Article
Thermodynamics
T. J. Chuang, J. W. Chen, Y. M. Ferng
APPLIED THERMAL ENGINEERING
(2017)
Article
Nuclear Science & Technology
Kecheng Jiang, Jinzhao Yang, Xueli Zhao, Lei Chen, Fujun Gou, Songlin Liu
Summary: The blanket, as a key component of the fusion reactor, plays important roles in breeding tritium, shielding neutrons, and extracting thermal energy for electricity generation. Understanding the characteristics of gas-liquid two-phase flow and mass transfer is essential for optimizing the design of tritium extraction units in the blanket.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Anna-Elina Pasi, Teemu Karkela, Fredrik Borjesson Sanden, Unto Tapper, Tuula Kajolinna, Christian Ekberg
Summary: This study investigates the gas-phase interactions between tellurium and organic material under severe nuclear accident conditions. The results show that there is interaction between tellurium aerosols and organic material, leading to an increase in the gaseous fraction and changes in XPS spectra. Although the exact species are not identified, these findings raise questions about the behavior of tellurium and its reactions with organic material in severe accident conditions.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Ao Zhang, Qingye Li, Chaoyong Zong, Fuwen Liu, Tianhang Xue, Jian Xiao, Xueguan Song
Summary: In this study, a high-fidelity computational fluid dynamics model was established to investigate the flow characteristics of a novel balanced globe valve. The study found that the size of the throttle orifice and valve disc displacement have a significant impact on fluid force. The findings provide a basis for the design and dynamic control of globe valves, and also have potential value for energy utilization.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Wenbo Li, Yunqing Bai, Shuai Zhang, Yang Li, Ming Jin, Chunjing Li
Summary: In this study, a 3D-CFD model based on the SUPERCAVNA facility was established to analyze thermal stratification in liquid-metal-cooled nuclear reactors. The results show that the SKE model is the most accurate in predicting temperature distribution, and further parametric studies were conducted.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Song Jin, Di Jiang, Dongmei Wang, Shaojie Wang, Zhen Wang
Summary: This study presents the fragility evaluation of a nuclear containment structure subjected to earthquake and subsequent internal pressure sequence. Nonlinear finite element model and ground motion records are used to analyze the nonlinear response and fragility of the structure. Results show that the distribution of maximum strain and displacement of the structure under earthquake and subsequent pressure are significantly different, with displacement distribution related to ground motion intensity levels.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Kazumasa Shimada, Tatsuya Sakurahara, Pegah Farshadmanesh, Seyed Reihani, Zahra Mohaghegh
Summary: This research improves the realism of Level 3 probabilistic risk assessment for nuclear power plants by modeling the evacuation behavior of residents and incorporating two advancements. The first advancement uses evacuation speed from a transportation simulation code as input to the Level 3 PRA code, enabling explicit incorporation of spatiotemporal evacuation processes. The second advancement incorporates the probability of seismic damage to roadway bridges into Level 3 PRA and calculates evacuation routes and speeds considering the impact of seismic damage.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
F. Mascari, A. Bersano, M. Massone, G. Agnello, O. Coindreau, S. Beck, L. Tiborcz, S. Paci, M. Angelucci, L. E. Herranz, R. Bocanegra, Y. Pontillon, M. Berdai, O. Cherednichenko, A. Iskra, M. Nudi, P. Groudev, P. Petrova, F. Kretzschmar, F. Gabrielli, Z. Kanglong, V. Vileiniskis, T. Kaliatka, J. Kalilainen, M. Malicki, D. Gumenyuk, Y. Vorobyov, O. Kotsuba, P. Dejardin, M. Di Giuli, R. Thomas, I. V. Ivanov, F. Giannetti, M. D'Onorio, G. Caruso, M. Salay, T. Sevon
Summary: The MUSA project aims to analyze uncertainties and sensitivities associated with severe accidents using a harmonized approach, particularly focusing on source term figures of merit. The project applied and tested uncertainty quantification methodologies using the PHEBUS FPT1 test. The study found that scripting for coupling SA codes and uncertainty tools can increase flexibility, and careful consideration should be given to selecting the input uncertain parameters.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Ian Greenquist, Nathan Capps
Summary: The US nuclear energy industry is investigating strategies to increase reactor operating cycle to 24 months. Multiphysics simulations tools and methodologies are being developed to predict the effects of this change during transient events such as loss-of-coolant accidents (LOCAs).
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Guangchun Zhang, Hu Zhang
Summary: In this study, a neutron transport code called TARS is introduced, which is based on the discrete-ordinates discontinuous finite element method. TARS provides accurate and efficient solutions to the neutron transport equation, addressing existing challenges in the field. The evaluation results demonstrate that TARS generates highly accurate solutions and achieves high parallel computation efficiency.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
J. R. Daniels, M. M. R. Williams, M. D. Eaton
Summary: This paper presents the development and verification of a collision probability (CP) code for neutron transport in slabs and cylinders. The CP code is particularly useful for modelling layered systems of aqueous and organic plutonium nitrate. The code provides a computationally inexpensive alternative to higher fidelity codes like MCNP. It is effective for slab geometries with at least 0.7 g cm-2 plutonium, but its approximation for heterogeneous cylinders can lead to overestimation of neutron leakage. Increasing the cylinder radius to 40.0 cm improves the accuracy for systems with at least 2.75 kg plutonium. However, the code's accuracy decreases when modelling cylindrical geometries with dished ends and low plutonium content.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Alexander A. Ryzhkov, Georgy V. Tikhomirov, Mikhail Yu. Ternovykh
Summary: This paper analyzes the impact of nuclear data uncertainties on the safety of advanced reactors, with a specific focus on angular distribution uncertainties. Through sensitivity and uncertainty analysis, key parameters for MOX3600 are identified, and a comparison of different libraries' uncertainties on the eigenvalue is performed.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
Y. Fontenla, A. Vidal-Ferrandiz, A. Carreno, D. Ginestar, G. Verdu
Summary: FEMFFUSION is an open source code that solves the multigroup neutron transport equation using the diffusion and the SPN approximations. It uses the finite element method to handle various geometries and problem dimensions, and has been verified against the C5G7 benchmark.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
J. Tyler Gates, Pavel V. Tsvetkov
Summary: The Optical Fiber Based Gamma Thermometer utilizes optical fiber as a distributed temperature sensor to measure the temperature of a thermal mass undergoing gamma heating and calculate the gamma flux data. This technology shows promise in determining the local power density within a nuclear reactor core and provides an unparalleled level of precision in reactor power measurement.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
A. de Lara, A. Schubert, E. Shwageraus, P. Van Uffelen
Summary: This study presents a new methodology to derive the radial form factor in the TRANSURANUS burnup model using simulations. The proposed methodology can be applied to different types of reactors, including LWRs and HWRs, and is suitable for advanced technology fuels.
ANNALS OF NUCLEAR ENERGY
(2024)
Article
Nuclear Science & Technology
A. Bousbia Salah, M. Di Giuli, P. Foucaud, R. Iglesias, A. Malkhasyan, M. Salmaoui, L. E. Herranz
Summary: In the framework of the R2CA project, the application of advanced codes for evaluating radiological release under design basis accidents was considered. The study focused on a specific scenario and assessed the results obtained by different organizations using different computational tools and approaches. The outcomes highlighted modeling differences and challenges in carrying out such analysis.
ANNALS OF NUCLEAR ENERGY
(2024)
