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Proceedings Papers

Modeling and Analysis of VENUS-2 MOX Core Experiment Based on OpenMC Monte Carlo Code

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Zelong Zhao
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A001, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130363
https://doi.org/10.1115/ICONE31-130363
View Paper titled, Modeling and Analysis of VENUS-2 MOX Core Experiment Based on OpenMC Monte Carlo Code
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Topics: Cross section (Physics), Dosimetry, Flux (Metallurgy), Fuels, Modeling, Nuclear fission, Pins (Engineering), Sensors
Proceedings Papers

Simulation and Analysis of 4H-SiC-Based PiN Fast Neutron Detector With Polyethylene Converter Using Geant4

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Xiong Yanli, Qiu Xiaopeng, Liu Shuhuan, Li Zhuoqi, Liu Shuangying, Ma Yong, Song Ci, Han Ning
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A088, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92268
https://doi.org/10.1115/ICONE29-92268
View Paper titled, Simulation and Analysis of 4H-SiC-Based PiN Fast Neutron Detector With Polyethylene Converter Using Geant4
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Topics: Neutrons, Pins (Engineering), Sensors, Simulation
Proceedings Papers

Three-Dimensional Fine-Mesh Coupled Neutronics and Thermal-Hydraulics Calculation for PWR Fuel Pins

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Qiuxia Xie, Xiaojing Liu, Xiang Chai
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A056, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93140
https://doi.org/10.1115/ICONE29-93140
View Paper titled, Three-Dimensional Fine-Mesh Coupled Neutronics and Thermal-Hydraulics Calculation for PWR Fuel Pins
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Topics: Diffusion (Physics), Fuels, Neutrons, Pins (Engineering), Pressurized water reactors, Thermal hydraulics
Proceedings Papers

The Location of Spent Fuel Pins in Heavy Water Research Reactor in the Spent Fuel Pool

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Jin Lu, Peng Nie, Ren Ren, Yaping Guo, Qi Wang, Xinwang Zhang, Lijun Zhang
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91465
https://doi.org/10.1115/ICONE29-91465
View Paper titled, The Location of Spent Fuel Pins in Heavy Water Research Reactor in the Spent Fuel Pool
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Topics: Fuels, Pins (Engineering), Spent nuclear fuels, Uranium, Water
Proceedings Papers

Turbulent Flow Characteristics in a Blocked Exterior Subchannel of a Helically Wrapped Rod Bundle

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Thien Nguyen, Rodolfo Vaghetto, Yassin Hassan
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A029, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16570
https://doi.org/10.1115/ICONE2020-16570
View Paper titled, Turbulent Flow Characteristics in a Blocked Exterior Subchannel of a Helically Wrapped Rod Bundle
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Topics: Fuel rods, Turbulence, Flow (Dynamics), Fuels, Wire, Coolants, Heat transfer, Manufacturing, Cladding systems (Building), Deformation
Proceedings Papers

Multi-Dimensional Heterogeneous Resonance Integral Tables Generated for Embedded Self-Shielding Method Towards Irregular Lattices

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Qian Zhang, Qiang Zhao, Hongchun Wu, Liangzhi Cao, Zheng Zheng
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A002, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81041
https://doi.org/10.1115/ICONE26-81041
View Paper titled, Multi-Dimensional Heterogeneous Resonance Integral Tables Generated for Embedded Self-Shielding Method Towards Irregular Lattices
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Topics: Resonance, Fuels, Density, Dimensions, Pins (Engineering)
Proceedings Papers

Isogeometric Multi-Level Iterative Solution Algorithms With Applications in Nuclear Reactor Physics

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C. Latimer, J. Kópházi, M. D. Eaton
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A014, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81316
https://doi.org/10.1115/ICONE26-81316
View Paper titled, Isogeometric Multi-Level Iterative Solution Algorithms With Applications in Nuclear Reactor Physics
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Topics: Algorithms, Nuclear reactors, Physics, Diffusion (Physics), Geometry, Neutrons, Algebra, Chemical kinetics, Construction, Finite element analysis
Proceedings Papers

Turbulent Transverse Plane PIV Measurements on a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle

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Nolan E. Goth, Philip Jones, Thien D. Nguyen, Rodolfo Vaghetto, Yassin Hassan
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A043, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81462
https://doi.org/10.1115/ICONE26-81462
View Paper titled, Turbulent Transverse Plane PIV Measurements on a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle
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Topics: Fuels, Turbulence, Wire, Flow (Dynamics), Computational fluid dynamics, Sodium fast reactors, Axial flow, Cooling, Corners (Structural elements), Ducts
Proceedings Papers

Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding

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Muhammad Altahhan, Noah McFerran, Jonathan Morrell, Maria Avramova
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A031, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81464
https://doi.org/10.1115/ICONE26-81464
View Paper titled, Multiphysics Analysis of CMC Silicon Carbide and Zircaloy Cladding
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Topics: Ceramic matrix composites, Cladding systems (Building), Silicon, Fuels, Pressurized water reactors, Critical heat flux, Design, Manufacturing, Pressure, Boiling
Proceedings Papers

Post-Test CFD Analysis of Non-Uniformly Heated 19-Pin Fuel Bundle Cooled by HLM

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R. Marinari, I. Di Piazza, M. Angelucci, D. Martelli
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81307
https://doi.org/10.1115/ICONE26-81307
View Paper titled, Post-Test CFD Analysis of Non-Uniformly Heated 19-Pin Fuel Bundle Cooled by HLM
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Topics: Computational fluid dynamics, Fuels, Mixed convection, Coolants, Density, Electrical conductivity, Engineering design, Engineering prototypes, Errors, Fast neutron reactors
Proceedings Papers

Influence of Spacer Elements on Flow Distribution and Heat Transfer in Experimental Models of Fuel Assemblies

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O. Kashinsky, D. Kulikov, A. Kurdyumov, S. Lezhnin, P. Lobanov, N. Pribaturin, A. Svetonosov, J. Pacio, L. Stoppel, T. Wetzel
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A034, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82163
https://doi.org/10.1115/ICONE26-82163
View Paper titled, Influence of Spacer Elements on Flow Distribution and Heat Transfer in Experimental Models of Fuel Assemblies
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Topics: Flow (Dynamics), Fuels, Heat transfer, Coolants, Friction, Fuel rods, Geometry, Lasers, Pins (Engineering), Pipes
Proceedings Papers

Geometry Survey on the Convex Shaped Core for Recriticality Prevention Against CDA in Sodium-Cooled Fast Reactor

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Keiko Chitose, Yoshiaki Tachi, Toshio Wakabayashi, Naoyuki Takaki
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A009, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81331
https://doi.org/10.1115/ICONE26-81331
View Paper titled, Geometry Survey on the Convex Shaped Core for Recriticality Prevention Against CDA in Sodium-Cooled Fast Reactor
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Topics: Geometry, Sodium fast reactors, Fuels, Compacting, Neutrons, Coolants, Deformation, Design, Feedback, Leakage
Proceedings Papers

Experimental Tests With Non-Uniformly Heated 19-Pins Fuel Bundle Cooled by HLM

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M. Angelucci, I. Di Piazza, M. Tarantino, R. Marinari, G. Polazzi, V. Sermenghi
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A003, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81216
https://doi.org/10.1115/ICONE26-81216
View Paper titled, Experimental Tests With Non-Uniformly Heated 19-Pins Fuel Bundle Cooled by HLM
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Topics: Fuels, Pins (Engineering), Flow (Dynamics), Computational fluid dynamics, Heating, Temperature, Wire, Computation, Coolants, Heat transfer coefficients
Proceedings Papers

Characterization of FUTURIX-FTA Irradiated Nuclear Fuel Samples

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Concettina Andrello, Daniel Freis, Rosa Lo Frano, Dimitri Papaioannou, Fabienne Delage
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A040, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67252
https://doi.org/10.1115/ICONE25-67252
View Paper titled, Characterization of FUTURIX-FTA Irradiated Nuclear Fuel Samples
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Topics: Nuclear fuels, Irradiation (Radiation exposure), Fuels, Heat, Nuclear fission, Safety, Spent nuclear fuels, Uranium, Metals, Model validation
Proceedings Papers

Analytical and Experimental Study on CAP1000 Guide Tube Assembly

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Guohong Xue, Ming Zhang, Zhai Zhang, Jiaming Luan
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A002, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66014
https://doi.org/10.1115/ICONE25-66014
View Paper titled, Analytical and Experimental Study on CAP1000 Guide Tube Assembly
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Topics: Crude oil, Finite element model, Manufacturing, Modeling, Pins (Engineering), Shapes, Stiffness, Systems analysis
Proceedings Papers

Physics Design of Epi-Thermal Neutron Beam for BNCT Based on C-MNSR

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Peng Dan, Wu Xiaobo, Lu Jin, Hao Qian, Hong Jingyan, Li Yiguo
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A054, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67384
https://doi.org/10.1115/ICONE25-67384
View Paper titled, Physics Design of Epi-Thermal Neutron Beam for BNCT Based on C-MNSR
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Topics: Design, Neutron beams, Physics, Fuels, Neutrons, Cancer, Uranium, Boron, Contamination, Density
Proceedings Papers

Thermal-Hydraulic Analysis of Fuel Assembly With Inner Duct Structure of an Advanced Loop-Type Sodium-Cooled Fast Reactor Using ASFRE Code

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Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka, Hiroyuki Ohshima
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A054, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67870
https://doi.org/10.1115/ICONE25-67870
View Paper titled, Thermal-Hydraulic Analysis of Fuel Assembly With Inner Duct Structure of an Advanced Loop-Type Sodium-Cooled Fast Reactor Using ASFRE Code
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Topics: Ducts, Fuels, Manufacturing, Sodium fast reactors, Pins (Engineering), Flow (Dynamics), Temperature distribution, Design, Thermal hydraulics, Turbulence
Proceedings Papers

A Study on Hydrogen Emission of Zirconium Hydride

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Fu Xiaogang, Qin Bo, Ma Haoran, Zhang Jinquan, Long Bin
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A092, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67271
https://doi.org/10.1115/ICONE25-67271
View Paper titled, A Study on Hydrogen Emission of Zirconium Hydride
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Topics: Emissions, Hydrogen, Zirconium, High temperature, Oxygen, Pins (Engineering), Cladding systems (Building), Temperature
Proceedings Papers

CFD Pre-Test Analysis and Design of the NACIE-UP BFPS Fuel Pin Bundle Simulator

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R. Marinari, I. Di Piazza, M. Tarantino, F. Magugliani, A. Alemberti, W. Borreani, P. B. Ghionzoli
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A038, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60914
https://doi.org/10.1115/ICONE24-60914
View Paper titled, CFD Pre-Test Analysis and Design of the NACIE-UP BFPS Fuel Pin Bundle Simulator
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Topics: Computational fluid dynamics, Design, Fuels, Temperature, Fast neutron reactors, Flow (Dynamics), Manufacturing, Pins (Engineering), Safety, Engineering simulation
Proceedings Papers

Experimental Study on Critical Heat Flux in Three Pin Bundle With Wire Spacer for Boiling Water Reactor

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Sho Tanabe, Dan Tri Le, Masatoshi Kondo, Minoru Takahashi
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A073, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60997
https://doi.org/10.1115/ICONE24-60997
View Paper titled, Experimental Study on Critical Heat Flux in Three Pin Bundle With Wire Spacer for Boiling Water Reactor
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Topics: Boiling water reactors, Critical heat flux, Wire, Pins (Engineering), Flow (Dynamics), Water, Forced convection, Fuel rods, Pressure, Stainless steel