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2014 22nd International Conference on Nuclear Engineering

July 7–11, 2014

Prague, Czech Republic

Conference Sponsors:

ISBN:

978-0-7918-4594-3

In This Volume

Radiation Protection and Nuclear Technology Applications (3)
Fuel Cycle, Radioactive Waste Management and Decommissioning (23)
Computational Fluid Dynamics (CFD) and Coupled Codes (51)
Reactor Physics and Transport Theory (15)

Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory

Radiation Protection and Nuclear Technology Applications

The Research of Suitable Collimator Used in Gamma Scanning System

Nan Qian, Dezhong Wang, Weiguo Gu, Yuanwei Ma

ICONE 2014; V004T04A001https://doi.org/10.1115/ICONE22-30550

Abstract

View Articletitled, The Research of Suitable Collimator Used in Gamma Scanning System

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Topics: Experimental design , Shapes

Design and Development of Virtual Assembly Prototype System for CLEAR-I

Leiming Shang, Zihui Yang, Jinbo Zhao, Tao He, Liqin Hu

ICONE 2014; V004T04A002https://doi.org/10.1115/ICONE22-30752

Abstract

View Articletitled, Design and Development of Virtual Assembly Prototype System for CLEAR-I

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Topics: Design , Engineering prototypes , Virtual assembly , Simulation , Virtual reality , China , Computer-aided design , Ergonomics , Manufacturing , Modeling

Verification for Ray Effects Elimination Module of Radiation Shielding Code ARES by Kobayashi Benchmarks

Mengteng Chen, Bin Zhang, Yixue Chen

ICONE 2014; V004T04A003https://doi.org/10.1115/ICONE22-31196

Abstract

View Articletitled, Verification for Ray Effects Elimination Module of Radiation Shielding Code ARES by Kobayashi Benchmarks

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Topics: Radiation (Physics) , Collisions (Physics) , Electromagnetic scattering , Radiation scattering , Scattering (Physics) , Anisotropy , Flux (Metallurgy) , Neutrons , Ray tracing

Fuel Cycle, Radioactive Waste Management and Decommissioning

Interim Storage of Spent Nuclear Fuel in the UAE Nuclear Power Plants

Sara Al Saadi, Yongsun Yi

ICONE 2014; V004T08A001https://doi.org/10.1115/ICONE22-30081

Abstract

View Articletitled, Interim Storage of Spent Nuclear Fuel in the UAE Nuclear Power Plants

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Topics: Nuclear power stations , Spent nuclear fuels , Storage , Cooling , Construction , Cycles , Natural convection , Safety , Stress corrosion cracking , Temperature

Stress Concentration Factor Calculation for the Hooks in Lifting Appliance of Spent Fuel Well Cover

Xiang Liu, Yue Li, Jinhua Wang, Bin Wu

ICONE 2014; V004T08A002https://doi.org/10.1115/ICONE22-30272

Abstract

View Articletitled, Stress Concentration Factor Calculation for the Hooks in Lifting Appliance of Spent Fuel Well Cover

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Topics: Spent nuclear fuels , Stress concentration , Corners (Structural elements) , Fatigue life , Finite element methods , High temperature , Numerical analysis , Saint-Venant's principle , Wells

Adsorption Properties of Sr(II) on Zeolite Type Adsorbents and Their Irradiation Stabilities

Hitoshi Mimura, Shunsuke Susa, Yoshiyuki Ito, Yasuo Saito, Minoru Matsukura

ICONE 2014; V004T08A003https://doi.org/10.1115/ICONE22-30329

Abstract

View Articletitled, Adsorption Properties of Sr(II) on Zeolite Type Adsorbents and Their Irradiation Stabilities

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Topics: Irradiation (Radiation exposure) , Flow (Dynamics) , Radioactive wastes , Equilibrium (Physics) , Ions , Optimization , Particle size , Sodium

Decreasing Waste of Laser Cutting by Metal Fume Capturing With Water

Itaru Chida, Katsunori Shiihara, Kota Nomura, Rie Sumiya, Naotaka Suganuma

ICONE 2014; V004T08A004https://doi.org/10.1115/ICONE22-30337

Abstract

View Articletitled, Decreasing Waste of Laser Cutting by Metal Fume Capturing With Water

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Topics: Laser cutting , Metals , Water , Cutting , Stainless steel , Lasers , Machining , Nuclear decommissioning , Nuclear reactors , Radioactive wastes

Application of Ultrasonic Technique for Precipitate Detection and Viscosity Measurement of Molten Glass at Elevated Temperature

Midori Uchiyama, Arisa Yanagihara, Hajime Koikegami, Hiroaki Hatanaka, Tadashi Maruyama

ICONE 2014; V004T08A005https://doi.org/10.1115/ICONE22-30360

Abstract

View Articletitled, Application of Ultrasonic Technique for Precipitate Detection and Viscosity Measurement of Molten Glass at Elevated Temperature

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Topics: Glass , Temperature , Viscosity measurement , Waveguides , Alloys , Corrosion , Density , Graphite , Nickel , Ultrasound

Safety Evaluation of KAERI Pyroprocess Facilities

G. S. You, W. M. Choung, J. H. Ku, S. I. Moon, H. D. Kim

ICONE 2014; V004T08A006https://doi.org/10.1115/ICONE22-30363

Abstract

View Articletitled, Safety Evaluation of KAERI Pyroprocess Facilities

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Topics: Safety , Design , Evaluation methods , Nuclear power , Spent nuclear fuels

A Double Porosity Model to Describe Both Permeability Change and Dissolution Processes

Yuichi Niibori, Hideo Usui, Taiji Chida, Hitoshi Mimura

ICONE 2014; V004T08A007https://doi.org/10.1115/ICONE22-30481

Abstract

View Articletitled, A Double Porosity Model to Describe Both Permeability Change and Dissolution Processes

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Topics: Permeability , Porosity , Particulate matter , Diffusion (Physics) , Ions , Cements (Adhesives) , Diffusion processes , Fittings , Flow (Dynamics) , Groundwater

The Treatment of Low-Level Radioactive Wastewater by the Nuclear Weapons Using Ultrasonic Standing Wave Methods

Suxia Hou, Jijun Luo, Bin He, Jun Xu, Rusong Li

ICONE 2014; V004T08A008https://doi.org/10.1115/ICONE22-30532

Abstract

View Articletitled, The Treatment of Low-Level Radioactive Wastewater by the Nuclear Weapons Using Ultrasonic Standing Wave Methods

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Topics: Nuclear weapons , Sewage , Standing waves , Particulate matter , Decontamination , Radioactive wastes , Ultrasound , Contamination , Hazards , Radiation (Physics)

Safety Requirements for Engineering Scale Pyroprocess Demonstration Facility

Seong-In Moon, Won-Myung Chong, Gil-Sung You, Jeong-Hoe Ku, Ho-Dong Kim

ICONE 2014; V004T08A009https://doi.org/10.1115/ICONE22-30637

Abstract

View Articletitled, Safety Requirements for Engineering Scale Pyroprocess Demonstration Facility

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Topics: Safety , Hazards , Accidents , Design , Conceptual design , Nuclear fuel cycle , Nuclear power , Risk , Spent nuclear fuels

Optimization of Chemical Composition in the Iron Phosphate Glass as the Matrix of High Level Waste Generated From Pyroprocessing

Hirohide Kofuji, Tetsuji Yano, Munetaka Myochin, Kanae Matsuyama, Takeshi Okita, Shinya Miyamoto

ICONE 2014; V004T08A010https://doi.org/10.1115/ICONE22-30688

Abstract

View Articletitled, Optimization of Chemical Composition in the Iron Phosphate Glass as the Matrix of High Level Waste Generated From Pyroprocessing

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Topics: Glass , Iron , Optimization , Durability , Electrolytes , Industrial research , Radioactive waste disposal , Radioactive wastes , Transition metals

Development of Glass Melter Technology for HLLW Vitrification in Japan

Akira Sakai, Hajime Koikegami, Nobuyuki Miura, Eiji Ochi

ICONE 2014; V004T08A011https://doi.org/10.1115/ICONE22-30693

Abstract

View Articletitled, Development of Glass Melter Technology for HLLW Vitrification in Japan

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Topics: Glass , Vitrification , Metals , Design , Testing , Ceramics , Glassmaking , Joules , Precipitation , Process design

Modeling of Cladding Thermal Evolution Along Cask Storage

Jaime E. Penalva, Francisco Feria, Luis E. Herranz

ICONE 2014; V004T08A012https://doi.org/10.1115/ICONE22-30758

Abstract

View Articletitled, Modeling of Cladding Thermal Evolution Along Cask Storage

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Topics: Cladding systems (Building) , Modeling , Storage , Temperature , Fuel rods , Equipment performance , Thermal characterization , Arches , Creep , Embrittlement

Feasibility Study on Direct Waste Salt Disposition Through Measurement and Analysis of Salt Bead Dissolutions in Aqueous Solvents

Michael Shaltry, Supathorn Phongikaroon

ICONE 2014; V004T08A013https://doi.org/10.1115/ICONE22-30841

Abstract

View Articletitled, Feasibility Study on Direct Waste Salt Disposition Through Measurement and Analysis of Salt Bead Dissolutions in Aqueous Solvents

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Topics: Ceramics , Modeling , Water

Decommissioning Combustible Waste Treatment Using Oxygen-Enriched Incinerator

Byung Youn Min, Yoon Ji Lee, Gyoung Su Yun, Ki Won Lee, Jae Kwon Moon

ICONE 2014; V004T08A014https://doi.org/10.1115/ICONE22-30855

Abstract

View Articletitled, Decommissioning Combustible Waste Treatment Using Oxygen-Enriched Incinerator

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Topics: Incinerators , Nuclear decommissioning , Oxygen , Waste treatment , Carbon dioxide , Clearances (Engineering) , Nitrogen oxides , Pressure , Temperature

The Implementing Geological Disposal Technology Platform: Key Challenges in Research and Development in Radioactive Waste Management

Jacques Delay, Jiri Slovak, Raymond Kowe

ICONE 2014; V004T08A015https://doi.org/10.1115/ICONE22-30962

Abstract

View Articletitled, The Implementing Geological Disposal Technology Platform: Key Challenges in Research and Development in Radioactive Waste Management

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Topics: Industrial research , Radioactive wastes , Radiological dispersal devices , Safety , Spent nuclear fuels , Vehicles , Waste management

Spent Fuel Canister Criticality Safety Calculation in Groundwater Immersion Accident

Siyuan Wu, Bo Yang, Hexi Wu, Qianglin Wei, Yibao Liu

ICONE 2014; V004T08A016https://doi.org/10.1115/ICONE22-30978

Abstract

View Articletitled, Spent Fuel Canister Criticality Safety Calculation in Groundwater Immersion Accident

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Topics: Accidents , Groundwater , Safety , Spent nuclear fuels , Computer software , Computers , Isotopes , Pressurized water reactors

Shipment of Spent Nuclear Fuel From the Czech Republic for Reprocessing

Josef Podlaha

ICONE 2014; V004T08A017https://doi.org/10.1115/ICONE22-31003

Abstract

View Articletitled, Shipment of Spent Nuclear Fuel From the Czech Republic for Reprocessing

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Topics: Spent nuclear fuels , Nuclear fuels , Nuclear power , Radioactive wastes , Sealing (Process) , Transport packages

Modelling of RBMK Spent Nuclear Fuel Characteristics

Arturas Smaizys, Povilas Poskas, Ernestas Narkunas

ICONE 2014; V004T08A018https://doi.org/10.1115/ICONE22-31005

Abstract

View Articletitled, Modelling of RBMK Spent Nuclear Fuel Characteristics

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Topics: Modeling , Spent nuclear fuels , Fuels , Radioisotopes , Evaluation methods , Heat , Neutron sources , Nuclear fission , Nuclear power stations , Safety

Scenario Analysis on the Benefits of Multi-National Cooperation for the Development of a Common Nuclear Energy System Based on PWR and LFR Fleets

Marco Ciotti, Jorge L. Manzano, Vladimir Kuznetsov, Galina Fesenko, Luisa Ferroni, Fabio Giannetti

ICONE 2014; V004T08A019https://doi.org/10.1115/ICONE22-31012

Abstract

View Articletitled, Scenario Analysis on the Benefits of Multi-National Cooperation for the Development of a Common Nuclear Energy System Based on PWR and LFR Fleets

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Topics: Nuclear power , Pressurized water reactors , Nuclear power stations , Nuclear fuel cycle , Stress , Uranium , Carbon , Carbon dioxide , Cycles , Dimensions

Ageing Management of Dry Storage Systems for Long-Term Storage

Justo Garcia, Hervé Issard

ICONE 2014; V004T08A020https://doi.org/10.1115/ICONE22-31118

Abstract

View Articletitled, Ageing Management of Dry Storage Systems for Long-Term Storage

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Topics: Storage , Nuclear fuels , Safety , Nuclear reactors , Accidents , Containers , Delays , Feedback , Nuclear fuel cycle , Transportation systems

Decommissioning of Obsolete Nuclear Facilities in the UJV Rez, a. s.

Milan Tous, Josef Podlaha

ICONE 2014; V004T08A021https://doi.org/10.1115/ICONE22-31155

Abstract

View Articletitled, Decommissioning of Obsolete Nuclear Facilities in the UJV Rez, a. s.

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Topics: Nuclear decommissioning , Nuclear power stations , Blasting , Decontamination , Ice , Nuclear research , Radioactive wastes , Water

ÚJV Řež, a.s. Research Programme Supporting Development of Deep Geological Repository in the Czech Republic

Václava Havlová

ICONE 2014; V004T08A022https://doi.org/10.1115/ICONE22-31177

Abstract

View Articletitled, ÚJV Řež, a.s. Research Programme Supporting Development of Deep Geological Repository in the Czech Republic

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Topics: Heat , Radioactive wastes , Rocks , Safety

Mechanical Stresses Affecting Deep Borehole Disposal of High Level Nuclear Waste

Ethan A. Bates, Jacopo Buongiorno, Emilio Baglietto, Michael J. Driscoll

ICONE 2014; V004T08A023https://doi.org/10.1115/ICONE22-31259

Abstract

View Articletitled, Mechanical Stresses Affecting Deep Borehole Disposal of High Level Nuclear Waste

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Topics: Radioactive wastes , Stress , Rocks , Density , Drilling , Compressive strength , Critical points (Physics) , Reservoirs , Stability , Temperature

Computational Fluid Dynamics (CFD) and Coupled Codes

Multi-Group Two-Phase Flow Model of Drift Drop Plume

Vladimir M. Agranat, Sergei V. Zhubrin, Igor Pioro

ICONE 2014; V004T10A001https://doi.org/10.1115/ICONE22-30010

Abstract

View Articletitled, Multi-Group Two-Phase Flow Model of Drift Drop Plume

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Topics: Plumes (Fluid dynamics) , Two-phase flow , Computational fluid dynamics , Water , Cooling towers , Flux (Metallurgy) , Drops , Errors , Kinetic energy , Turbulence

RANS and LES Analyses on a Density Stratified Layer Behavior of Multicomponent Gas by Buoyant Jet in a Small Vessel

Satoshi Abe, Masahiro Ishigaki, Yasuteru Sibamoto, Taisuke Yonomoto

ICONE 2014; V004T10A002https://doi.org/10.1115/ICONE22-30020

Abstract

View Articletitled, RANS and LES Analyses on a Density Stratified Layer Behavior of Multicomponent Gas by Buoyant Jet in a Small Vessel

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Topics: Density , Reynolds-averaged Navier–Stokes equations , Vessels , Erosion , Turbulence , Computational fluid dynamics , Containment vessels , Accidents , Damping , Gases

Application of Some Turbulence Models to Simulate Buoyancy-Driven Flow

Aniseh A. A. Abdalla, Jiyang Yu, Mohammad Alrwashdeh

ICONE 2014; V004T10A003https://doi.org/10.1115/ICONE22-30060

Abstract

View Articletitled, Application of Some Turbulence Models to Simulate Buoyancy-Driven Flow

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Topics: Buoyancy , Flow (Dynamics) , Turbulence , Accidents , Containment , Hydrogen , Nuclear power stations , Combustion , Explosions , Computation

Research on Nodal Expansion Method for Transient Convection Diffusion Equation

Xiafeng Zhou, Fu Li

ICONE 2014; V004T10A004https://doi.org/10.1115/ICONE22-30074

Abstract

View Articletitled, Research on Nodal Expansion Method for Transient Convection Diffusion Equation

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Topics: Convection , Diffusion (Physics) , Transients (Dynamics) , Finite difference methods , Neutrons , Error analysis , Finite volume methods , Physics

Numerical Simulation of Steam Generator Tube Rupture Sequence in ADS Reactor

Xu Yang, Tao Zhou, Daping Lin, Xiaolu Fang, Baixu Chen, Xiaolong Ru

ICONE 2014; V004T10A005https://doi.org/10.1115/ICONE22-30187

Abstract

View Articletitled, Numerical Simulation of Steam Generator Tube Rupture Sequence in ADS Reactor

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Topics: Boilers , Computer simulation , Rupture , Steam , Coolants , Flow (Dynamics) , Particulate matter , Accidents , Corrosion , Safety

Numerical Analysis of the Residual Heat Removal for the Spent Fuel Canister of HTR-PM in Fuel Loading Process

Jinhua Wang, Bing Wang, Bin Wu

ICONE 2014; V004T10A006https://doi.org/10.1115/ICONE22-30284

Abstract

View Articletitled, Numerical Analysis of the Residual Heat Removal for the Spent Fuel Canister of HTR-PM in Fuel Loading Process

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Topics: Fuels , Heat , Numerical analysis , Spent nuclear fuels , Temperature , Ventilation , Accidents , Safety , Boron , Failure

Numerical Simulation of Thermal Behavior of a Molten Droplet Covered With Vapor Film

Mingjun Zhong, Meng Lin, Jinbiao Xiong, Yankai Li, Yanhua Yang

ICONE 2014; V004T10A007https://doi.org/10.1115/ICONE22-30293

Abstract

View Articletitled, Numerical Simulation of Thermal Behavior of a Molten Droplet Covered With Vapor Film

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Topics: Computer simulation , Drops , Vapors , Cavities , Density , Film thickness , Fluids , Fuels , Heat transfer , High temperature

Numerical Investigation on Heat Removal Capacity of Passive Residual Heat Removal Heat Exchanger

Wenwen Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su

ICONE 2014; V004T10A008https://doi.org/10.1115/ICONE22-30302

Abstract

View Articletitled, Numerical Investigation on Heat Removal Capacity of Passive Residual Heat Removal Heat Exchanger

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Topics: Heat , Heat exchangers , Heat transfer , Fluids , Temperature , Computational fluid dynamics , Porous materials , Thermal hydraulics , Water temperature , Containment

Validation of a New Method for Solving of CFD Problems in Nuclear Engineering Using Petascale HPC

Vladimir Chudanov, Anna Aksenova, Sergey Goreinov, Artem Makarevich, Valerii Pervichko

ICONE 2014; V004T10A009https://doi.org/10.1115/ICONE22-30311

Abstract

View Articletitled, Validation of a New Method for Solving of CFD Problems in Nuclear Engineering Using Petascale HPC

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Topics: Computational fluid dynamics , Nuclear engineering

Investigating the Natural Convection Behavior in the Transportable Storage Canister of Dry Storage Systems Through CFD Simulation

Yung-Shin Tseng, Chun-Yu Chen, Yuh-Ming Ferng, Chunkuan Shih

ICONE 2014; V004T10A010https://doi.org/10.1115/ICONE22-30330

Abstract

View Articletitled, Investigating the Natural Convection Behavior in the Transportable Storage Canister of Dry Storage Systems Through CFD Simulation

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Topics: Computational fluid dynamics , Natural convection , Simulation , Storage , Accidents , Leakage , Design , Safety , Shells , Temperature

CFD Analysis of Subcooled Wall Boiling at Shell Side of Steam Generator With TSP

Chenglong Wang, Dalin Zhang, Suizheng Qiu, Wenxi Tian, Guanghui Su

ICONE 2014; V004T10A011https://doi.org/10.1115/ICONE22-30334

Abstract

View Articletitled, CFD Analysis of Subcooled Wall Boiling at Shell Side of Steam Generator With TSP

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Topics: Boilers , Boiling , Computational fluid dynamics , Shells , Subcooling , Computer simulation , Heat transfer , Design , Flow (Dynamics) , Nucleate boiling

Numerical Simulation of Two-Phase Flows Using 3D-VOSET Method on Dynamically Adaptive Octree Grids

Tai Wang, Huixiong Li, Yifan Zhang, Wei Han, Tianyou Sheng, Weiqiang Zhang

ICONE 2014; V004T10A012https://doi.org/10.1115/ICONE22-30355

Abstract

View Articletitled, Numerical Simulation of Two-Phase Flows Using 3D-VOSET Method on Dynamically Adaptive Octree Grids

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Topics: Computer simulation , Octrees , Two-phase flow , Bubbles , Accuracy and precision , Computers , Deformation , Equilibrium (Physics) , Fluids , Gravity (Force)

Coupling of the 3D Neutron Kinetic Core Model DYN3D With the CFD Software ANSYS CFX

Alexander Grahn, Sören Kliem, Ulrich Rohde

ICONE 2014; V004T10A013https://doi.org/10.1115/ICONE22-30400

Abstract

View Articletitled, Coupling of the 3D Neutron Kinetic Core Model DYN3D With the CFD Software ANSYS CFX

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Topics: Computational fluid dynamics , Computer software , Neutrons , Coolants , Fuels , Heat transfer , Transients (Dynamics)

FloEFD Calculation Assessment to Experimental Data in Nuclear Safety Case

Svetlin Philipov, Dimitar Popov, Krasimir Batakliev

ICONE 2014; V004T10A014https://doi.org/10.1115/ICONE22-30411

Abstract

View Articletitled, FloEFD Calculation Assessment to Experimental Data in Nuclear Safety Case

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Topics: Safety , Coolants , Temperature distribution , Computational fluid dynamics , Nuclear power stations

Development of a PWR-W and an AP1000® Containment Building 3D Model With a CFD Code for Best-Estimate Thermal-Hydraulic Analysis

Gonzalo Jiménez, Rafael Bocanegra, Kevin Fernández, César Queral, Javier Montero-Mayorga

ICONE 2014; V004T10A015https://doi.org/10.1115/ICONE22-30445

Abstract

View Articletitled, Development of a PWR-W and an AP1000® Containment Building 3D Model With a CFD Code for Best-Estimate Thermal-Hydraulic Analysis

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Topics: Computational fluid dynamics , Containment buildings , Pressurized water reactors , Three-dimensional models , Containment , Accidents , Design , Geometry , Licensing , Lumped parameter models

Prediction of Laminar to Turbulent Transition in 90° Curved Duct Based on Energy Gradient Theory

Xuekuan Fu, Hongsheng Yuan, Chong Chen, Hanying Chen, Yulin Song, Sichao Tan

ICONE 2014; V004T10A016https://doi.org/10.1115/ICONE22-30467

Abstract

View Articletitled, Prediction of Laminar to Turbulent Transition in 90° Curved Duct Based on Energy Gradient Theory

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Topics: Ducts , Turbulence , Flow (Dynamics) , Stability , Computer simulation , Computer software , Fluid dynamics , Fluids , Geometry , Gradient methods

Hydrodynamic Performance Study on Flow Field in Rod Bundles With Spacer Grids

Li-feng Song, Rui-feng Tian, Lan-xin Sun, Cong Shi, Peng Li

ICONE 2014; V004T10A017https://doi.org/10.1115/ICONE22-30478

Abstract

View Articletitled, Hydrodynamic Performance Study on Flow Field in Rod Bundles With Spacer Grids

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Topics: Flow (Dynamics) , Fuel rods , Computational fluid dynamics , Cross-flow , Design , Fluid dynamics , Heat transfer , Nuclear power , Nuclear reactors , Numerical analysis

Simulation of a Gas Jet in the Secondary Side of a Steam Generator Bundle Following a Tube Rupture Sequence

Roman Mukin, Abdel Dehbi

ICONE 2014; V004T10A018https://doi.org/10.1115/ICONE22-30517

Abstract

View Articletitled, Simulation of a Gas Jet in the Secondary Side of a Steam Generator Bundle Following a Tube Rupture Sequence

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Topics: Boilers , Rupture , Simulation , Flow (Dynamics) , Aerosols , Particulate matter , Turbulence

The Natural Circulation Characteristic Analysis of AP1000 IRWST

Ruojun Xue, Bin Xia, Wang Mingyuan

ICONE 2014; V004T10A019https://doi.org/10.1115/ICONE22-30520

Abstract

View Articletitled, The Natural Circulation Characteristic Analysis of AP1000 IRWST

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Topics: Accidents , Computer software , Containment , Design , Errors , Flow (Dynamics) , Fluids , Heat , Heat exchangers , Heat transfer

Coupled Simulations of Natural and Forced Circulation Tests in NACIE Facility Using RELAP5 and ANSYS Fluent Codes

D. Martelli, N. Forgione, G. Barone, A. Del Nevo, I. Di Piazza, M. Tarantino

ICONE 2014; V004T10A020https://doi.org/10.1115/ICONE22-30552

Abstract

View Articletitled, Coupled Simulations of Natural and Forced Circulation Tests in NACIE Facility Using RELAP5 and ANSYS Fluent Codes

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Topics: Collaboration , Computational fluid dynamics , Computer simulation , Electricity (Physics) , Engineering simulation , Feedback , Flow (Dynamics) , Simulation

CFD Simulation of PANDA and MISTRA Cooler Tests of ERCOSAM-SAMARA Project

A. S. Filippov, S. Y. Grigoryev, O. V. Tarasov, T. A. Iudina

ICONE 2014; V004T10A021https://doi.org/10.1115/ICONE22-30557

Abstract

View Articletitled, CFD Simulation of PANDA and MISTRA Cooler Tests of ERCOSAM-SAMARA Project

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Topics: Computational fluid dynamics , Simulation , Helium , Accidents , Condensation , Coolers , Hydrogen , Steam , Accident management , Accounting

Development and Application of a UTSG Thermal-Hydraulic Analysis Code

Tenglong Cong, Guanghui Su, Wenxi Tian, Suizheng Qiu

ICONE 2014; V004T10A022https://doi.org/10.1115/ICONE22-30569

Abstract

View Articletitled, Development and Application of a UTSG Thermal-Hydraulic Analysis Code

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Topics: Boilers , Boiling , Coolants , Design , Failure , Fatigue , Flow (Dynamics) , Heat transfer , Plates (structures) , Porous materials

Stress Analysis of the Canned Nuclear Coolant Pump Based on FSI

Zhang Ji-Ge, Zhu Yue

ICONE 2014; V004T10A023https://doi.org/10.1115/ICONE22-30587

Abstract

View Articletitled, Stress Analysis of the Canned Nuclear Coolant Pump Based on FSI

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Topics: Coolants , Fluid structure interaction , Pumps , Stress analysis (Engineering) , Impellers , Stress , Blades , Flow (Dynamics) , Fracture (Materials) , Fracture (Process)

Validation of a 3D Hybrid CFD-DEM Method Based on a Self-Leveling Experiment

Liancheng Guo, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita

ICONE 2014; V004T10A024https://doi.org/10.1115/ICONE22-30618

Abstract

View Articletitled, Validation of a 3D Hybrid CFD-DEM Method Based on a Self-Leveling Experiment

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Topics: Computational fluid dynamics , Discrete element methods , Fluid dynamics , Particulate matter , Liquid metal cooled reactors , Safety , Accidents , Computational methods , Computer simulation , Computers

3D Flow Field Analysis for a Traditional II+ PWR Containment Under Normal Condition

Maolin Tian, Wenxi Tian, Guanghui Su, Suizheng Qiu

ICONE 2014; V004T10A025https://doi.org/10.1115/ICONE22-30634

Abstract

View Articletitled, 3D Flow Field Analysis for a Traditional II+ PWR Containment Under Normal Condition

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Topics: Containment , Flow (Dynamics) , Pressurized water reactors , Ventilation equipment , Computational fluid dynamics , Fans , Geometry , Ventilation , Computer software , Cooling

Thermal Hydraulic Analysis of a Water Tank With Large Aspect Ratio

Qi Min, Li Zhang, Hongtao Wang, Junpeng Zhai

ICONE 2014; V004T10A026https://doi.org/10.1115/ICONE22-30642

Abstract

View Articletitled, Thermal Hydraulic Analysis of a Water Tank With Large Aspect Ratio

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Topics: Water , Pipes , Heat transfer , Temperature , Cooling , Computational fluid dynamics , Heat flux , Hot water , Natural convection

Computation of Thermal Striping in the Upper Plenum of PGSFR

Dong-Eun Kim, Sung-Ho Ko, Seok-Ki Choi, Tae-Ho Lee

ICONE 2014; V004T10A027https://doi.org/10.1115/ICONE22-30666

Abstract

View Articletitled, Computation of Thermal Striping in the Upper Plenum of PGSFR

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Topics: Computation , Eddies (Fluid dynamics) , Engineering prototypes , Heat exchangers , Large eddy simulation , Nuclear power , Reynolds-averaged Navier–Stokes equations , Simulation , Sodium fast reactors , Temperature

Numerical Investigation on Thermal Striping Phenomena in a T-Junction Piping System

Masaaki Tanaka, Yasuhiro Miyake

ICONE 2014; V004T10A028https://doi.org/10.1115/ICONE22-30683

Abstract

View Articletitled, Numerical Investigation on Thermal Striping Phenomena in a T-Junction Piping System

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Topics: Junctions , Piping systems , Computer simulation , Eddies (Fluid dynamics) , Pipes , Vortices , Wakes , Cycles , Fatigue , Temperature

The Surge Line Stress Analysis Model Setup With the Consideration of Thermal Stratification

Jianjun Wang, Zengfang Ge, Zhongning Sun, Changqi Yan

ICONE 2014; V004T10A029https://doi.org/10.1115/ICONE22-30686

Abstract

View Articletitled, The Surge Line Stress Analysis Model Setup With the Consideration of Thermal Stratification

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Topics: Stress analysis (Engineering) , Surges , Thermal stratification , Stress , Transients (Dynamics) , Heat , Temperature , Pressurized water reactors , Computational fluid dynamics , Design

Development of Evaluation Method for Impact of Aircraft Fuel Explosion and Fire on BWR Reactor Building

Norio Sakai, Yoshihiro Shoji, Masakazu Jimbo, Nobuhiko Tanaka

ICONE 2014; V004T10A030https://doi.org/10.1115/ICONE22-30699

Abstract

View Articletitled, Development of Evaluation Method for Impact of Aircraft Fuel Explosion and Fire on BWR Reactor Building

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Topics: Aircraft , Boiling water reactors , Evaluation methods , Explosions , Fire , Fuels , Drops , Combustion , Dynamics (Mechanics) , Liquid pool fires

Electromagnetic Pump Flow Simulation by 3D MHD Code

Takatoshi Asada, Yosuke Hirata, Rie Aizawa, Tetsu Suzuki, Yasushi Fujishima

ICONE 2014; V004T10A031https://doi.org/10.1115/ICONE22-30710

Abstract

View Articletitled, Electromagnetic Pump Flow Simulation by 3D MHD Code

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Topics: Flow simulation , Magnetohydrodynamics , Pumps , Flow (Dynamics) , Sodium , Pressure , Vortices , Design , Electromagnetic force , Electromagnetic induction

3D Core Thermal Hydraulics With the PORFLO Code: Turbulence Modeling and Porous Medium With Porosity Steps

Mikko Ilvonen, Ville Hovi, Veikko Taivassalo

ICONE 2014; V004T10A032https://doi.org/10.1115/ICONE22-30731

Abstract

View Articletitled, 3D Core Thermal Hydraulics With the PORFLO Code: Turbulence Modeling and Porous Medium With Porosity Steps

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Topics: Modeling , Porosity , Porous materials , Thermal hydraulics , Turbulence , Fuels , Interpolation , Pressure , Algorithms , Boilers

CFD Validation of Void Distribution in a Rod Bundle With Spacer

Kevin Goodheart, Arto Ylönen, Victor De Cacqueray, Horst-Michael Prasser

ICONE 2014; V004T10A033https://doi.org/10.1115/ICONE22-30741

Abstract

View Articletitled, CFD Validation of Void Distribution in a Rod Bundle With Spacer

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Topics: Computational fluid dynamics , Fuel rods , Bubbles , Nuclear industry , Sensors , Stability , Wire mesh

A CFD Analysis of Flow Blockage Phenomena in ALFRED LFR DEMO Fuel Assembly

I. Di Piazza, M. Tarantino, F. Magugliani, A. Alemberti

ICONE 2014; V004T10A034https://doi.org/10.1115/ICONE22-30777

Abstract

View Articletitled, A CFD Analysis of Flow Blockage Phenomena in ALFRED LFR DEMO Fuel Assembly

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Topics: Computational fluid dynamics , Flow (Dynamics) , Fuels , Manufacturing , Temperature , Engineering simulation , Simulation , Accidents , Feedback , Fluid dynamics

CFD Analysis of the Flow in Crud-Coated Nuclear Rod Bundles

Nicolas Cinosi, Simon P. Walker, Mike Bluck, Raad I. Issa

ICONE 2014; V004T10A035https://doi.org/10.1115/ICONE22-30788

Abstract

View Articletitled, CFD Analysis of the Flow in Crud-Coated Nuclear Rod Bundles

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Topics: Computational fluid dynamics , Flow (Dynamics) , Fuel rods , Pressurized water reactors , Rods , Surface roughness , Coolants , Fuels , Heat transfer , Reynolds-averaged Navier–Stokes equations

Coolant Mixing in the VVER-440 Fuel Assembly Head

Tomas Romsy, Pavel Zacha

ICONE 2014; V004T10A036https://doi.org/10.1115/ICONE22-30823

Abstract

View Articletitled, Coolant Mixing in the VVER-440 Fuel Assembly Head

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Topics: Coolants , Fuels , Manufacturing , Temperature , Thermocouples , Engineering simulation , Flow (Dynamics) , Pins (Engineering) , Simulation , Computational fluid dynamics

Computational Fluid Dynamics Modeling of Two-Phase Boiling Flow and Critical Heat Flux

Adrian Tentner, Elia Merzari, Prasad Vegendla

ICONE 2014; V004T10A037https://doi.org/10.1115/ICONE22-30844

Abstract

View Articletitled, Computational Fluid Dynamics Modeling of Two-Phase Boiling Flow and Critical Heat Flux

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Topics: Boiling , Computational fluid dynamics , Critical heat flux , Flow (Dynamics) , Modeling , Boiling water reactors , Coolants , Fuels , Two-phase flow , Wall temperature

Optimization of Confined Laminar Natural Convection for Dry Cask Storage Systems

Corey E. Clifford, Mark L. Kimber

ICONE 2014; V004T10A038https://doi.org/10.1115/ICONE22-30862

Abstract

View Articletitled, Optimization of Confined Laminar Natural Convection for Dry Cask Storage Systems

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Topics: Natural convection , Optimization , Storage , Cylinders , Heat transfer , Rayleigh number , Fuels , Heat , Heat flux , Boundary-value problems

Numerical Analysis on Flow Inversion in a Uniformly Heated Thin Rectangular Channel Array

Jonghark Park, Suki Park, Daeseong Jo, Heetaek Chae, Byungcheol Lee

ICONE 2014; V004T10A039https://doi.org/10.1115/ICONE22-30876

Abstract

View Articletitled, Numerical Analysis on Flow Inversion in a Uniformly Heated Thin Rectangular Channel Array

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Topics: Flow (Dynamics) , Numerical analysis , Computational fluid dynamics , Valves , Temperature , Computer simulation , Coolants , Fuels , Nucleate boiling , Plates (structures)

Eulerian Two-Phase Flow Modeling of Steam Direct Contact Condensation for the Fukushima Accident Investigation

Marco Pellegrini, Giulia Agostinelli, Hidetoshi Okada, Masanori Naitoh

ICONE 2014; V004T10A040https://doi.org/10.1115/ICONE22-30937

Abstract

View Articletitled, Eulerian Two-Phase Flow Modeling of Steam Direct Contact Condensation for the Fukushima Accident Investigation

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Topics: Condensation , Fukushima nuclear disaster, Japan, 2011 , Modeling , Steam , Two-phase flow , Fluids , Computational fluid dynamics , Bubbles , Accidents , Boiling

Validation DualSPHysics Code for Liquid Sloshing Phenomena

Sergei K. Buruchenko, Alejandro J. C. Crespo

ICONE 2014; V004T10A041https://doi.org/10.1115/ICONE22-30968

Abstract

View Articletitled, Validation DualSPHysics Code for Liquid Sloshing Phenomena

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Topics: Sloshing , Simulation , Accidents , Compacting , Fuels , Hydrodynamics , Liquid metals , Nuclear power , Numerical analysis , Particulate matter

Computational Simulation of Turbulent Natural Convection in a Volumetrically Heated Hemispherical Cavity

Camila Braga Vieira, Bojan Ničeno, Jian Su

ICONE 2014; V004T10A042https://doi.org/10.1115/ICONE22-30992

Abstract

View Articletitled, Computational Simulation of Turbulent Natural Convection in a Volumetrically Heated Hemispherical Cavity

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Topics: Cavities , Natural convection , Simulation , Turbulence , Computational fluid dynamics , Fluids , Light water reactors , Accidents , Bearings , Computer simulation

CFD Simulation of Deflagration to Detonation Transition for Nuclear Safety

Eduardo Hwang, Felipe Porto Ribeiro, Jian Su

ICONE 2014; V004T10A043https://doi.org/10.1115/ICONE22-31010

Abstract

View Articletitled, CFD Simulation of Deflagration to Detonation Transition for Nuclear Safety

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Topics: Computational fluid dynamics , Explosions , Safety , Simulation , Combustion , Flames , Hydrogen , Nuclear power stations , Shock waves , Turbulence

Multi-Scale 2D Sensitivity Analysis of the TALL-3D Experiment

Clotaire Geffray, Rafael Macián-Juan

ICONE 2014; V004T10A044https://doi.org/10.1115/ICONE22-31022

Abstract

View Articletitled, Multi-Scale 2D Sensitivity Analysis of the TALL-3D Experiment

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Topics: Sensitivity analysis , Uncertainty , Computational fluid dynamics , Design , Flow (Dynamics) , Modeling , Simulation , Thermal hydraulics

Pseudo-Transient Simulation of Turbulent Mixing in a Rectangular Channel

Ivan Otic, Xiang Chai, Xu Cheng

ICONE 2014; V004T10A045https://doi.org/10.1115/ICONE22-31023

Abstract

View Articletitled, Pseudo-Transient Simulation of Turbulent Mixing in a Rectangular Channel

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Topics: Simulation , Transients (Dynamics) , Turbulence , Fluctuations (Physics) , Heat transfer , Helium , Kraft papers , Large eddy simulation , Reynolds-averaged Navier–Stokes equations , Simulation results

Preliminary Results on the Coupling of a Three-Dimensional Lead Fast Reactor Model and a One-Dimensional External Loop

Daniele Cerroni, Antonio Cervone, Paride Meloni, Massimiliano Polidori, Sandro Manservisi

ICONE 2014; V004T10A046https://doi.org/10.1115/ICONE22-31052

Abstract

View Articletitled, Preliminary Results on the Coupling of a Three-Dimensional Lead Fast Reactor Model and a One-Dimensional External Loop

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Topics: Fast neutron reactors , Accidents , Circuits , Complex systems , Finite element methods , Finite element model , Heat , Simulation

A New Data-Driven ATHLET – ANSYS CFD Coupling Method for Efficient Simulation of Nuclear Power Plant Circuits

Georgios Theodoridis, Angel Papukchiev, Dominik Scholz, Georg Lerchl

ICONE 2014; V004T10A047https://doi.org/10.1115/ICONE22-31119

Abstract

View Articletitled, A New Data-Driven ATHLET – ANSYS CFD Coupling Method for Efficient Simulation of Nuclear Power Plant Circuits

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Topics: Circuits , Computational fluid dynamics , Nuclear power stations , Simulation , Junctions , Graphical user interfaces , Heat transfer , Two-phase flow

LES of an Isothermal High Reynolds Number Turbulent Round Jet

Sasan Salkhordeh, Sagnik Mazumdar, D. Tyler Landfried, Anirban Jana, Mark L. Kimber

ICONE 2014; V004T10A048https://doi.org/10.1115/ICONE22-31154

Abstract

View Articletitled, LES of an Isothermal High Reynolds Number Turbulent Round Jet

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Topics: Reynolds number , Turbulence , Flow (Dynamics) , Fluctuations (Physics) , Very high temperature reactors , Statistics , Stress , Eddies (Fluid dynamics) , Engineering systems and industry applications , Jets

Conjugated Numerical Study on the Performance of Microchannel Heat Sink Using Al₂O₃/H₂O Nanofluid

J. M. Wu, J. Y. Zhao

ICONE 2014; V004T10A049https://doi.org/10.1115/ICONE22-31210

Abstract

View Articletitled, Conjugated Numerical Study on the Performance of Microchannel Heat Sink Using Al2O3/H2O Nanofluid

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Topics: Heat sinks , Microchannels , Nanofluids , Water , Heat , Control systems , Coolants , Cooling systems , Electronics , Fluids

CFD Analysis of Single Phase Counter-Current Buoyancy Driven Flows and its Applications to Passive Reactor Design

Frederic Sebilleau, Anuj K. Kansal, Raad I. Issa, Simon P. Walker

ICONE 2014; V004T10A050https://doi.org/10.1115/ICONE22-31264

Abstract

View Articletitled, CFD Analysis of Single Phase Counter-Current Buoyancy Driven Flows and its Applications to Passive Reactor Design

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Topics: Buoyancy , Computational fluid dynamics , Design , Flow (Dynamics) , Pipes , Fluids , Turbulence , Anisotropy , Containment , Heat sinks

SKYTHIA: A Universal Multi-Phase Flow Analyzer

Nikolay Ivanov Kolev

ICONE 2014; V004T10A051https://doi.org/10.1115/ICONE22-31285

Abstract

View Articletitled, SKYTHIA: A Universal Multi-Phase Flow Analyzer

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Topics: Multiphase flow , Water , Equilibrium (Physics) , Fluids , Flow (Dynamics) , Pipes , Simulation , Boilers , Piping systems , Steam

Reactor Physics and Transport Theory

²³³U Evaluation Comparison Study

Mohammad Alrwashdeh, Aniseh Abdalla, Kan Wang

ICONE 2014; V004T11A001https://doi.org/10.1115/ICONE22-30057

Abstract

View Articletitled, 233U Evaluation Comparison Study

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Topics: Bayes methods , Computers , Cross section (Physics) , Databases , Fittings , Resonance

Monte Carlo Neutron Transport on GPUs

Ryan M. Bergmann, Jasmina L. Vujić

ICONE 2014; V004T11A002https://doi.org/10.1115/ICONE22-30148

Abstract

View Articletitled, Monte Carlo Neutron Transport on GPUs

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Topics: Graphics processing units , Neutrons , Algorithms , Energy consumption , Architecture , Engineering simulation , Lumber , Power stations , Simulation

A 1D Monoenergetic Neutron Transport Benchmark in an Infinite Medium

Barry D. Ganapol

ICONE 2014; V004T11A003https://doi.org/10.1115/ICONE22-30156

Abstract

View Articletitled, A 1D Monoenergetic Neutron Transport Benchmark in an Infinite Medium

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Topics: Neutrons , Approximation , Engineering simulation , Matlab , Simulation

Physical Analysis of LBE Spallation Target Coupled With the Reactor for CIADS

Lu Zhang, Yongwei Yang, Yucui Gao

ICONE 2014; V004T11A004https://doi.org/10.1115/ICONE22-30195

Abstract

View Articletitled, Physical Analysis of LBE Spallation Target Coupled With the Reactor for CIADS

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Topics: Spallation (Nuclear physics) , Density , Design , Neutrons , Pipes , Heat , Neutron flux , Optimization , Physics , Thermal hydraulics

Application of Hybrid Subgroup Decomposition Method to Gas Cooled Thermal Reactor Problem

Saam Yasseri, Farzad Rahnema

ICONE 2014; V004T11A005https://doi.org/10.1115/ICONE22-30353

Abstract

View Articletitled, Application of Hybrid Subgroup Decomposition Method to Gas Cooled Thermal Reactor Problem

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Topics: Eigenvalues , Thermal reactors

Development of Grid Depression Model for GalaxyCosmo-S

Hiroki Koike, Kazuki Kirimura, Kazuya Yamaji, Shinya Kosaka, Hideki Matsumoto

ICONE 2014; V004T11A006https://doi.org/10.1115/ICONE22-30379

Abstract

View Articletitled, Development of Grid Depression Model for GalaxyCosmo-S

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Topics: Cycles , Design , Fittings , Fuels , Manufacturing , Nuclear design , Pressurized water reactors , Sensors , Uncertainty

Comparison Between PARCS and MCNP6 Codes on VVER1000/V320 Core

Guido Mazzini, Bruno Miglierini, Marek Ruščák

ICONE 2014; V004T11A007https://doi.org/10.1115/ICONE22-30386

Abstract

View Articletitled, Comparison Between PARCS and MCNP6 Codes on VVER1000/V320 Core

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Topics: Accidents , Boron , Cross section (Physics) , Design , Engineering simulation , Neutrons , Nuclear power stations , Nuclear reactor kinetics , Pressurized water reactors , Safety

A Time-Dependent Solver for Coupled Neutron-Transport Thermal-Mechanics Calculations and Simulation of a Godiva Prompt-Critical Burst

Carlo Fiorina, Manuele Aufiero, Sandro Pelloni, Konstantin Mikityuk

ICONE 2014; V004T11A008https://doi.org/10.1115/ICONE22-30395

Abstract

View Articletitled, A Time-Dependent Solver for Coupled Neutron-Transport Thermal-Mechanics Calculations and Simulation of a Godiva Prompt-Critical Burst

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Topics: Neutrons , Simulation , Transients (Dynamics) , Uranium , Collaboration , Computer software , Fluid dynamics , Manufacturing , Physics , Slabs

Analysis of Isotopic Contributions to Doppler Coefficients of Inert Matrix Fuels

Jinsen Xie, Tao Yu

ICONE 2014; V004T11A009https://doi.org/10.1115/ICONE22-30620

Abstract

View Articletitled, Analysis of Isotopic Contributions to Doppler Coefficients of Inert Matrix Fuels

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Topics: Fuels , Neutrons , Absorption , Resonance , Hazards , Isotopes , Pressurized water reactors , Temperature , Weapons , Zirconium

Application of 3D Coupled Code SPARKLE-2 to PWR Anticipated Transient Without Scram

Koji Asano, Hikaru Sakamoto, Satoshi Imura, Junto Ogawa

ICONE 2014; V004T11A010https://doi.org/10.1115/ICONE22-30744

Abstract

View Articletitled, Application of 3D Coupled Code SPARKLE-2 to PWR Anticipated Transient Without Scram

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Topics: Pressurized water reactors , Scram , Transients (Dynamics) , Failure , Pressure , Design , Feedback , Feedwater , Flow (Dynamics) , Neutrons

ANDREA 2: Improved Version of Code for Reactor Core Analysis

František Havlůj, Radim Vočka, Jiří Vysoudil

ICONE 2014; V004T11A011https://doi.org/10.1115/ICONE22-30840

Abstract

View Articletitled, ANDREA 2: Improved Version of Code for Reactor Core Analysis

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Topics: Physics , Workflow

The Super Equivalence Method in Monte Carlo Based Homogenization

Mancang Li, Kan Wang, Dong Yao

ICONE 2014; V004T11A012https://doi.org/10.1115/ICONE22-30882

Abstract

View Articletitled, The Super Equivalence Method in Monte Carlo Based Homogenization

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Topics: Chemical kinetics , Cross section (Physics) , Diffusion (Physics) , Eigenvalues , Errors , Light water reactors , Monte Carlo methods , Physics , Preservation