Volumes | International Conference on Nuclear Engineering | American Society of Mechanical Engineers Digital Collection

Topics: Accidents , Materials testing , Simulation , Safety , Geometry , Thermal hydraulics , Approximation , Chemistry , Condensation , Diffusion (Physics)

Validation of a New Lattice Physics Code GALAXY for PWRs

Kazuya Yamaji, Hiroki Koike, Daisuke Sato, Shinobu Tsubota, Hideki Matsumoto

ICONE 2010; 27-34doi:https://doi.org/10.1115/ICONE18-29221

Abstract

View Articletitled, Validation of a New Lattice Physics Code GALAXY for PWRs

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Topics: Physics , Pressurized water reactors , Computational methods , Experimental analysis , Irradiation (Radiation exposure) , Manufacturing , Nuclear design

Evaluation Technique With MCNP for Temperature Dependent Problems

Hiroyuki Fujime, Shinji Abe, Kazuya Yamaji, Daisuke Sato, Hideki Matsumoto

ICONE 2010; 35-41doi:https://doi.org/10.1115/ICONE18-29252

Abstract

View Articletitled, Evaluation Technique With MCNP for Temperature Dependent Problems

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Topics: Temperature , Cross section (Physics) , Nuclear design , Approximation , Design , Fuels , Light water reactors , Temperature distribution , Temperature profiles

Validation of a New Core Simulator COSMO-S for PWRs

Shinobu Tsubota, Daisuke Sato, Kazuya Yamaji, Hiroki Koike, Hideki Matsumoto

ICONE 2010; 43-48doi:https://doi.org/10.1115/ICONE18-29254

Abstract

View Articletitled, Validation of a New Core Simulator COSMO-S for PWRs

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Topics: Pressurized water reactors , Design , Manufacturing , Fittings , Temperature , Accuracy and precision , Density , Fuels , Nuclear design , Robustness

Study of the Space-Time Neutron Multiplication Formula

Jianli Hao, Wenzhen Chen, Shaoming Wang, De Zhang

ICONE 2010; 49-54doi:https://doi.org/10.1115/ICONE18-29279

Abstract

View Articletitled, Study of the Space-Time Neutron Multiplication Formula

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Topics: Density , Neutrons , Spacetime

Analysis of ABWR Critical Control and Heat-Up Control Operation by TRACG Code

Yoshihiko Ishii, Kazuaki Kitou, Tomohiko Ikegawa, Shin Hasegawa, Hitoshi Ochi

ICONE 2010; 55-62doi:https://doi.org/10.1115/ICONE18-29285

Abstract

View Articletitled, Analysis of ABWR Critical Control and Heat-Up Control Operation by TRACG Code

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Topics: Heat , Neutrons , Water temperature , Algorithms , Boiling water reactors , Control algorithms , Design , Neutron sources , Power regulators , Sensors

A New Method on Flux Mapping by Function Expansion

Bin Zhong, Kan Wang, Ganglin Yu

ICONE 2010; 63-68doi:https://doi.org/10.1115/ICONE18-29315

Abstract

View Articletitled, A New Method on Flux Mapping by Function Expansion

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Topics: Coolants , Density , Diffusion (Physics) , Fuel cells , Fuels , Nuclear reactors , Sensors , Simulation results , Surveillance , Temperature

Conceptual Design of CANDU-SCWR With Thermal-Hydraulics Coupling

Ping Yang, Liangzhi Cao, Hongchun Wu, Changhui Wang

ICONE 2010; 69-77doi:https://doi.org/10.1115/ICONE18-29373

Abstract

View Articletitled, Conceptual Design of CANDU-SCWR With Thermal-Hydraulics Coupling

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Topics: Conceptual design , Design , Supercritical water reactors , Thermal hydraulics

Acceleration Technique Using Krylov Subspace Methods for 2D Arbitrary Geometry Characteristics Solver

Hongbo Zhang, Hongchun Wu, Liangzhi Cao

ICONE 2010; 79-87doi:https://doi.org/10.1115/ICONE18-29420

Abstract

View Articletitled, Acceleration Technique Using Krylov Subspace Methods for 2D Arbitrary Geometry Characteristics Solver

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Topics: Geometry , Linear systems , Algebra , Flux (Metallurgy)

Direct 3D MOC for Whole-Core Transport Calculation

Zhouyu Liu, Hongchun Wu, Liangzhi Cao, Qichang Chen, Yunzhao Li

ICONE 2010; 89-96doi:https://doi.org/10.1115/ICONE18-29425

Abstract

View Articletitled, Direct 3D MOC for Whole-Core Transport Calculation

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Topics: Computers , Geometry , Neutrons , Ray tracing

Neutron Transport Solution Using the Daubechies’ Wavelets in the Spatial Discretization

Youqi Zheng, Hongchun Wu, Liangzhi Cao

ICONE 2010; 97-105doi:https://doi.org/10.1115/ICONE18-29429

Abstract

View Articletitled, Neutron Transport Solution Using the Daubechies’ Wavelets in the Spatial Discretization

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Topics: Neutrons , Wavelets , Boundary-value problems , Galerkin method , Neutron flux

EPR™: A Reactor to Support Economical Fuel Cycles

S. Zheng, R. Meinl, J. Stephens

ICONE 2010; 107-112doi:https://doi.org/10.1115/ICONE18-29439

Abstract

View Articletitled, EPR™: A Reactor to Support Economical Fuel Cycles

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Topics: Cycles , Fuels , Fuel management , Design , Economic analysis , Nuclear fuel cycle , Pressurized water reactors , Safety , Uranium

Determinant Methods for Solving Neutron Transport Equation in Unstructured Geometry

Hongchun Wu, Guoming Liu, Liangzhi Cao, Qichang Chen

ICONE 2010; 113-117doi:https://doi.org/10.1115/ICONE18-29442

Abstract

View Articletitled, Determinant Methods for Solving Neutron Transport Equation in Unstructured Geometry

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Topics: Fuels , Geometry , Manufacturing , Neutrons

Self-Shielding and Criticality Calculation in Spent Fuel Dissolving Vessel

Qingjie Liu, Hongchun Wu, Liangzhi Cao

ICONE 2010; 119-125doi:https://doi.org/10.1115/ICONE18-29481

Abstract

View Articletitled, Self-Shielding and Criticality Calculation in Spent Fuel Dissolving Vessel

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Topics: Spent nuclear fuels , Vessels , Resonance , Isotopes , Cross section (Physics) , Fuels , Pressurized water reactors , Carbon reinforced plastics , Elastic scattering , Fittings

RMC1.0: Development of Monte Carlo Code for Reactor Analysis

Ding She, Qi Xu, Kan Wang, Ganglin Yu

ICONE 2010; 127-131doi:https://doi.org/10.1115/ICONE18-29482

Abstract

View Articletitled, RMC1.0: Development of Monte Carlo Code for Reactor Analysis

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Topics: Collisions (Physics) , Eigenvalues , Geometry

Resonance Calculation Code UFOP Based on the Hyper-Fine Group Neutron Resonance Calculation Method

Yulong Qin, Hongchun Wu, Liangzhi Cao, Qingjie Liu

ICONE 2010; 133-141doi:https://doi.org/10.1115/ICONE18-29491

Abstract

View Articletitled, Resonance Calculation Code UFOP Based on the Hyper-Fine Group Neutron Resonance Calculation Method

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Topics: Computational methods , Neutrons , Resonance , Collisions (Physics) , Probability , Computation , Errors , Fuel cells , Physics , Pressurized water reactors

Study of Self-Shielding Calculation With Temperature Distribution Applying Wavelets Scaling Function Expansion Continuous-Energy Resonance Method

Weiyan Yang, Hongchun Wu, Liangzhi Cao

ICONE 2010; 143-150doi:https://doi.org/10.1115/ICONE18-29498

Abstract

View Articletitled, Study of Self-Shielding Calculation With Temperature Distribution Applying Wavelets Scaling Function Expansion Continuous-Energy Resonance Method

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Topics: Resonance , Temperature distribution , Wavelets , Temperature , Cross section (Physics) , Fuel rods , Interpolation , Chemical kinetics , Doppler effect , Fuels

Analytic Basis Function Expansion Nodal Method for Neutron Diffusion Equations in Triangular Geometry

Kunpeng Wang, Hongchun Wu, Liangzhi Cao, Changhui Wang

ICONE 2010; 151-157doi:https://doi.org/10.1115/ICONE18-29518

Abstract

View Articletitled, Analytic Basis Function Expansion Nodal Method for Neutron Diffusion Equations in Triangular Geometry

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Topics: Diffusion (Physics) , Geometry , Neutrons

A Method of Optimized Utilization of Point-Wise Data Format in Monte Carlo Code

Yuxuan Liu, Ganglin Yu, Kan Wang

ICONE 2010; 159-165doi:https://doi.org/10.1115/ICONE18-29533

Abstract

View Articletitled, A Method of Optimized Utilization of Point-Wise Data Format in Monte Carlo Code

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Topics: Algorithms , Cross section (Physics) , Geometry , Monte Carlo methods , Nuclides , Particulate matter

Treatment of Neutron Cross-Section With Interpolation

Xiang Zhang, Ganglin Yu, Guangwen Bi, Kang Wang

ICONE 2010; 167-174doi:https://doi.org/10.1115/ICONE18-29540

Abstract

View Articletitled, Treatment of Neutron Cross-Section With Interpolation

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Topics: Interpolation , Neutrons , Temperature

Effect of Pin and Subassembly Heterogenity in Sodium Void Worth Calculations

G. Raghu Kumar, C. P. Reddy, V. Sathyamoorthy

ICONE 2010; 175-180doi:https://doi.org/10.1115/ICONE18-29547

Abstract

View Articletitled, Effect of Pin and Subassembly Heterogenity in Sodium Void Worth Calculations

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Topics: Accidents , Fast neutron reactors , Flow (Dynamics) , Sodium

The Consistency of WIMS-D Library and ACE Format Library

Zhiyan Liu, Hongchun Wu, Liangzhi Cao, Qingjie Liu

ICONE 2010; 181-188doi:https://doi.org/10.1115/ICONE18-29548

Abstract

View Articletitled, The Consistency of WIMS-D Library and ACE Format Library

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Topics: Design , Errors , Wavelets

Localization of a Noise Source in VVER-1000 Reactor Core Using Neutron Noise Analysis Methods

Hessam Malmir, Naser Vosoughi, Ehsan Zahedinejad

ICONE 2010; 189-196doi:https://doi.org/10.1115/ICONE18-29562

Abstract

View Articletitled, Localization of a Noise Source in VVER-1000 Reactor Core Using Neutron Noise Analysis Methods

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Topics: Neutrons , Noise (Sound) , Diffusion (Physics) , Transfer functions , Approximation , Finite difference methods , Sensors

Multi-Group Library Generation for the Study of Nuclide Transmutation in High Flux Engineering Test Reactor

Lei He, Hongchun Wu, Liangzhi Cao, Qingjie Liu, Zhiyan Liu

ICONE 2010; 197-204doi:https://doi.org/10.1115/ICONE18-29563

Abstract

View Articletitled, Multi-Group Library Generation for the Study of Nuclide Transmutation in High Flux Engineering Test Reactor

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Topics: Absorption , Nuclides , Radioactive wastes , Resonance , Thermal reactors , Weight (Mass)

High Performance Reconfigurable Hardware Acceleration on Neutron Transport Computation Based on AGENT Methodology

Shanjie Xiao, Tatjana Jevremovic

ICONE 2010; 205-210doi:https://doi.org/10.1115/ICONE18-29614

Abstract

View Articletitled, High Performance Reconfigurable Hardware Acceleration on Neutron Transport Computation Based on AGENT Methodology

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Topics: Computation , Hardware , Neutrons , Simulation , Computer software , Physics

Solving the Time-Dependent Transport Equation Using Time-Dependent Method of Characteristics and Rosenbrock Method

Xue Yang, Tatjana Jevremovic

ICONE 2010; 211-216doi:https://doi.org/10.1115/ICONE18-29638

Abstract

View Articletitled, Solving the Time-Dependent Transport Equation Using Time-Dependent Method of Characteristics and Rosenbrock Method

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Topics: Approximation , Boundary-value problems , Differential equations , Fast neutron reactors , Geometry , Leakage , Neutrons , Steady state , Vacuum

Decay Heat Benchmark for Uranium-Free Fuels With Minor Actinides

Andrei Rineiski, Ge´rald Rimpault, Georgios Glinatsis, Nadia Messaoudi, Sandro Pelloni, Aleksandra Schwenk-Ferrero, Maria Carmen Vicente

ICONE 2010; 217-226doi:https://doi.org/10.1115/ICONE18-29654

Abstract

View Articletitled, Decay Heat Benchmark for Uranium-Free Fuels With Minor Actinides

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Topics: Fuels , Heat , Uranium , Bearings , Design , Cooling , Safety , Uncertainty

Experimental Comparisons of 3D Reconstructed Pin-Power Distributions in Full-Scale BWR Fuel Assemblies

Flavio D. Giust, Peter Grimm, Rakesh Chawla

ICONE 2010; 227-236doi:https://doi.org/10.1115/ICONE18-29691

Abstract

View Articletitled, Experimental Comparisons of 3D Reconstructed Pin-Power Distributions in Full-Scale BWR Fuel Assemblies

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Topics: Boiling water reactors , Fuels , Blades , Gadolinium , Diffusion (Physics) , Nuclear fission , Nuclear power stations , Polishing equipment , Rods , Temperature

On Line Monitoring the Reactor Power Distribution Based on the Data Library of the Eigenfunctions

Changhui Wang, Hongchun Wu, Liangzhi Cao

ICONE 2010; 237-243doi:https://doi.org/10.1115/ICONE18-29709

Abstract

View Articletitled, On Line Monitoring the Reactor Power Distribution Based on the Data Library of the Eigenfunctions

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Topics: Eigenfunctions

Qualification of Reactor Physics Toolset for a Thorium-Fuelled CANDU Reactor

Peter G. Boczar, Bronwyn Hyland, Erik Hagberg

ICONE 2010; 245-250doi:https://doi.org/10.1115/ICONE18-29763

Abstract

View Articletitled, Qualification of Reactor Physics Toolset for a Thorium-Fuelled CANDU Reactor

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Topics: Physics , Fuels , Design , Uncertainty , Uranium , Computers , Isotopes

Monte Carlo Simulation Compared With Classic Deterministic Solutions for Neutron Transport and Diffusion

Zafar Ullah Koreshi, Sadaf Siddiq

ICONE 2010; 251-258doi:https://doi.org/10.1115/ICONE18-29971

Abstract

View Articletitled, Monte Carlo Simulation Compared With Classic Deterministic Solutions for Neutron Transport and Diffusion

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Topics: Diffusion (Physics) , Neutrons , Simulation , Slabs , Electromagnetic scattering , Geometry , Radiation scattering , Scattering (Physics) , Aluminum , Eigenfunctions

DeCART Depletion Calculation for PMR200 Two-Dimensional Core

Jin-Young Cho, Chang-Keun Jo, Kyo-Youn Kim, Hyun-Chul Lee

ICONE 2010; 259-265doi:https://doi.org/10.1115/ICONE18-30017

Abstract

View Articletitled, DeCART Depletion Calculation for PMR200 Two-Dimensional Core

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Topics: Eigenvalues , Neutrons , Pressurized water reactors , Vacuum , Very high temperature reactors , Vessels

Resonance Calculation for Large and Complicated Geometry Using Tone’s Method by Incorporating the Method of Characteristics

Yu Hao, Akio Yamamoto, Yoshihiro Yamane

ICONE 2010; 267-273doi:https://doi.org/10.1115/ICONE18-30046

Abstract

View Articletitled, Resonance Calculation for Large and Complicated Geometry Using Tone’s Method by Incorporating the Method of Characteristics

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Topics: Geometry , Resonance , Cylinders , Fuels , Manufacturing , Slabs

Calculation of Fuel Burn Up and Radioactive Inventory for HEU Fuel Element of Tehran Research Reactor

Seyed Abolfazl Hosseini, Naser Vosoughi, Mohammad Hosseini

ICONE 2010; 275-280doi:https://doi.org/10.1115/ICONE18-30159

Abstract

View Articletitled, Calculation of Fuel Burn Up and Radioactive Inventory for HEU Fuel Element of Tehran Research Reactor

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Topics: Fuels

Development of a Software for Calculation of Kinetic Parameters of PWR Reactors

Ali Jahanbin, Mehrdad Boroushaki

ICONE 2010; 281-286doi:https://doi.org/10.1115/ICONE18-30160

Abstract

View Articletitled, Development of a Software for Calculation of Kinetic Parameters of PWR Reactors

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Topics: Computer software , Pressurized water reactors , Accidents , Computer programming languages , Safety

Investigations on the Impact of Heavy Nuclides Resonance Elastic Scattering Models on Resonance Integrals

Sitao Peng, Shaohong Zhang, Xiaofeng Jiang

ICONE 2010; 287-295doi:https://doi.org/10.1115/ICONE18-30195

Abstract

View Articletitled, Investigations on the Impact of Heavy Nuclides Resonance Elastic Scattering Models on Resonance Integrals

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Topics: Elastic scattering , Nuclides , Resonance , Electromagnetic scattering , Neutrons , Radiation scattering , Scattering (Physics) , Errors , Monte Carlo methods

A New Methodology to Obtain the 1D Cross-Sections for TRAC-BF1 Code: Application to Peach Bottom NPP

T. Barrachina, R. Miro´, G. Verdu´, I. Collazo, P. Gonza´lez, A. Concejal, P. Ortego, J. Melara

ICONE 2010; 297-301doi:https://doi.org/10.1115/ICONE18-30203

Abstract

View Articletitled, A New Methodology to Obtain the 1D Cross-Sections for TRAC-BF1 Code: Application to Peach Bottom NPP

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Topics: Cross section (Physics) , Nuclear power stations , Polynomials , Simulation , Flux (Metallurgy) , Neutrons , Steady state , Transients (Dynamics) , Turbines

Development of Buildup Factors for Updating the ANSI/ANS-6.4.3 Standard

Charlotta E. Sanders

ICONE 2010; 303-309doi:https://doi.org/10.1115/ICONE18-30212

Abstract

View Articletitled, Development of Buildup Factors for Updating the ANSI/ANS-6.4.3 Standard

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Topics: Absorption , Anisotropy , Computer technology , Concretes , Data centers , Databases , Energy transformation , Failure , Gamma rays , National Institute of Standards and Technology

Depletion Calculation for a Nodal Reactor Physics Code

Antonio Carlos Marques Alvim, Fernando Carvalho da Silva, Aquilino Senra Martinez

ICONE 2010; 311-316doi:https://doi.org/10.1115/ICONE18-30310

Abstract

View Articletitled, Depletion Calculation for a Nodal Reactor Physics Code

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Topics: Boron , Chain , Cycles , Design , Differential equations , Diffusion (Physics) , Fuels , Isotopes , Neutrons , Nuclear design

Wavelets Scaling Function Expansion Resonance Self-Shielding Calculation Based on the DDPM

Tiejun Zu, Hongchun Wu, Liangzhi Cao, Qingjie Liu, Weiyan Yang

ICONE 2010; 317-322doi:https://doi.org/10.1115/ICONE18-30370

Abstract

View Articletitled, Wavelets Scaling Function Expansion Resonance Self-Shielding Calculation Based on the DDPM

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Topics: Resonance , Wavelets , Computational methods , Neutrons , Neutron flux , Probability , Thermal energy

Nuclear Education, Public Acceptance and Related Issues

Reactor Experiments Course of the Swiss Nuclear Engineering Master

R. Chawla, G. Girardin, O. P. Joneja

ICONE 2010; 323-330doi:https://doi.org/10.1115/ICONE18-29183

Abstract

View Articletitled, Reactor Experiments Course of the Swiss Nuclear Engineering Master

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Topics: Nuclear engineering , Feedback , Radiation (Physics) , Statistics , Students , Teaching

The Swiss Master in Nuclear Engineering: A Collaboration Between Universities, Research Centre and Industry

R. Chawla, J. P. Ansermet, J. M. Cavedon, P. Hirt, W. Kro¨ger, H. M. Prasser, M. Q. Tran

ICONE 2010; 331-340doi:https://doi.org/10.1115/ICONE18-29218

Abstract

View Articletitled, The Swiss Master in Nuclear Engineering: A Collaboration Between Universities, Research Centre and Industry

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Topics: Collaboration , Nuclear engineering , Students , Education , Nuclear fission , Public utilities , Teaching

Frame of Two Way Risk Communication by Learning Organization to Foster Safety Culture

Hidekazu Yoshikawa

ICONE 2010; 341-346doi:https://doi.org/10.1115/ICONE18-29271

Abstract

View Articletitled, Frame of Two Way Risk Communication by Learning Organization to Foster Safety Culture

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Topics: Risk communication , Safety , Nuclear industry , Earthquakes , Governments , Nuclear power , Nuclear power stations

Comparative Study of Government Subsidization of U.S. Electrical Energy Sources

Gary M. Sandquist, Jay F. Kunze

ICONE 2010; 347-353doi:https://doi.org/10.1115/ICONE18-29327

Abstract

View Articletitled, Comparative Study of Government Subsidization of U.S. Electrical Energy Sources

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Topics: Energy resources , Governments , Renewable energy sources , Solar energy , Nuclear power , Wind , Coal , Geothermal engineering , Hydropower

What Opinions Do People Have Through the Understanding Concerning High-Level Radioactive Waste Disposal Project?

Hiroshi Kimura, Masashi Furukawa, Daisuke Sugiyama, Taiji Chida

ICONE 2010; 355-359doi:https://doi.org/10.1115/ICONE18-29340

Abstract

View Articletitled, What Opinions Do People Have Through the Understanding Concerning High-Level Radioactive Waste Disposal Project?

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Topics: Nuclear power , Radioactive waste disposal , Radioactive wastes

Economic Analysis on MOX Fuels

Shizhuang Jia, Liangzhi Cao, Hongchun Wu

ICONE 2010; 361-366doi:https://doi.org/10.1115/ICONE18-29416

Abstract

View Articletitled, Economic Analysis on MOX Fuels

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Topics: Economic analysis , Fuels , Flow (Dynamics) , Pressurized water reactors , Nuclear fuel cycle

Introducing Nuclear Power Plants in an OECD Country: Size Influence on the External Factors

Giorgio Locatelli, Mauro Mancini, Alessandro Galli

ICONE 2010; 367-379doi:https://doi.org/10.1115/ICONE18-29460

Abstract

View Articletitled, Introducing Nuclear Power Plants in an OECD Country: Size Influence on the External Factors

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Topics: Nuclear power stations , Economics , Construction , Economic analysis , Flow (Dynamics) , Fuels , Maintenance , Nuclear decommissioning

An Overview for Achieving Public Understanding and Acceptance of Nuclear Power: Bangladesh Perspective

A. S. Mollah

ICONE 2010; 381-384doi:https://doi.org/10.1115/ICONE18-29781

Abstract

View Articletitled, An Overview for Achieving Public Understanding and Acceptance of Nuclear Power: Bangladesh Perspective

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Topics: Nuclear power , Construction , Emissions , Energy resources , Failure , Fuels , Gases , Nuclear power stations , Nuclear reactors , Safety

Study on HSE Management System of AP1000 Nuclear Plant Project

Xiaogang He, Xiaopeng Fang, Zhong Wei, Yanli Yang, Zhiyou Sun

ICONE 2010; 385-390doi:https://doi.org/10.1115/ICONE18-29798

Abstract

View Articletitled, Study on HSE Management System of AP1000 Nuclear Plant Project

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Topics: Environmental health and safety , Modular construction , Nuclear power stations , Safety

A Comparison of Different Communication Tools for Distance Learning in Nuclear Education

Glenn Harvel, Wendy Hardman

ICONE 2010; 391-401doi:https://doi.org/10.1115/ICONE18-29824

Abstract

View Articletitled, A Comparison of Different Communication Tools for Distance Learning in Nuclear Education

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Topics: Education , Students , Nuclear engineering , Nuclear industry , Chemical engineering , Computers , Engineering standards , Mechanical engineering , Nuclear engineers , Physics

Misunderstanding Regarding to Global Warming and Nuclear Power

Chiyokazu Fukae

ICONE 2010; 403-408doi:https://doi.org/10.1115/ICONE18-29841

Abstract

View Articletitled, Misunderstanding Regarding to Global Warming and Nuclear Power

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Topics: Climate change , Nuclear power , Nuclear power stations , Accidents , Carbon dioxide , Energy generation , Radioactive substances

Comparison of Publicity Materials Pertaining to the Selection of High Level Radioactive Waste Repository Sites

Noriko Kanzaki, Koji Okamoto, Ryutaro Wada

ICONE 2010; 409-414doi:https://doi.org/10.1115/ICONE18-29883

Abstract

View Articletitled, Comparison of Publicity Materials Pertaining to the Selection of High Level Radioactive Waste Repository Sites

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Topics: Radioactive wastes , Radioactive waste repositories

Reform of Nuclear Safety Education for Non-Nuclear Engineering Students

Qinghai Luo, Zhuying Zou

ICONE 2010; 415-420doi:https://doi.org/10.1115/ICONE18-29983

Abstract

View Articletitled, Reform of Nuclear Safety Education for Non-Nuclear Engineering Students

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Topics: Education , Engineering students , Safety

The Progress of ICRP New Recommendations

Aiguo Shang, Changjie Lu, Jin Qin

ICONE 2010; 421-424doi:https://doi.org/10.1115/ICONE18-30111

Abstract

View Articletitled, The Progress of ICRP New Recommendations

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Topics: Biological tissues , Probes , Radiation (Physics) , Risk , Systems analysis

Application of RELSIM-RELAP/SCDAPSIM for University Training and Simulator Development

Chris M. Allison, Brian S. Allison, Uwe Luettringhaus, Judith K. Hohorst

ICONE 2010; 425-430doi:https://doi.org/10.1115/ICONE18-30215

Abstract

View Articletitled, Application of RELSIM-RELAP/SCDAPSIM for University Training and Simulator Development

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Topics: Accidents , Blocks (Building materials) , Engineering education , Fuels , Graphical user interfaces , Hydraulic drive systems , Nuclear reactors , Pipes , Risk management , Simulation

Student Paper Competition

Probabilistic Safety Assessment to the 1000 MWe NPP During Shutdown Conditions

Lin Li, Bo Zhao

ICONE 2010; 431-445doi:https://doi.org/10.1115/ICONE18-29007

Abstract

View Articletitled, Probabilistic Safety Assessment to the 1000 MWe NPP During Shutdown Conditions

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Topics: Nuclear power stations , Probabilistic safety assessment , Risk , Human reliability analysis , Computer software , Damage , Design , Failure data , Safety , Systems analysis

Measurement of Neutron and Gamma Spatial Distribution in Radial Channel at VR1 Reactor

Marija Miletic´

ICONE 2010; 447-456doi:https://doi.org/10.1115/ICONE18-29099

Abstract

View Articletitled, Measurement of Neutron and Gamma Spatial Distribution in Radial Channel at VR1 Reactor

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Topics: Neutrons , Gamma rays , Sensors

Peculiarities of Hydrodynamics of Lead and Lead-Bismuth Coolant Flows of Reactor Loops

P. A. Bokov, V. S. Baranova, M. S. Kustov, M. A. Antonenkov, A. G. Meluzov, A. V. Besnosov

ICONE 2010; 457-462doi:https://doi.org/10.1115/ICONE18-29173

Abstract

View Articletitled, Peculiarities of Hydrodynamics of Lead and Lead-Bismuth Coolant Flows of Reactor Loops

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Topics: Coolants , Flow (Dynamics) , Hydrodynamics , Liquid metals , Water , Cavitation , Temperature , Circuits , Nozzles , Pumps

Peculiarities of Friction and Depreciation of Contact Surfaces in High-Temperature Lead and Lead-Bismuth Coolants of Reactor Loops

M. A. Antonenkov, P. A. Bokov, D. V. Kuznetsov, T. A. Bokova, A. V. Besnosov

ICONE 2010; 463-469doi:https://doi.org/10.1115/ICONE18-29175

Abstract

View Articletitled, Peculiarities of Friction and Depreciation of Contact Surfaces in High-Temperature Lead and Lead-Bismuth Coolants of Reactor Loops

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Topics: Coolants , Friction , High temperature , Liquid metals , Neutrons , Nuclear fission

3D Simulation of Molten Metal Freezing Behaviour Using Finite Volume Particle Method

Rida S. N. Mahmudah, Masahiro Kumabe, Takahito Suzuki, LianCheng Guo, Koji Morita, Kenji Fukuda

ICONE 2010; 471-479doi:https://doi.org/10.1115/ICONE18-29198

Abstract

View Articletitled, 3D Simulation of Molten Metal Freezing Behaviour Using Finite Volume Particle Method

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Topics: Freezing , Metals , Particulate matter , Simulation , Metalwork , Accidents , Flow (Dynamics) , Fluid dynamics , Heat transfer , Liquid metals

A Parametric Study of Fuel Lattice Design for HTR-10

Meng-Jen Wang, Jinn-Jer Peir, Chen-Wei Chi, Jenq-Horng Liang

ICONE 2010; 481-485doi:https://doi.org/10.1115/ICONE18-29253

Abstract

View Articletitled, A Parametric Study of Fuel Lattice Design for HTR-10

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Topics: Design , Fuels , Neutrons , Absorption , Computation , Computers , Energy levels (Quantum mechanics) , Sensors , Simulation , Stability

Dialogue Process Between Expert and Public Regarding HLW Disposal in Japan

Masashi Furukawa, Hiroshi Kimura, Haruki Madarame, Daisuke Sugiyama, Taiji Chida

ICONE 2010; 487-495doi:https://doi.org/10.1115/ICONE18-29283

Abstract

View Articletitled, Dialogue Process Between Expert and Public Regarding HLW Disposal in Japan

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Topics: Nuclear power , Safety , Uncertainty

Development of Real-Time Thermal-Hydraulic Analysis Code for Plate Type Fuel Reactor

Lei Li, Zhijian Zhang

ICONE 2010; 497-505doi:https://doi.org/10.1115/ICONE18-29297

Abstract

View Articletitled, Development of Real-Time Thermal-Hydraulic Analysis Code for Plate Type Fuel Reactor

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Topics: Fuels

Risk Importance Measures for Maintenance in Non-Coherent Systems

Ye Tao, Lixuan Lu

ICONE 2010; 507-516doi:https://doi.org/10.1115/ICONE18-29321

Abstract

View Articletitled, Risk Importance Measures for Maintenance in Non-Coherent Systems

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Topics: Maintenance , Risk , Nuclear power stations , Boilers , Control systems , Probabilistic safety assessment , Safety

Dimensionless Analysis of Pressure Drop and Heat Transfer on HTGR Coupled With Closed Brayton Cycle

Zhenjia Yu, Xiaoyong Yang, Xiaoli Yu, Jie Wang

ICONE 2010; 517-525doi:https://doi.org/10.1115/ICONE18-29344

Abstract

View Articletitled, Dimensionless Analysis of Pressure Drop and Heat Transfer on HTGR Coupled With Closed Brayton Cycle

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Topics: Brayton cycle , Heat transfer , Pressure drop , Very high temperature reactors

Thermal Hydraulics Behavior Around a Single Heated Rod With Sodium-Water Reaction (1)

Hideyuki Kudoh, Masanori Nishizaki, Ken-ichiro Sugiyama, Hiroyuki Ohshima

ICONE 2010; 527-532doi:https://doi.org/10.1115/ICONE18-29388

Abstract

View Articletitled, Thermal Hydraulics Behavior Around a Single Heated Rod With Sodium-Water Reaction (1)

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Topics: Sodium , Thermal hydraulics , Water , Heat transfer , Liquid metal fast breeder reactors , Safety , Temperature , Boilers , Chemical reactions , Chemistry

Thermal Neutron Cross Sections of Cold-Moderators

Guanbo Wang, Bin Zhong, Kan Wang, Ganglin Yu

ICONE 2010; 533-536doi:https://doi.org/10.1115/ICONE18-29408

Abstract

View Articletitled, Thermal Neutron Cross Sections of Cold-Moderators

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Topics: Cross section (Physics) , Neutrons , Neutron sources , Density , Electromagnetic scattering , Methane , Protons , Radiation scattering , Scattering (Physics) , Spectra (Spectroscopy)

Heat Transfer Characteristics of a Circular Channel Inserted Metallic Wire With High Porosity

Mitsutoshi Tendo, Tetsuaki Takeda

ICONE 2010; 537-542doi:https://doi.org/10.1115/ICONE18-29421

Abstract

View Articletitled, Heat Transfer Characteristics of a Circular Channel Inserted Metallic Wire With High Porosity

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Topics: Heat transfer , Porosity , Wire , Copper , Fins , Heat exchangers , Design , Flow (Dynamics) , Fluids , Forced convection

Compact Engineering Simulator for HTR-PM by Embedding THERMIX Code in vPower Simulation Platform

Qiang Gao, Yangping Zhou, Zhiwei Zhou, Zhe Sui, Yuanle Ma, Fu Li

ICONE 2010; 543-549doi:https://doi.org/10.1115/ICONE18-29437

Abstract

View Articletitled, Compact Engineering Simulator for HTR-PM by Embedding THERMIX Code in vPower Simulation Platform

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Topics: Simulation , Design , Boilers , Cycles , Energy generation , Machinery , Safety , Simulation results , Steam , Very high temperature reactors

Exponential Function Expansion Nodal Diffusion Method

Yunzhao Li, Hongchun Wu, Liangzhi Cao, Qichang Chen

ICONE 2010; 551-555doi:https://doi.org/10.1115/ICONE18-29447

Abstract

View Articletitled, Exponential Function Expansion Nodal Diffusion Method

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Topics: Diffusion (Physics) , Geometry , Neutrons

CFD Analysis of PWR Core Top Region: Top Fuel Assembly and Top Nozzle Regions

Chung-Yun Wu, Min-Tsung Kao, Ching-Chang Chieng, Kun Yuan, Yiban Xu, Milorad B. Dzodzo, Michael E. Conner, Steven A. Beltz, Sumit Ray

ICONE 2010; 557-564doi:https://doi.org/10.1115/ICONE18-29463

Abstract

View Articletitled, CFD Analysis of PWR Core Top Region: Top Fuel Assembly and Top Nozzle Regions

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Topics: Computational fluid dynamics , Fuels , Manufacturing , Nozzles , Pressurized water reactors , Flow (Dynamics) , Computation , Pressure , Reactor vessels , Computer software

Model Development of Turbulent Dispersion Force for Advanced Two-Fluid Model in Consideration of Bubble-Liquid Phase Interactions

Hideaki Hosoi, Hiroyuki Yoshida

ICONE 2010; 565-571doi:https://doi.org/10.1115/ICONE18-29517

Abstract

View Articletitled, Model Development of Turbulent Dispersion Force for Advanced Two-Fluid Model in Consideration of Bubble-Liquid Phase Interactions

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Topics: Bubbles , Fluids , Model development , Turbulent diffusion , Kinetic energy , Constitutive equations , Turbulence , Two-phase flow , Deformation , Drops

Characteristics of Cavitation and Erosion Phenomena in Sodium Flow

Teddy Ardiansyah, Makoto Asaba, Kuniaki Miura, Minoru Takahashi

ICONE 2010; 573-579doi:https://doi.org/10.1115/ICONE18-29545

Abstract

View Articletitled, Characteristics of Cavitation and Erosion Phenomena in Sodium Flow

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Topics: Cavitation , Erosion , Flow (Dynamics) , Sodium , Venturi tubes , Bubbles , Pressure , Sodium fast reactors , Cavities , Cladding systems (Building)

Structural Design of S-Bend Box for ITER Feeder Based on Optimization Technique of ANSYS

Biao Dong, Kai-song Wang, Yun-tao Song

ICONE 2010; 581-586doi:https://doi.org/10.1115/ICONE18-29546

Abstract

View Articletitled, Structural Design of S-Bend Box for ITER Feeder Based on Optimization Technique of ANSYS

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Topics: Design , Optimization , Structural design , Stress , Stress concentration , Displacement , Finite element analysis , Modeling , Pressure , Reliability

Numerical Research on Oscillation of Two-Phase Flow Under Rolling Motion

Y. J. Zhang, G. H. Su, S. Z. Qiu, H. Li

ICONE 2010; 587-598doi:https://doi.org/10.1115/ICONE18-29550

Abstract

View Articletitled, Numerical Research on Oscillation of Two-Phase Flow Under Rolling Motion

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Topics: Chaos , Oscillations , Stability , Two-phase flow

Study on the Interfacial Behavior and Thermal Characteristics in Liquid-Vapor Flow of the Supersonic Steam Injector

Shunsuke Shibayama, Yutaka Abe, Akiko Kaneko, Akira Fukuichi, Chikako Iwaki, Tadashi Narabayashi, Michitsugu Mori, Shuichi Ohmori

ICONE 2010; 599-608doi:https://doi.org/10.1115/ICONE18-29568

Abstract

View Articletitled, Study on the Interfacial Behavior and Thermal Characteristics in Liquid-Vapor Flow of the Supersonic Steam Injector

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Topics: Ejectors , Flow (Dynamics) , Vapors , Water , Heat , Momentum , Steam , Boundary layers , Condensation , Enthalpy

Prediction of Pressure Drop in Air-Water Two Phase Upflow Through Packed Bed

Nan Zhang, Zhongning Sun

ICONE 2010; 609-614doi:https://doi.org/10.1115/ICONE18-29572

Abstract

View Articletitled, Prediction of Pressure Drop in Air-Water Two Phase Upflow Through Packed Bed

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Topics: Pressure drop , Water , Flow (Dynamics) , Particulate matter , Porosity , Glass , Reynolds number , Transparency

Preliminary Study of Influence of Severe Accident Mitigation Countermeasures to In-Vessel Release of Fisson Products

Gaofeng Huang, Xuewu Cao, Jingxi Li

ICONE 2010; 615-621doi:https://doi.org/10.1115/ICONE18-29585

Abstract

View Articletitled, Preliminary Study of Influence of Severe Accident Mitigation Countermeasures to In-Vessel Release of Fisson Products

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Topics: Accidents , Countermeasures , Vessels

Solids Formation Behavior of Simulated High-Level Liquid Waste During Long-Term Storage

Jin Chen, Xuegang Liu, Yanchao Zhang, Qian’ge He, Jianchen Wang

ICONE 2010; 623-627doi:https://doi.org/10.1115/ICONE18-29590

Abstract

View Articletitled, Solids Formation Behavior of Simulated High-Level Liquid Waste During Long-Term Storage

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Topics: Solids , Storage , Precipitation , Zirconium , Hazards , Light water reactors , Nuclear fission , Separation (Technology) , Spent nuclear fuels , Stability

Collapse Limit of Water Jetting With Surface Condensation in Steam Injector

Ryuhei Ikuta, Yasuo Koizumi, Hiroyuki Yoshida

ICONE 2010; 629-634doi:https://doi.org/10.1115/ICONE18-29612

Abstract

View Articletitled, Collapse Limit of Water Jetting With Surface Condensation in Steam Injector

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Topics: Collapse , Condensation , Ejectors , Water

Experimental Study on Jet Breakup Behavior With Surface Solidification

Takashi Wada, Yutaka Abe, Akiko Kaneko, Yuta Uchiyama, Hideki Nariai, Makoto Yamagishi, Kazuya Koyama, Kazuhiro Itoh

ICONE 2010; 635-644doi:https://doi.org/10.1115/ICONE18-29618

Abstract

View Articletitled, Experimental Study on Jet Breakup Behavior With Surface Solidification

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Topics: Accidents , Alloys , Breeder reactors , Coolants , Density , Design , Heat , Image processing , Reactor vessels , Safety

Image Analysis of Carry-Under by Falling Liquid Flow

Tomohiko Ohtsuka, Naoki Haraguchi, Hiroyasu Ohtake, Yasuo Koizumi

ICONE 2010; 645-649doi:https://doi.org/10.1115/ICONE18-29631

Abstract

View Articletitled, Image Analysis of Carry-Under by Falling Liquid Flow

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Topics: Flow (Dynamics) , Water , Waves , Nozzles , Bubbles , Video cameras

Study on Corrosion Control in Reactors Using Radiation Induced Surface Activation (RISA): Mechanism Behind Stainless Steel Durability Due to RISA Against Crevice Corrosion

Shogo Mabuchi, Tatsuya Hazuku, Shin-ichi Motoda, Tomoji Takamasa, Susumu Uematsu, Mashiro Furuya

ICONE 2010; 651-656doi:https://doi.org/10.1115/ICONE18-29633

Abstract

View Articletitled, Study on Corrosion Control in Reactors Using Radiation Induced Surface Activation (RISA): Mechanism Behind Stainless Steel Durability Due to RISA Against Crevice Corrosion

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Topics: Corrosion , Corrosion protection , Durability , Radiation (Physics) , Stainless steel , Corrosion resistant materials , Seawater , Coating processes , Coatings , Ions

Effect of Gravity on Phase Distribution Patterns of Bubbly Two-Phase Flow in a Vertical Mini Pipe

Shunichi Watanabe, Yutaka Fukuhara, Tatsuya Hazuku, Tomoji Takamasa, Takashi Hibiki

ICONE 2010; 657-664doi:https://doi.org/10.1115/ICONE18-29636

Abstract

View Articletitled, Effect of Gravity on Phase Distribution Patterns of Bubbly Two-Phase Flow in a Vertical Mini Pipe

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Topics: Gravity (Force) , Pipes , Two-phase flow , Bubbles , Databases , Bubbly flow , Flow (Dynamics) , Flow measurement , Image processing , Nitrogen

Experimental Investigation of Freezing Behavior of Melt/Solid Particles Mixture on to Metal Structure

Md. Abdul Malek Soner, Shunichi Seo, Yu Hasegawa, Yusuke Himuro, Koji Morita, Tatsuya Matsumoto, Kenji Fukuda, Werner Maschek

ICONE 2010; 665-673doi:https://doi.org/10.1115/ICONE18-29708

Abstract

View Articletitled, Experimental Investigation of Freezing Behavior of Melt/Solid Particles Mixture on to Metal Structure

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Topics: Freezing , Metalwork , Particulate matter , Metals , Flow (Dynamics) , Safety , Accidents , Brass (Metal) , Copper , Databases

Effect of Melting Processing on Tensile Properties and Microstructure of New RAFM Steel

Jun Yao, Jinping Suo

ICONE 2010; 675-680doi:https://doi.org/10.1115/ICONE18-29724

Abstract

View Articletitled, Effect of Melting Processing on Tensile Properties and Microstructure of New RAFM Steel

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Topics: Melting , Slags , Steel , Tensile strength

Large Eddy Simulations of Jet Flow Interaction Within Staggered Rod Bundles

Nathaniel Salpeter, Yassin Hassan

ICONE 2010; 681-691doi:https://doi.org/10.1115/ICONE18-29737

Abstract

View Articletitled, Large Eddy Simulations of Jet Flow Interaction Within Staggered Rod Bundles

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Topics: Fuel rods , Jets , Large eddy simulation , Turbulence , Wear , Abrasion , Cylinders , Engineering simulation , Gas flow , Graphite

Modeling the Spectral History in the Depletion of a PWR Core

I. Bilodid

ICONE 2010; 693-700doi:https://doi.org/10.1115/ICONE18-29748

Abstract

View Articletitled, Modeling the Spectral History in the Depletion of a PWR Core

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Topics: Cross section (Physics) , Density , Errors , Fuels , Modeling , Power density , Pressurized water reactors , Uranium

Simulation of Heavy Ion Source-Drain Penetration Effect in SOI MOS and Bulk MOS

Yonghong Li, Chaohui He, Chunmei Xia

ICONE 2010; 701-704doi:https://doi.org/10.1115/ICONE18-29782

Abstract

View Articletitled, Simulation of Heavy Ion Source-Drain Penetration Effect in SOI MOS and Bulk MOS

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Topics: Silicon-on-insulator , Simulation , Silicon

Thermal Aspects of Using Uranium Nitride in SuperCritical Water-Cooled Nuclear Reactors

Lisa Grande, Wargha Peiman, Sally Mikhael, Bryan Villamere, Adrianexy Rodriguez-Prado, Leyland Allison, Igor Pioro

ICONE 2010; 705-712doi:https://doi.org/10.1115/ICONE18-29790

Abstract

View Articletitled, Thermal Aspects of Using Uranium Nitride in SuperCritical Water-Cooled Nuclear Reactors

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Topics: Nuclear reactors , Uranium , Water , Fuels , Temperature , Supercritical water reactors , Nuclear fuels , Coolants , Design , Fluids

The Research on Scale of Cluster Fuel Assembly Spacer Grids

Jie Chen, Bingde Chen, Hong Zhang

ICONE 2010; 713-719doi:https://doi.org/10.1115/ICONE18-29835

Abstract

View Articletitled, The Research on Scale of Cluster Fuel Assembly Spacer Grids

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Topics: Fuels , Manufacturing

Advances in Inverse Transport Methods

Zeyun Wu, Marvin L. Adams

ICONE 2010; 721-727doi:https://doi.org/10.1115/ICONE18-29881

Abstract

View Articletitled, Advances in Inverse Transport Methods

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Topics: Cross section (Physics) , Dimensions , Electromagnetic scattering , Neutrons , Optimization , Radiation (Physics) , Radiation scattering , Scattering (Physics) , Sensors

Experimental Investigation of Reactor Cavity Cooling System (RCCS) for a Very High Temperature Reactor (VHTR)

L. Capone, C. E. Perez, Y. Hassan

ICONE 2010; 729-738doi:https://doi.org/10.1115/ICONE18-29918

Abstract

View Articletitled, Experimental Investigation of Reactor Cavity Cooling System (RCCS) for a Very High Temperature Reactor (VHTR)

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Topics: Cavities , Cooling systems , Very high temperature reactors , Cooling , Vessels , Temperature , Pipes , Temperature profiles , Flow (Dynamics) , Water

RBMK Fuel Rod Modelling and Investigation of Process During Operation Cycle

Tadas Kaliatka, Ausˇra Marao, Renatas Karalevicˇius, Eugenijus Usˇpuras

ICONE 2010; 739-745doi:https://doi.org/10.1115/ICONE18-29952

Abstract

View Articletitled, RBMK Fuel Rod Modelling and Investigation of Process During Operation Cycle

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Topics: Cycles , Fuel rods , Modeling , Cladding systems (Building) , Fuels , Spent nuclear fuels , Deformation , Fuel storage , Residual stresses , Safety

Design Concept and Heat Transfer Analysis for a Double Pipe Channel for SCWR Type Reactors

J. Samuel, G. D. Harvel, I. Pioro

ICONE 2010; 747-754doi:https://doi.org/10.1115/ICONE18-29956

Abstract

View Articletitled, Design Concept and Heat Transfer Analysis for a Double Pipe Channel for SCWR Type Reactors

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Topics: Design , Heat transfer , Pipes , Supercritical water reactors , Annulus , Flow (Dynamics) , Fuels , Coolants , Pressure , Temperature

Steam-Reheat Options for Pressure-Tube SCWRs

Eugene Saltanov, Wargha Peiman, Amjad Farah, Krysten King, Maria Naidin, Igor Pioro

ICONE 2010; 755-766doi:https://doi.org/10.1115/ICONE18-29972

Abstract

View Articletitled, Steam-Reheat Options for Pressure-Tube SCWRs

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Topics: Pressure , Steam , Supercritical water reactors , Nuclear reactors , Nuclear power stations , Water , Temperature , Thermal efficiency , Boilers , Boiling

Thermal Aspects of Using Uranium Dicarbide Fuel in an SCWR at Maximum Heat-Flux Conditions

Caleb Pascoe, Ashley Milner, Hemal Patel, Wargha Peiman, Graham Richards, Lisa Grande, Igor Pioro

ICONE 2010; 767-774doi:https://doi.org/10.1115/ICONE18-29974

Abstract

View Articletitled, Thermal Aspects of Using Uranium Dicarbide Fuel in an SCWR at Maximum Heat-Flux Conditions

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Topics: Fuels , Heat flux , Supercritical water reactors , Uranium , Temperature , Design , Water , Pressure , Cycles , Fluids

Thermal Aspects of Using Thorium Dioxide as Alternative Nuclear Fuel in SuperCritical Water-Cooled Reactors

Hemal Patel, Ashley Milner, Caleb Pascoe, Wargha Peiman, Graham Richards, Lisa Grande, Igor Pioro

ICONE 2010; 775-781doi:https://doi.org/10.1115/ICONE18-29975

Abstract

View Articletitled, Thermal Aspects of Using Thorium Dioxide as Alternative Nuclear Fuel in SuperCritical Water-Cooled Reactors

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Topics: Nuclear fuels , Water , Fuels , Temperature , Nuclear power stations , Supercritical water reactors , Steam , Cycles , Boilers , Circuits

Comparison of Selected Forced-Convection Supercritical-Water Heat-Transfer Correlations for Vertical Bare Tubes

Amjad Farah, Krysten King, Sahil Gupta, Sarah Mokry, Wargha Peiman, Igor Pioro

ICONE 2010; 783-792doi:https://doi.org/10.1115/ICONE18-29990

Abstract

View Articletitled, Comparison of Selected Forced-Convection Supercritical-Water Heat-Transfer Correlations for Vertical Bare Tubes

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Topics: Forced convection , Heat transfer , Water , Nuclear power stations , Flux (Metallurgy) , Heat exchangers , Pressure , Temperature , Combined heat and power , Cycles

Comparison of Three-Rod Bundle Data With Existing Heat-Transfer Correlations for Bare Vertical Tubes

Krysten King, Amjad Farah, Sahil Gupta, Sarah Mokry, Igor Pioro

ICONE 2010; 793-799doi:https://doi.org/10.1115/ICONE18-29991

Abstract

View Articletitled, Comparison of Three-Rod Bundle Data With Existing Heat-Transfer Correlations for Bare Vertical Tubes

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Topics: Heat transfer , Temperature , Supercritical water reactors , Water , Heat flux

Thermal Aspects of Using Uranium Mononitride Fuel in a SuperCritical Water-Cooled Reactor at Maximum Heat Flux Conditions

Ashley Milner, Caleb Pascoe, Hemal Patel, Wargha Peiman, Graham Richards, Igor Pioro

ICONE 2010; 801-808doi:https://doi.org/10.1115/ICONE18-29998

Abstract

View Articletitled, Thermal Aspects of Using Uranium Mononitride Fuel in a SuperCritical Water-Cooled Reactor at Maximum Heat Flux Conditions

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Topics: Fuels , Heat flux , Uranium , Water , Supercritical water reactors , Temperature , Nuclear power stations , Light water reactors , Thermal efficiency , Generation IV reactors

Developing New Heat-Transfer Correlation for SuperCritical-Water Flow in Vertical Bare Tubes

Sahil Gupta, Amjad Farah, Krysten King, Sarah Mokry, Igor Pioro

ICONE 2010; 809-817doi:https://doi.org/10.1115/ICONE18-30024

Abstract

View Articletitled, Developing New Heat-Transfer Correlation for SuperCritical-Water Flow in Vertical Bare Tubes

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Topics: Flow (Dynamics) , Heat transfer , Water , Wall temperature , Supercritical water reactors , Fluids , Heat exchangers , Nuclear power stations , Combined heat and power , Computational fluid dynamics

Design Study on Power Flattening to Sodium Cooled Large-Scale CANDLE Burning Reactor With Using Thorium Fuel

Tsuyoshi Okawa, Sinsuke Nakayama, Hiroshi Sekimoto

ICONE 2010; 819-824doi:https://doi.org/10.1115/ICONE18-30063

Abstract

View Articletitled, Design Study on Power Flattening to Sodium Cooled Large-Scale CANDLE Burning Reactor With Using Thorium Fuel

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Topics: Combustion , Design , Fuels , Sodium , Power density , Uranium , Neutrons , Coolants , Leakage , Shapes

Heat-Loss Calculations in a SCWR Fuel-Channel

Wargha Peiman, Eugene Saltanov, Kamiel Gabriel, Igor Pioro

ICONE 2010; 825-833doi:https://doi.org/10.1115/ICONE18-30069

Abstract

View Articletitled, Heat-Loss Calculations in a SCWR Fuel-Channel

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Topics: Fuels , Heat losses , Supercritical water reactors , Pressure , Annulus , Coolants , Nuclear power stations , Temperature , Computer programming , Computer software

Measurement of the Dynamical Mass Transfer of a Single CO₂ Bubble Using LIF/HPTS Visualization and a Photoelectric Optical Fiber Probe

Kodai Hanyu, Takayuki Saito

ICONE 2010; 835-843doi:https://doi.org/10.1115/ICONE18-30073

Abstract

View Articletitled, Measurement of the Dynamical Mass Transfer of a Single CO<sub>2</sub> Bubble Using LIF/HPTS Visualization and a Photoelectric Optical Fiber Probe

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Topics: Bubbles , Carbon dioxide , Mass transfer , Optical fiber , Probes , Visualization , Wakes , Buoyancy , Two-phase flow , Vortices

SuperCritical Water-Cooled Nuclear Reactor With Intermediate Heat Exchangers

H. Thind, I. Pioro, G. Harvel

ICONE 2010; 845-854doi:https://doi.org/10.1115/ICONE18-30104

Abstract

View Articletitled, SuperCritical Water-Cooled Nuclear Reactor With Intermediate Heat Exchangers

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Topics: Heat exchangers , Nuclear reactors , Water , Nuclear power stations , Supercritical water reactors , Cycles , Pressurized water reactors , Contamination , Dimensions , Heat transfer

Towards Understanding Melt Eruption Phenomena During Molten Corium Concrete Interactions

Kevin R. Robb, Michael L. Corradini

ICONE 2010; 855-864doi:https://doi.org/10.1115/ICONE18-30116

Abstract

View Articletitled, Towards Understanding Melt Eruption Phenomena During Molten Corium Concrete Interactions

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Topics: Concretes , Cooling , Flow (Dynamics) , Modeling , Vessels , Accidents , Defense industry , Design , Geometry , Light water reactors

Analysis of Operator Responses to Mitigate Temperature Rise in Electrical Auxiliary Building

M. James Hardy, Matthew F. King, Ryan Bigelow

ICONE 2010; 865-871doi:https://doi.org/10.1115/ICONE18-30119

Abstract

View Articletitled, Analysis of Operator Responses to Mitigate Temperature Rise in Electrical Auxiliary Building

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Topics: Temperature , Computational fluid dynamics , Heat , Air conditioning , Damage , Energy budget (Physics) , HVAC equipment , Probabilistic risk assessment , Probability , Simulation

Clarification of Ejection and Sweep in Rectangular Channel Turbulent Flow

Muhammad Kunta Biddinika, Noriyuki Watanabe, Masanori Aritomi, Hiroshige Kikura

ICONE 2010; 873-878doi:https://doi.org/10.1115/ICONE18-30148

Abstract

View Articletitled, Clarification of Ejection and Sweep in Rectangular Channel Turbulent Flow

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Topics: Turbulence , Flow (Dynamics) , Ultrasonic measurement

Advanced MOX and IMF Fuel Assembly Designs for Multi-Recycling Transuranics

Yunhuang Zhang, Jean C. Ragusa

ICONE 2010; 879-885doi:https://doi.org/10.1115/ICONE18-30153

Abstract

View Articletitled, Advanced MOX and IMF Fuel Assembly Designs for Multi-Recycling Transuranics

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Topics: Fuels , Manufacturing , Recycling , Pins (Engineering) , Uranium , Coating processes , Coatings , Pressurized water reactors , Simulation , Spent nuclear fuels

Isotope-Based Analysis of Nuclear Waste Repository Performance

Joosep Pata, Alan H. Tkaczyk

ICONE 2010; 887-893doi:https://doi.org/10.1115/ICONE18-30173

Abstract

View Articletitled, Isotope-Based Analysis of Nuclear Waste Repository Performance

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Topics: Isotopes , Radioactive wastes , Decision making , Nuclear fission , Robustness , Safety , Sensitivity analysis

Nuclear Analysis During Modification of NPP Core

Andrius Slavickas

ICONE 2010; 895-900doi:https://doi.org/10.1115/ICONE18-30177

Abstract

View Articletitled, Nuclear Analysis During Modification of NPP Core

PDF

Topics: Nuclear power stations , Fuels , Neutrons , Design , Rods , Stress , Accidents , Computer software , Graphite , Safety

Analysis of Updated SuperCritical Water Heat Transfer Correlations for Vertical Bare Tubes

Sarah Mokry, Sahil Gupta, Amjad Farah, Krysten King, Igor Pioro

ICONE 2010; 901-912doi:https://doi.org/10.1115/ICONE18-30192

Abstract

View Articletitled, Analysis of Updated SuperCritical Water Heat Transfer Correlations for Vertical Bare Tubes

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Topics: Heat transfer , Water , Temperature , Fuels , Supercritical water reactors , Coolants , Fluids , Wall temperature , Computers , Convection

Experimental Turbulence Analysis of Fuel Bundle With Spacer Grids

Elvis Dominguez-Ontiveros, Carlos Estrada-Perez, Yassin Hassan

ICONE 2010; 913-922doi:https://doi.org/10.1115/ICONE18-30225

Abstract

View Articletitled, Experimental Turbulence Analysis of Fuel Bundle With Spacer Grids

PDF

Topics: Computational fluid dynamics , Fuel rods , Fuels , Refractive index , Turbulence , Rods , Databases , Engineering simulation , Simulation , Boilers