Proceedings of the

18th International Conference

on Nuclear Engineering

- 2010 -

VOLUME 2

REACTOR PHYSICS AND TRANSPORT THEORY

NUCLEAR EDUCATION, PUBLIC ACCEPTANCE AND

RELATED ISSUES

STUDENT PAPER COMPETITION

presented at

18th international conference on nuclear engineering

MAY 17-21, 2010

XI'AN, china

sponsored by

NUCLEAR ENGINEERING DIVISION, ASME

THE JAPAN SOCIETY OF MECHANICAL ENGINEERS, JSMi

THE CHINESE NUCLEAR SOCIETY, CNS

ASME

Three Park Avenue New York, N.Y. 10016

CONTENTS

REACTOR PHYSICS AND TRANSPORT THEORY

ICONE18-29070 1

A Predictor-Corrector Scheme for the Microscopic Depletion Solver of the

COCAGNE Core Code

Fabrice Hoareau, Nadine Schwartz, and David Couyras

ICONE18-29154 9

Verification and Validation of AEGIS/SC0PE2: The State-of-the-Art In-Core Fuel

Management System for PWRs

Masahiro Tatsumi, Yasunori Ohoka, Tomohiro Endo, Naoki Sugimura, Masato Tabuchi,Hideaki Hyoudou, Tadashi Ushio, Masaaki Mori, and Akio Yamamoto

ICONE18-29188,

17

Validation of SIMMER-MI Neutronics Module for the Simulation of Reactivity InjectionAccident in Material Testing Reactors

Yacine Chegrani, Corinne D'Aletto, Jacques Di Salvo, and Evgeny Ivanov

ICONE18-29221 27

Validation of a New Lattice Physics Code GALAXY for PWRs

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

ICONE18-29252 35

Evaluation Technique With MCNP for Temperature Dependent Problems

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

ICONE18-29254 43

Validation of a New Core Simulator COSMO-S for PWRs

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

ICONE18 29279 49

Study of the Space-Time Neutron Multiplication FormulaJianli Hao, Wenzhen Chen, Shaoming Wang, and De Zhang

ICONE18-29285 55

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

Yoshihiko ishii, Kazuaki Kitou, Tomohiko Ikegawa, Shin Hasegawa, and Hitoshi Ochi

ICONE18-29315 63

A New Method on Flux Mapping by Function ExpansionBin Zhong, Kan Wang, and Ganglin Yu

ICONE18-29373 69

Conceptual Design of CANDU-SCWR With Thermal-Hydraulics CouplingPing Yang, Liangzhi Cao, Hongchun Wu, and Changhui Wang

vii

ICONE18-29420 79

Acceleration Technique Using Krylov Subspace Methods for 2D Arbitrary GeometryCharacteristics Solver

Hongbo Zhang, Hongchun Wu, and Liangzhi Cao

ICONE18-29425 89Direct 3D MOC for Whole-Core Transport Calculation

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

ICONE18-29429 97Neutron Transport Solution Using the Daubechies' Wavelets in the Spatial Discretization

Youqi Zheng, Hongchun Wu, and Liangzhi Cao

ICONE18-29439 107

EPR: A Reactor to Support Economical Fuel CyclesS. Zheng, R. Meinl, and J. Stephens

ICONE18-29442 113

Determinant Methods for Solving Neutron Transport Equation in Unstructured GeometryHongchun Wu, Guoming Liu, Liangzhi Cao, and Qichang Chen

ICONE18-29481 119

Self-Shielding and Criticality Calculation in Spent Fuel Dissolving Vessel

Qingjie Liu, Hongchun Wu, and Liangzhi Cao

ICONE18-29482 127RMC1.0: Development of Monte Carlo Code for Reactor Analysis

Ding She, Qi Xu, Kan Wang, and Ganglin Yu

ICONE18-29491 133Resonance Calculation Code UFOP Based on the Hyper-Fine Group Neutron Resonance

Calculation Method

Yulong Qin, Hongchun Wu, Liangzhi Cao, and Qingjie Liu

ICONE18-29498 143

Study of Self-Shielding Calculation With Temperature Distribution:

Applying Wavelets Scaling Function Expansion Continuous-Energy Resonance Method

Weiyan Yang, Hongchun Wu, and Liangzhi Cao

ICONE18-29518 151

Analytic Basis Function Expansion Nodal Method for Neutron Diffusion Equations in

Triangular GeometryKunpeng Wang, Hongchun Wu, Liangzhi Cao, and Changhui Wang

ICONE18-29533 159A Method of Optimized Utilization of Point-Wise Data Format in Monte Carlo Code

Yuxuan Liu, Ganglin Yu, and Kang Wang

ICONE18-29540 167Treatment of Neutron Cross-Section With Interpolation

Xiang Zhang, Ganglin Yu, Guangwen Bi, and Kan Wang

viii

ICONE18-29547 175

Effect of Pin and Subassembly Heterogenity in Sodium Void Worth Calculations

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

ICONE18-29548 181

The Consistency of WIMS-D Library and ACE Format LibraryZhiyan Liu, Hongchun Wu, Liangzhi Cao, and Qingjie Liu

ICONE18-29562 189

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

Analysis Methods

Hessam Malmir, Naser Vosoughi, and Ehsan Zahedinejad

ICONE18-29563 197

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

Engineering Test Reactor

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

ICONE18-29614 205

High Performance Reconfigurable Hardware Acceleration on Neutron TransportComputation Based on AGENT Methodology

Shanjie Xiao and Tatjana Jevremovic

ICONE18-29638 211

Solving the Time-Dependent Transport Equation Using Time-Dependent Method of

Characteristics and Rosenbrock Method

Xue Yang and Tatjana Jevremovic

ICONE18-29654 217

Decay Heat Benchmark for Uranium-Free Fuels With Minor Actinides

Andrei Rineiski, Gerald Rimpault, Georgios Glinatsis, Nadia Messaoudi, Sandro Pelloni,Aleksandra Schwenk-Ferrero, and Maria Carmen Vicente

ICONE18-29691 227

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

BWR Fuel Assemblies

Flavio D. Giust, Peter Grimm, and Rakesh Chawla

ICONE18-29709 237On Line Monitoring the Reactor Power Distribution Based on the Data Library of the

EigenfunctionsChanghui Wang, Hongchun Wu, and Liangzhi Cao

ICONE18-29763 245

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

Peter G. Boczar, Bronwyn Hyland, and Erik Hagberg

ICONE18-29971 251

Monte Carlo Simulation Compared With Classic Deterministic Solutions for Neutron

Transport and Diffusion

Zafar Ullah Koreshi and Sadaf Siddiq

ix

ICONE18-30017 259

DeCART Depletion Calculation for PMR200 Two-Dimensional Core

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

ICONE18-30046 267

Resonance Calculation for Large and Complicated Geometry Using Tone's Method by

Incorporating the Method of Characteristics

Yu Hao, Akio Yamamoto, and Yoshihiro Yamane

ICONE18-30159 275

Calculation of Fuel Burn Up and Radioactive Inventory for HEU Fuel Element of

Tehran Research Reactor

Seyed Abolfazl Hosseini, Naser Vosoughi, and Mohammad Hosseini

ICONE18-30160 281

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

Ali Jahanbin and Mehrdad Boroushaki

ICONE18-30195 287

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

Resonance IntegralsSitao Peng, Shaohong Zhang, and Xiaofeng Jiang

ICONE18-30203 297

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. Gonzalez, A. Concejal, P. Ortego, and

J, Melara

ICONE18-30212 303

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

Charlotta E. Sanders

ICONE18-30310 311

Depletion Calculation for a Nodal Reactor Physics Code

Antonio Carlos Marques Alvim, Fernando Carvalho da Silva, and

Aquilino Senra Martinez

ICONE18-30370 317

Wavelets Scaling Function Expansion Resonance Self-Shielding Calculation

Based on the DDPM

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

NUCLEAR EDUCATION, PUBLIC ACCEPTANCE AND RELATED ISSUES

ICONE18-29183 323Reactor Experiments Course of the Swiss Nuclear Engineering Master

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

x

ICONE18-29218 331

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. Kroger, H. M. Prasser, and

M. Q. Tran

ICONE18-29271 341

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

Hidekazu Yoshikawa

ICONE18-29327 347

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

Gary M. Sandquist and Jay F. Kunze

ICONE18-29340 355

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

Hiroshi Kimura, Masashi Furukawa, Daisuke Sugiyama, and Taiji Chida

ICONE18-29416 361

Economic Analysis on MOX Fuels

Shizhuang Jia, Liangzhi Cao, and Hongchun Wu

ICONE18-29460 367

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

External Factors

Giorgio Locatelli, Mauro Mancini, and Alessandro Galli

ICON El 8-29781 381

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

Bangladesh PerspectiveA. S. Mollah

ICONE18-29798 385

Study on HSE Management System of AP1000 Nuclear Plant ProjectXiaogang He, Xiaopeng Fang, Wei Zhong, Yanli Yang, and Zhiyou Sun

ICONE18-29824 391

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

Glenn Harvel and Wendy Hardman

ICONE18-29841 403

Misunderstanding Regarding to Global Warming and Nuclear Power

Chiyokazu Fukae

ICONE18-29883 409

Comparison of Publicity Materials Pertaining to the Selection of High Level Radioactive

Waste Repository Sites

Noriko Kanzaki, Koji Okamoto, and Ftyutaro Wada

xi

ICONE18-29983..... 415

Reform of Nuclear Safety Education for Non-Nuclear Engineering Students

Qinghai Luo and Zhuying Zou

ICONE18-30111 421

The Progress of ICRP New Recommendations

Aiguo Shang, Changjie Lu, and Jin Qin

ICONE18-30215 425

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

DevelopmentChris M. Allison, Brian S. Allison, Uwe Luttringhaus, and Judith K. Hohorst

STUDENT PAPER COMPETITION

ICONE18-29007 431

Probabilistic Safety Assessment to the 1000 MWe NPP During Shutdown Conditions

Lin Li and Bo Zhao

ICONE18-29099 447

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

Marija Miletic

ICONE18-29173 457

Peculiarities of Hydrodynamics of Lead and Lead-Bismuth Coolant Flows of Reactor LoopsP. A. Bokov, V. S. Baranova, M. S. Kustov, M. A. Antonenkov, A. G. Meluzov, and

A. V. Besnosov

ICONE18-29175 463

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, and A. V. Besnosov

ICONE18-29198 471

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

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

ICONE18-29253 481

A Parametric Study of Fuel Lattice Design for HTR-10

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

ICONE18-29283 487

Dialogue Process Between Expert and Public Regarding HLW Disposal in JapanMasashi Furukawa, Hiroshi Kimura, Haruki Madarame, Daisuke Sugiyama, and

Taiji Chida

ICONE18-29297 497

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

Li Lei and Zhijian Zhang

xii

ICONE18-29321 507

Risk Importance Measures for Maintenance in Non-Coherent SystemsYe Tao and Lixuan Lu

ICONE18-29344 517

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

Closed Brayton Cycle

Zhenjia Yu, Xiaoyong Yang, Xiaoli Yu, andJie Wang

ICONE18-29388 527

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

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

ICONE18-29408 533

Thermal Neutron Cross Sections of Cold-Moderators

Guanbo Wang, Bin Zhong, Kan Wang, and Ganglin Yu

ICONE18-29421 537

Heat Transfer Characteristics of a Circular Channel Inserted Metallic Wire With High PorosityMitsutoshi Tendo and Tetsuaki Takeda

ICONE18-29437 543

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

Simulation Platform

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

ICONE18-29447 551

Exponential Function Expansion Nodal Diffusion Method

Yunzhao Li, Hongchun Wu, Liangzhi Cao, and Qichang Chen

ICONE18-29463 557

CFD Analysis of PWR Core Top Region: Top Fuel Assembly and Top Nozzle RegionsChung-Yun Wu, Min-Tsung Kao, Ching-Chang Chieng, Yuan Kun, Yiban Xu,

Milorad B. Dzodzo, Michael E. Conner, Steven A. Beltz, and Sumit Ray

ICONE18-29517 565

Model Development of Turbulent Dispersion Force for Advanced Two-Fluid Model in

Consideration of Bubble-Liquid Phase Interactions

Hideaki Hosoi and Hiroyuki Yoshida

ICONE18-29545 573

Characteristics of Cavitation and Erosion Phenomena in Sodium Flow

Teddy Ardiansyah, Makoto Asaba, Kuniaki Miura, and Minoru Takahashi

ICONE18-29546 581Structural Design of S-Bend Box for ITER Feeder Based on OptimizationTechnique of ANSYS

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

1CONE18-29550 587Numerical Research on Oscillation of Two-Phase Flow Under Rolling Motion

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

xiii

ICONE18-29568 599

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

Supersonic Steam InjectorShunsuke Shibayama, Yutaka Abe, Akiko Kaneko, Akira Fukuichi, Chikako Iwaki,

Tadashi Narabayashi, Michitsugu Mori, and Shuichi Ohmori

ICONE18 29572 609

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

Nan Zhang and Zhongning Sun

ICONE18-29585 615

Preliminary Study of Influence of Severe Accident Mitigation Countermeasures to

In-Vessel Release of Fisson Products

Gaofeng Huang, Xuewu Cao, and Jingxi Li

ICONE18-29590 623

Solids Formation Behavior of Simulated High-Level Liquid Waste During

Long-Term StorageJin Chen, Xuegang Liu, Yanchao Zhang, Qian'ge He, and Jianchen Wang

ICOIME18-29612 629

Collapse Limit of Water Jetting With Surface Condensation in Steam InjectorRyuhei Ikuta, Yasuo Koizumi, and Hiroyuki Yoshida

ICONE18-29618 635

Experimental Study on Jet Breakup Behavior With Surface Solidification

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

ICONE18-29631 645

Image Analysis of Carry-Under by Falling Liquid Flow

Tomohiko Ohtsuka, Naoki Haraguchi, Hiroyasu Ohtake, and Yasuo Koizumi

ICONE18-29633 651

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, and Mashiro Furuya

ICONE18-29636 657

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

Vertical Mini PipeShunichi Watanabe, Yutaka Fukuhara, Tatsuya Hazuku, Tomoji Takamasa, and

Takashi Hibiki

ICONE18-29708 665

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, and Werner Maschek

xiv

ICONE18-29724 675

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

Jun Yao and Jinping Suo

ICONE18-29737 681

Large Eddy Simulations of Jet Flow Interaction Within Staggered Rod Bundles

Nathaniel Salpeter and Yassin Hassan

ICONE18-29748 693

Modeling the Spectral History in the Depletion of a PWR Core

/. Bilodid

ICONE18-29782 701

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

Yonghong Li, Chaohui He, and Chunmei Xia

IC0NE18-29790 705

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, and Igor Pioro

IC0NE18-29835 713

The Research on Scale of Cluster Fuel Assembly Spacer Grids

Jie Chen, Bingde Chen, and Hong Zhang

IC0NE18-29881 721

Advances in Inverse Transport Methods

Zeyun Wu and Marvin L. Adams

IC0NE18-29918 729

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

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

IC0NE18-29952 739

RBMK Fuel Rod Modelling and Investigation of Process During Operation CycleTadas Kaliatka, Ausra Marao, Renatas Karalevicius, and Eugenijus Uspuras

IC0NE18-29956 747

Design Concept and Heat Transfer Analysis for a Double Pipe Fuel Channel for

SCWR Type Reactors

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

IC0NE18-29972 755

Steam-Reheat Options for Pressure-Tube SCWRs

Eugene Saltanov, Wargha Peiman, Amjad Farah, Krysten King, Maria Naidin, and

Igor Pioro

ICONE18-29974 767

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, and Igor Pioro

xv

ICONE18-29975 - 775

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

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

Lisa Grande, and Igor Pioro

ICONE18-29990 783

Comparison of Selected Forced-Convection Supercritical-Water Heat-Transfer

Correlations for Vertical Bare Tubes

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

ICONE18-29991 793

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

Bare Vertical Tubes

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

ICONE18-29998 801

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, and

Igor Pioro

ICONE18-30024 809

Developing New Heat-Transfer Correlation for Supercritical-Water Flow in

Vertical Bare Tubes

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

ICONE18-30063 819

Design Study on Power Flattening to Sodium Cooled Large-Scale CANDLE Burning Reactor

With Using Thorium Fuel

Tsuyoshi Okawa, Sinsuke Nakayama, and Hiroshi Sekimoto

1CONE18-30069 825

Heat-Loss Calculations in a SCWR Fuel-Channel

Wargha Peiman, Eugene Saltanov, Kamiel Gabriel, and Igor Pioro

ICONE18-30073 835

Measurement of the Dynamical Mass Transfer of a Single C02 Bubble Using LIF/HPTS

Visualization and a Photoelectric Optical Fiber Probe

Kodai Hanyu and Takayuki Saito

ICOIME18-30104 845

Supercritical Water-Cooled Nuclear Reactor With Intermediate Heat ExchangersH. Thind, I. Pioro, and G. Harvel

ICONE18-30116 855

Towards Understanding Melt Eruption Phenomena During Molten Corium

Concrete Interactions

Kevin R. Robb and Michael L. Corradini

xvi

ICONE18-30119 865

Analysis of Operator Responses to Mitigate Temperature Rise in Electrical

Auxiliary BuildingM. James Hardy, Matthew F. King, and Ryan Bigelow

ICOIME18-30148 873

Clarification of Ejection and Sweep in Rectangular Channel Turbulent Flow

Muhammad Kunta Biddinika, Noriyuki Watanabe, Masanori Aritomi, and

Hiroshige Kikura

ICONE18-30153 879

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

Yunhuang Zhang and Jean C. Ragusa

ICONE18-30173 887

Isotope-Based Analysis of Nuclear Waste Repository Performance

Joosep Pata and Alan H. Tkaczyk

ICONE18-30177 895

Nuclear Analysis During Modification of NPP Core

Andrius Slavickas

ICONE18-30192 901

Analysis of Updated Supercritical Water Heat Transfer Correlation for Vertical Bare Tubes

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

ICONE18-30225 913

Experimental Turbulence Analysis of Fuel Bundle With Spacer Grids

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

ICON E18-30347 923

Particle Behaviors Under Acceleration Condition in Solid-Air Two Phase Flow

Tongr Zhao and Masahiro Takei

Author Index 929

xvii