CONFERENCE SESSIONS
Plenary Session
Grand Station Ballroom		 Monday / 08:30 - 12:00
1 The Nuclear Renaissance – Is it real? Dr. Aris Candris, President & CEO, Westinghouse (USA)
2 Future Advancements Needed in Reactor Technology Dan Pace, Senior Vice President, FENOC (USA)
3 Key Issues in the Future of Nuclear Power Bertrand Barre, Vice President Scientific Communications, AREVA (France)
4 Most Significant Historical Advances in Reactor Physics Since CP-1 Dr. Larry Foulke, Director of Nuclear Programs, University of Pittsburgh (USA)
Panel Global Education and Training Needs in Nuclear Engineering and Reactor Physics
Grand Station Ballroom 1		 Monday / 15:30 - 17:35
Panelists Region Covered
Carla Notari Argentina
Yung-An Chao China
Bertrand Barre France
Akio Yamamoto Japan
Nam-Zin Cho Republic of Korea
Joseph DeThomas Middle East
Oum Keltoum Bouhelal Morocco
Frederik Reitsma South Africa
Jack Brenizer  United States
Michael Robinson  (Moderator) United States
1A Nuclear Data Measurements and Evaluations Monday / 13:30 - 15:10
Chairs: Mike Zerkle (Bettis)
1 Sigma Web Interface For Reactor Data Applications Boris Pritychenko
2 235U(n,F) prompt fission neutron spectra Vladimir M Maslov
3 Commissioning of the n_TOF-Ph2 facility Eric Berthoumieux
4 Improvement Of The Resonance Cross Section Description using Transmission Experiments Nina Koyumdjieva

1B Nuclear Data Libraries Tuesday / 13:30 - 15:10
Chairs: Dimitri Rochman (NRG), Mike Zerkle (Bettis)
1 Tendl-2009: Comprehensive Nuclear Data Library With Covariances Dimitri Rochman
2 Paragon Library With 4.0Ev Upscattering Cut-Off Vefa N Kucukboyaci
3 ENDF/B-VII.0 Based Library for PARAGON Vefa N Kucukboyaci
4 Generation of 69 Group Cross Section Library Based on JEF Data for TRIGA Reactor Calculations and its Validation by analyzing the Benchmark Lattices of Thermal Reactors Md. Muslehuddin Sarker

1C Nuclear Data Testing and Validation I Wednesday / 10:20 - 12:00
Chairs: Jeremy Pencer (AECL), Mike Zerkle (Bettis)
1 ENDF/B-VII.0 versus ENDF/B-VI.8 in CANDU Calculations Dimitar V Altiparmakov
2 Impact Of Difference Of Neutron Cross Section Libraries To Isotopic Concentration Of Actinides Shogo Matsuoka
3 Thermal Spectrum Critical Experiments Using ENDF/B-VII.0, JEFF 3.1.1 And JENDL 3.3 Harish C Huria
4 Reactivity And Flux Calculations Using MCNP For Heavy-Water Experiments In The ZED-2 Critical Facility Using Low-Enriched Uranium Fuel Bundles Fook Choy Wong

1D Nuclear Data Testing and Validation II Thursday / 15:30 - 17:35
Chairs: Mike Zerkle (Bettis)
1 Measurements and Analysis of Reactivity Worth of Rare-Earth Elements at Kyoto University Critical Assembly Kosuke Shimozato
2 Validation Of The JEFF 3.1.1 Library For The Calculation Of The Physical Assays In The N4 Chooz-B1 PWR Using The Continuous Energy Monte Carlo Code TRIPOLI-4 Pierre Leconte

2A Numerical Methods for Deterministic and Stochastic Transport Monday / 13:30 - 15:10
Chairs: Igor Zmijarevic (CEA), Dmitriy Anistratov (NCSU)
1 Calculation of k-Eigenvalues and Multi-Group Eigenfunctions Using the Hybrid “Functional Monte Carlo” Method Jinan Yang
2 A Raviart-Thomas-Schneider Implementation of the Simplified Pn Method in 3-D Hexagonal Geometry Alain Hebert
3 A Low-order Quasidiffusion Discretization via Linear-Continuous Finite Elements on Unstructured Triangular Meshes William A Wieselquist
4 The Wavelet Function Expansion Method for Solving the Neutron Transport Equation Hongchun Wu

2B Acceleration Techniques for Deterministic Transport Methods Tuesday / 13:30 - 15:10
Chairs: Richard Sanchez (CEA), Bill Martin (Univ. Michigan)
1 Nonlinear Acceleration Methods for Even-Parity Neutron Transport William J Martin
2 Acceleration technique using Krylov subspace methods for 2D arbitrary geometry characteristics solver Hongbo Zhang
3 Generalized Coarse-Mesh Finite Difference Acceleration For The Method Of Characteristics XiaoMing Chai
4 3D Coarse Mesh NEM Embedded with 2D Fine Mesh NDOM for PWR Core Analysis Shengyi Si

2C Applications of Discontinuity Factors Tuesday / 10:20 - 12:00
Chairs: Akio Yamamoto (Nagoya Univ.), Kord Smith (Studsvik)
1 Pin Cell Discontinuity Factors in Transient 3-D Discrete Ordinates Code TORT-TD Armin Seubert
2 Linear Discontinuous (LD) Coefficients in the Slice Balance Approach (SBA) Mathematical Framework for the Discrete Ordinates Code Jaguar Ryanne A Kennedy
3 Utilization of Discontinuity Factor in Integro-differential Type of Boltzmann Transport Equation Akio YAMAMOTO
4 Angular Flux Discontinuity Factors For Reactor Core Transport Calculation Zhihong Liu

2D Validation of Computer Codes Thursday / 10:20 - 12:00
Chairs: Alain Hebert (Ecole Polytechnique), Masahiro Tatsumi (NFI)
1 Evolution of Computer Codes for CANDU Analysis Dimitar V Altiparmakov
2 Comparison of WIMS-AECL / DRAGON / RFSP and MCNP Results With ZED-2 Measurements For Control Device Worth and Reactor Kinetics Jeremy Pencer
3 Application of 3D Collision Probability Method to VHTR Spherical Geometries Marc-Andre Lajoie
4 COMET Calculations of a Postulated Stylized Small Region of a CANDU Core Dingkang Zhang

2E Kinetic Transport Methods and Sensitivity Analysis Applications Tuesday / 08:00 - 10:05
Chairs: Emiliano Masiello (CEA), Piero Ravetto (Politecnici Di Torino)
1 Deriving a Modified Asymptotic Telegrapher's Equation ($P_1$) Approximation Shay I Heizler
2 Spatial And Time-Dependent Reactor Kinetics Methodology Based On The Method Of Characteristics Xue Yang
3 A Hybrid Transport-Point Kinetic Method For The Analysis Of Source Transients In Subcritical Systems Paolo Picca
4 Application Of Artificial Neural Networks To Infer Subcriticality Level Through Kinetic Models Paolo Picca
5 Adjoint Based Error Measures For Functional Defect Correction In Deterministic Neutron Transport Applications Simon R Merton

2F Analytical Transport and Numerical Methods for The Diffusion Equation Monday / 15:30 - 17:35
Chairs: Farzad Rahnema (GATech), Ricardo Carvalho de Barros (Univ. Rio de Janeiro)
1 On The Order Of Spherical Harmonics Approximation For The Neutron Transport Equation Haileyesus Tsige-Tamitat
2 An Analytical Spatial Reconstruction Scheme For The Spectral Diamond – Spectral Green’S Function – Constant Nodal Method For One-Speed X,Y-Geometry Sn Eigenvalue Problems Ricardo C Barros
3 Analytic Basis Function Expansion Nodal Method For Neutron Diffusion Equations In Triangular Geometry Haoliang Lu
4 A 2D Triangular NODAL-SP3 Method for Solving Neutron Transport Equation Yunzhao Li
5 Analytic Basis Function Expansion Method for Neutron Diffusion Calculation in the Arbitrary Triangular Nodes WANG Kunpeng

2G Parallel Schemes and Applications Wednesday / 13:30 - 15:10
Chairs: Yousry Azmy (NCSU), Gianluca Longoni (Westinghouse)
1 A Parallel Algorithm for Solving the Multidimensional Within-Group Discrete Ordinates Equations with Spatial Domain Decomposition Robert J Zerr
2 FPGA Hardware Acceleration For High Performance Neutron Transport Computation Based On Agent Methodology Shanjie Xiao
3 Analysis of the Pool Critical Assembly Benchmark Using RAPTOR-M3G, a Parallel Deterministic Radiation Transport Code Greg A Fischer
4 Application Of Raptor-M3G To Reactor Dosimetry Problems On Massively Parallel Architectures Gianluca Longoni

2H Cross Section Collapsing & Cell/Assembly Calculations Thursday / 13:30 - 15:10
Chairs: Alireza Haghighat (Univ. Florida), Greg Fischer (Westinghouse)
1 Computationally Optimized Multi-group Cross Section Data Collapsing Using the YGROUP Code Ce Yi
2 Analysis of Cross-Section Condensation in PWR Simulations Steven J Douglass
3 Elements Of Validation Of The EDF R&D Sn And SPn Solvers Vs. MCNP Multigroup Assembly Calculations Tanguy Courau
4 Advanced Method Of Solution Of Neutron Transport Equation In Nuclear Reactor Cell Tamara S. Poveschenko

3A Monte Carlo Source Convergence Acceleration, Issues and Applications Tuesday / 08:00 - 10:05
Chairs: David Griesheimer (Bettis)
1 Investigation of CMFD Accelerated Monte Carlo Eigenvalue Calculation with Simplified Low Dimensional Multigroup Formulation Min-Jae Lee
2 Refinement Of Monte Carlo Anchoring Method Tested On Continuous-Energy Loosely-Coupled Fissile Problems Sunghwan Yun
3 Investigation of the Entropy-Based Convergence Dianostics in MCNP5 using the OECD/NEA Fuel Storage Pool Benchmark Problem Bo Shi
4 Analysis Of The Higher Mode Eigenfunction Calculation Using Modified Power Iteration Method Bo Shi
5 A Hybrid Source-Driven Method To Compute Fast Neutron Fluence In Reactor Pressure Vessel Ren-Tai Chiang

3B Monte Carlo Depletion and Propagation of Uncertainties Monday / 15:30 - 17:35
Chairs:
1 Statistical Implications in Monte Carlo Depletions Zhiwen Xu
2 Validating The Vesta Monte Carlo Depletion Interface Using Ariane Chemical Assay Data For Pressurized Water Reactor Applications L. Cousin
3 In-Line Xenon Convergence Algorithm for Monte Carlo Reactor Calculations David P Griesheimer
4 The Log Linear Rate Constant Power Depletion Method David C Carpenter
5 MC21 Monte Carlo Analysis Of The Hoogenboom-Martin Full-Core PWR Benchmark Problem Daniel J Kelly

3C Calculation of Kinetics Parameters in Monte Carlo Codes Tuesday / 10:20 - 12:00
Chairs:
1 Calculating Kinetics Parameters and Reactivity Changes with Continuous-Energy Monte Carlo Brian C. Kiedrowski
2 Calculating The Kinetic Parameters In The Continuous Energy Monte-Carlo Code Moret Alexis Jinaphanh
3 Estimation Of Adjoint-Weighted Kinectics Parameters In Monte Carlo Forward Calculations Hyung-Jin Shim
4 An Experience of Applying Iterated Fission Probability Method to Calculation of Effective Kinetics Parameters and
Keff Sensitivities with Monte Carlo		 Kirill Raskach

3D Monte Carlo Methods - General I Wednesday / 08:00 - 10:05
Chairs: Tom Sutton (KAPL)
1 An Investigation On The Use Of Probability Table Cross-Sections For Monte Carlo Lattice Calculations Nicolas Martin
2 Riding Bare-Back On Unstructured Meshes For 21st Century Criticality Calculations Karen Kelley
3 Moment-Conserving Histopolating B-Splines For Continuous Tally Estimation Justin M Pounders
4 A Monte Carlo Surface Source Method for Advanced Test Reactor Experiment Prototyping Paul Wilson
5 Estimation Of Coincidence And Correlation In Non-Analogous Monte Carlo Particle Transport Máté Szieberth

3E Monte Carlo Methods - General II Thursday / 08:00 - 10:05
Chairs: Tom Sutton (KAPL)
1 Verification Of Pwr In- And Ex- Vessel Neutron Fluence Calculations With Mcnpx, Based On The "H.B. Robinson-2" Dosimetry Benchmark Alexander Vasiliev
2 Monte Carlo Methods for Neutron Transport on Graphics Processing Units Using CUDA Adam G Nelson
3 PET Image Reconstruction With On-The-Fly Monte Carlo Using GPU David Legrady
4 TMCC: A Transient Three-Dimensional Neutron Transport Code by the Direct Simulation Method Huayun Shen
5 Monte Carlo Simulations and Experimental Validations of α Eigenvalues Zeguang LI

4A Sub-critical System & Reactor Dynamic - I Monday / 13:30 - 15:10
Chairs: Sandra Dulla (University of Torino), Imre Pázsit (Chalmers University of Technology)
1 Analysis of Photo-Neutron Physics During Moderator Event in a Deeply Sub-Critical CANDU Reactor Jim V. Donnelly
2 Correction Methods For Reactivity Monitoring Techniques In Pulsed Neutron Source (PNS) Measurements Vicente Bécares Palacios
3 Deterministic Calculation of the Effective Delayed Neutron Fraction without using the Adjoint Neutron Flux Alberto Talamo
4 Neutron Noise Calculations using the Analytical Nodal Method Viktor Larsson

4B Sub-critical System & Reactor Dynamic - II Monday / 15:30 - 17:35
Chairs: Sandra Dulla (University of Torino), Imre Pázsit (Chalmers University of Technology)
1 Numerical Solution Of Reactor Kinetics Equation With Krylov Subspace Method For Matrix Exponential Yuichiro Ban
2 Investigation of the Space-Dependent Noise Induced by Propagating Density Fluctuations Victor Dykin
3 Reactor Kinetics, Dynamic Response and Neutron Noise in Molten Salt Reactors Imre Pázsit
4 Fast Breeder Reactor Kinetics. A Direct Problem Evgeny F. Seleznev
5 Fast Breeder Reactor Kinetics. An Inverse Problem Evgeny F. Seleznev

4C Lattice Physics Calculations: in Memory of Rudi Stamm'ler - I Wednesday / 08:00 - 10:05
Chairs: Charles A. Wemple (Studsvik), Tomasz Kozlowski (Nuclear Power Safety - Sweden)
1 Dr. Rudolf J.J. Stamm’ler - In Memoriam Juan J. Casal
2 Rudi Stamm’ler Contributions And Dragon Robert Roy
3 Assembly Depletion with Critical Spectrum in McCARD Monte Carlo Calculations and Comparison with HELIOS Ho Jin Park
4 A Resonance Calculation Method based on the Multi-Terms Rational Approximation for General Geometry with Gray Resonance Absorbers Hiroki Koike
5 Neutronic Calculations for Steel-Reflected Fast Critical Systems with the Sub-Group Sn Method Go Chiba

4D Lattice Physics Calculations: in Memory of Rudi Stamm'ler - II Wednesday / 10:20 - 12:00
Chairs: Tomasz Kozlowski (Nuclear Power Safety - Sweden) , Taek K. Kim (ANL)
1 APOLLO2-A – AREVA's New Generation Lattice Physics Code: Methodology And Validation Emanuele Martinolli
2 Qualification of APOLLO2.8/JEFF-3.1.1 Code Package for the Calculations of PWR Plutonium Recycling Using the EPICURE Experiments Jean-François Vidal
3 Analsyis of the Spatial Isotopic Distributions during the Burnup of UMOX- and ThMOX-Fuels on Unit Cell Basis Bruno Merk
4 Analysis of the MISTRAL Experiment on the RTC for UOX and MOX Lattices using JEFF3.1.1 Alain Santamarina

4E Lattice Physics Calculations: in Memory of Rudi Stamm'ler - III Wednesday / 13:30 - 15:10
Chairs: Taek K. Kim (ANL) , Charles A. Wemple (Studsvik)
1 Validation of the Lattice Physics Code LANCER02 with ENDF/B-VII Library Uğur Mertyürek
2 Nodal Expansion Method with Axially Varying Cross-sections Benjamin Collins
3 Development Of The HELIOS/CAPP Code System for the Analysis of Pebble Type VHTR Cores Hyun Chul Lee
4 A Macro Reactivity-Equivalent Physical Transformation Method for Prismatic Gas-Cooled Reactors Utilizing Uranium Oxycarbide Fuel Brian J. Ade

4F Computainal Challanges of HTGRs Wednesday / 15:30 - 17:35
Chairs: Germina Ilas (ORNL), Eugene Shwageraus (MIT)
1 HTGR Fuel Element Depletion Benchmark: Stage Three Results Emil Fridman
2 HTTR Fuel Block Simulations With SCALE Dan Ilas
3 On SCALE Validation for PBR Analysis Germina Ilas
4 PEBBLES Mechanics Simulation Speedup Joshua J. Cogliati
5 PEBBLES Simulation of Static Friction and New Static Friction Benchmark Joshua J. Cogliati

4G Core Physics Methods - I Tuesday / 08:00 - 10:05
Chairs: Yung-An Chao (Westinghouse), Akio Yamamoto (Nagoya University)
1 Improved Reflector Modeling for LWR Analysis David Colameco
2 Analysis of Cold Critical Experiments by a Pin-by-Pin Core Analysis Method Using a Three-Dimensional Direct Response Matrix Takeshi Mitsuyasu
3 Group Decoupled Multi-Group Pin Power Reconstruction Utilizing Nodal Solution 1D Flux Profiles Shaohong Zhang
4 Accuracy Enhancements of the Coarse-Mesh Diffusion Core Model QUABBOX/CUBBOX for Highly Heterogeneous Core Configurations Markus Klein
5 An Alternative Solver for the Nodal Expansion Method Equations Antonio C.M. Alvim

4H Core Physics Methods - II Tuesday / 10:20 - 12:00
Chairs: Akio Yamamoto (Nagoya University), Rakesh Chawla (Swiss Federal Institute of Technology, Lausanne - EPFL)
1 A New Robust Cross Section Representation Methodology for PWR Core Simulator Daisuke Sato
2 Improving Cross Sections Via Spectral Rehomogenization Aldo Dall'Osso
3 Investigation on Macroscopic Cross Section Model for BWR Pin-By-Pin Core Analysis Tatsuya Fujita
4 Homogenization of Cross Sections and Related Performance Improvements in PWR Burnup using the PENBURN/PENTRAN Burnup Sequence Kevin Manalo

4J Core Physics Methods - III Tuesday / 13:30 - 15:10
Chairs: Bojan Petrovic (Georgia Technology University), Yung-An Chao (Westinghouse)
1 Development of Iterative Transport - Diffusion Methodology for LWR Analysis Kostadin N. Ivanov
2 A Comparison between Nodal Expansion Method and Nodal Green's Function Method Deng-ying Wang
3 Mixed Energy Reactor Simulations using the Discrete Generalized Multigroup Method Benoit Forget
4 Development of the Triangular Nodal Method TRIPEN for Prismatic HTR Analysis Brendan Kochunas

4K Core Physics Methods - IV Tuesday / 15:30 - 17:35
Chairs: Rakesh Chawla (Swiss Federal Institute of Technology, Lausanne - EPFL), Bojan Petrovic (Georgia Technology University)
1 3D Finite Element Method for the Lambda Modes Problem In Hexagonal-Z Geometry Sebastian Gonzalez-Pintor
2 Effect of Void Dependent Reactivity Modeling Bias on BWR Axial Power Tilt Shaohong Zhang
3 Generalized Equivalence Theory for Checkerboard Configurations in Natural-Uranium CANDU Lattices Eleodor M. Nichita
4 A Response Matrix Method for Improved Modeling of Neutron Streaming in Large Control Rod Channels of VHTR Cores Changho Lee
5 The Possibility to Online Reconstruct the HTR In-Core Power Distribution Fu Li

4L Advances and Validation of Reactor Physics Tools - I Thursday / 08:00 - 10:05
Chairs: Blair Bromley (AECL), Tamer Bahadir (Studsvik)
1 Multilevel Criticality Computations in AREVA NP's Core Simulation Code ARTEMIS Rene van Geemert
2 Evaluation of Gamma Scanning in Oskarshamn2 with SIMULATE-5 Tamer Bahadir
3 Bundle and Pin-By-Pin Power Gamma Scan Results for Modern BWR Fuel Brian R. Moore
4 Parallel Computing in Scale Mark D. DeHart
5 BWR Modeling Capability and SCALE/TRITON Lattice-to-Core Integration of the NESTLE Nodal Simulator Ivan Maldonado

4M Advances and Validation of Reactor Physics Tools - II Thursday / 10:20 - 12:00
Chairs: Blair Bromley (AECL), Tamer Bahadir (Studsvik)
1 Status of Updating the Cross Section Library of the Juelich Reactor Dynamic Codes TINTE/MGT to ENDF-B-VII Kay Nuenighoff
2 X2: a Coupled Neutronic - Thermal-Hydraulic Code System for Compact Research Reactor Cores Harald Breitkreutz
3 Development and Verification of Quick and Precise Core Physics Analysis Code Zhihong Liu
4 A Fast and Flexible Reactor Physics Model for Simulating Neutron Spectra and Depletion in Fast Reactors Mark R. Deinert

4N Reactor Operation & Design Tuesday / 08:00 - 10:05
Chairs: Dan Ilas (ORNL), Cenk Güler (Westinghouse)
1 Shielding Fuel Assemblies Used to Protect the Beltline Weld of the Reactor Pressure Vessel from Fast Neutron Radiation in Ringhals Unit 3 And 4 Henrik Nylen
2 A Method for Channel-Bow Indication by Neutron Flux Measurements John Loberg
3 Development of an Efficient Pentran Model for Neutron Flux Simulation of the UFTR Shield Tank Alireza Haghighat
4 Preliminary Feasibility Study of a Water Space Reactor with an Innovative Reactivity Control System Vito Memoli
5 Analysis of Accuracy of Reactivity Balance Components in BN-600 Power Fast Reactor Andrey V. Moiseev

4P In-Core Fuel Management and Optimization - I Thursday / 13:30 - 15:10
Chairs: Juan Luis Francois Lacouture (Universidad Nacional Autónoma de México-UNAM), Serkan Yilmaz (GE)
1 Loading Pattern Optimization Cooperatively Using Two New Algorithms Zhaohu Gong
2 Study on the Mechanism and Efficiency of Simulated Annealing Using an LP Optimization Benchmark Problem Xiaofeng Jiang
3 Direct Optimization of Loading Pattern Search Using the HHLP Theory and the MILP Method Xiaofeng Jiang
4 Development of an Automatic Tool for BWR Loading Pattern Optimization by Utilizing Genetic Algorithm Chien-Hsiang Chen

4Q In-Core Fuel Management and Optimization - II Thursday / 15:30 - 17:35
Chairs: Juan Luis Francois Lacouture (Universidad Nacional Autónoma de México-UNAM), Serkan Yilmaz (GE)
1 BWR Bundle Optimization by Linear Perturbation and MILP Tao Wang
2 Core Analysis, Design and Optimization of a Deep-Burn Pebble Bed Reactor Brian Boer
3 Breed-and-Burn Depleted Uranium in Fast Reactors without Actinide Separation Florent Heidet
4 Neutronic Evaluation of Breed-and-Burn Reactor Fuel Types Using an Infinite-Medium Depletion Approximation Robert C. Petroski
5 Single-cycle and Equilibrium-cycle Reloading Optimization on Real Nuclear Power Plant Zhihong Liu

5A Plant Improvements Thursday / 08:00 - 10:05
Chairs: C. Garzenne (EDF), Tanguy Courau (AREVA)
1 VVER-440 Control Rod Follower Induced Local Power Peaking Computational Benchmark: MCNP and KARATE Solutions Emese Temesvári
2 Improvement Of The Conversion Ratio In PWR Damian Frederic
3 Investigation Of RCCA Absorber Depletion In Normal Plant Operation. Application To The Shutdown Margin Analysis Marcel Bouffier
4 SCWR Assembly Designs with Peripheral Moderator Channels Peng Zhang
5 Review of Worldwide Reactor-Physics Codes and Their Applicability to the Current and Next-Generation CANDU Reactors Wei Shen

5B Liquid Metal Fast Reactor Design & Analysis Wednesday / 08:00 - 10:05
Chairs: Denis Verrier (AREVA), Joe Miller (EDA, Inc)
1 Feasibility Study Of Ultra-Long Life Fast Reactor Core Concept Taek K Kim
2 Studies Of Metal (U-Pu-Zr) fuel in BOR-60 Reactor With Focus On Its Use In High-Power Sodium Fast Reactors Mitenkova F Elena
3 Void Reactivity Decomposition For The Sodium-Cooled Fast Reactor In Equilibrium Closed Fuel Cycle Kaichao Sun
4 Conceptual Core Design Of A Generation IV LFR Demonstration Plant Sara Bortot
5 Application Of Method Of Characteristics To Fast Reactor Core Analysis Toshikazu Takeda

5C Advanced Reactors Desgins Tuesday / 08:00 - 10:05
Chairs: F. Damian (CEA), Guy Marleau (EPM)
1 Core Design Optimisation In Advanced Heavy Water Reactor For Achieving Self-Sustenance In 233U Neelima Prasad
2 Macroscopic Cross-Sections Of Neutron Radiation Capture By Pb-208, U-238 And Tc-99 Nuclides In The Accelerator Driven Subcritical Core Cooled With Molten Pb-208 Georgy L Khosasanov
3 The Research of Pb208 Coolant in Thorium-based Long Life Reactor Ganglin Yu
4 High Performance Fast Reactor Cores Employing Deuteride Moderators Tsugio Yokoyama
5 Neutronic Analysis Of Water-Steam Injection Accidents For Generation IV Gas-Cooled Fast Reactors Gaetan Girardin et al

5D Core Monitoring Thursday / 10:20 - 12:00
Chairs: Charls Rombough (CTR Technical Servies), Walid Metwally (GNF)
1 Assessment Of Fission Gas Vented Fuel Impact With Advanced Burner Reactor Taek K Kim
2 A Standard for the Determination of Thermal Energy Deposition Rates in Nuclear Reactors Dimitrios Cokinos
3 Incore Instrument Subcritical Verification (INCISV) – Core Design Verification Method Michael C Prible
4 Comparison of Experiments and Calculations of Void Fraction Distributions in Randomly Stacked Pebble Beds Ir. Gert Jan Auwerda

6A Thorium Fuel Cycle Tuesday / 15:30 - 17:35
Chairs: Moussa Mahgerefteh (Exelon Nuclear), Kevin Hesketh (UK National Laboratory)
1 Implementation Strategy Of Thorium Fuel Cycle Takashi Kamei
2 Roadmap Design For Thorium-Uranium Breeding Recycle In PWR Shengyi Si
3 Thorium Fuel Utilization In The BWR: Lattice Physics Analysis Of Reactivity Coefficients Andrew M Ward
4 Feasibility And Desirability Of Employing The Thorium Fuel Cycle For Power Generation Bal Raj Sehgal
5 Power Flattening For Sodium Cooled Metallic Fuel CANDLE Reactor By Adding Thorium In Inner Core Hiroshi Sekimoto

6B Minor Actinide Management Monday / 13:30 - 15:10
Chairs: Pavel V. Tsvetkov (Texas A&M), Bojan Petrovic (Georgia Tech)
1 Enhancing Advanced Candu Proliferation Resistance Fuel With Minor Actinides Gray S Chang
2 The Potential Of Pressurized Water Reactors For Recycle Of Americium-Curium Kevin W Hesketh
3 Recycling of VVER Minor Actinides in a Gas-Cooled Fast Reactor Zoltan Perko
4 Investigation Of Direct Transmutation Of Actinides By Spallation Neutrons István Rovni

6C Advanced Reactor Designs Wednesday / 10:20 - 12:00
Chairs: Kevan Weaver (TerraPower), Robb Borland (First Energy)
1 Preliminary Assessment of a Fusion-Fission Hybrid Reactor Terry Kammash
2 Definition Of Breeding Gain For Molten Salt Reactors Karoly Nagy
3 Fast Reactor Transmutation Performance And Conversion Ratio Effects Edward A Hoffman
4 Travelling wave reactor: velocity formation mechanisms Volodymyr M. Khotyayintsev

6D Alternative Fuel Cycles Wednesday / 15:30 - 17:35
Chairs: Pavel Tsvetkov (Texas A&M), Porsch Dieter (AREVA NP GmbH)
1 Closing the Nuclear Fuel Cycle in the 21st Century while Minimizing Proliferation Risk Chris Phillips
2 Introduction of MOTTO Cycle to CANDLE Fast Reactor Hiroshi Sekimoto
3 Solution Of The Equilibrium Fuel Vector In Closed Fuel Cycles And Application To A Lead Fast Reactor Carlo Petrovich
4 Nuclear Fuel Cycle Sensitivity To The Variation Of Physical Parameters Anthony M Scopatz
5 Consideration Of Reactor Systems For Uranium Resource Extension And Waste Minimization Temitope A Taiwo

6E Transuranic Applications Wednesday / 13:30 - 15:10
Chairs: Robert St.Clair (Duke Power), Moussa Mahgerefteh (Exelon Nuclear)
1 Design Studies for Full-MOX BWR Cores Wolf U Timm
2 Temperature Reactivity Coefficient For Plutonium Fuel In A High Temperature Reactor Christoph Pohl
3 The Behaviour Of A Preliminary Transuranic Mixed Oxide Fuel Design In A Candu 6 Reactor Andrew C Morreale
4 Attainable Burnup In A Life Engine Loaded With Depleted Uranium Massimiliano Fratoni

7A Nuclear Criticality Safety - I Wednesday / 08:00 - 10:05
Chairs: Dennis Mennerdahl (E Mennerdahl Systems), Tatiana Ivanova (IRSN)
1 FCC-NG: The Areva Safe Fresh Fuel Shipping Cask To Deliver The Future EPR™ Reactors Michel E Doucet
2 On the Criticality Safety of Transuranic Sodium Fast Reactor Fuel Transport Casks Samuel E. Bays
3 Isocrit: A Burnup Credit Tool For Spent Fuel Pool Storage Calculations Vefa N. Kucukboyaci
4 TGBLA Spent Fuel Isotopic Predictions And Their Effect On Criticality Calculations Walid A. Metwally
5 MCNP5 Criticality Experiment Benchmark For The Dry Storage System Of Chinshan Nuclear Power Plant Yung-Hung Teng

7B Nuclear Criticality Safety - II Thursday / 08:00 - 10:05
Chairs: Sedat Goluoglu (ORNL), Charles T. Rombough (CTR Technical Services)
1 OECD/NEA Expert Group On Uncertainty Analysis For Criticality Safety Assessment: Current Activities Tatiana Ivanova
2 Keff Sensitivity/Uncertainty Analysis of the Phase VII Burnup Credit Benchmark Oscar Cabellos
3 Determination Of A Depletion Uncertainty From Fuel Management Experience Dale B. Lancaster
4 Third Order Time Correlation Method Applied To SILENE Absolute Criticality Measurements Philippe P. Humbert
5 Hierarchical Monte-Carlo Approach To Bias Estimation For Criticality Safety Calculations Oliver Buss

8A Three-dimensional Transient Analysis Methods - I Monday / 15:30 - 17:35
Chairs: Gerardo M Grandi and Martin Zimmermann
1 ABWR Start-Up Test Analysis With Transient Code POLCA-T Kazuki Yano
2 Peach Bottom 2 Turbine Test 2 Simulation By TRACE-S3K Coupled Code Konstantin Nikitin
3 Modeling of VVER-1000 Partial Trip with Kinetic Codes Aleksandr I Zhukov
4 Benchmarking of Transient Codes against Cycle 19 Stability Measurements at Leibstadt Nuclear Power Plant (KKL) Carlos R Aguirre
5 Experimental Orthogonal Functions For The Qualification Of BWR Stability Events. Teresa Barrachina

8B Three-dimensional Transient Analysis Methods - II Tuesday / 15:30 - 17:35
Chairs: Serhat Lider (Westinghouse), Soeren Kliem (Forschungszentrum Dresden-Rossendorf)
1 BWR-Stability: Analysis of Cladding Temperature for High Amplitude Oscillations Peter Pohl
2 Validation Of ARCADIA® Transient Model With Rod Drop Test Benchmarking Songhui Zheng
3 Sensitivity Studies For The Main Steam Line Break In The Loviisa NPP With The HEXTRAN-SMABRE Elina Syrjälahti
4 Rod Ejection Accident 3D-Dynamic Analysis In Trillo NPP With RELAP5/PARCS V2.7 Teresa Barrachina
5 Fast Transient Evaluation Of Rod Ejection In VVER-1000 Core S. Mahmood Aletaha

8C Three-dimensional Transient Analysis Methods - III Wednesday / 10:20 - 12:00
Chairs: Bedirhan Akdeniz (Westinghouse), Gumersindo Verdu (Univ. Politecnica Valencia)
1 An Approach Of SFR Safety Study Through The Most Penalizing Sodium Void Reactivity Evgeny A Ivanov
2 Analysis Of Sodium Void Coefficient For 500 MWe Metal Reactor Prabhakara Chappidi Reddy
3 Coupled 3-D Neutronics/Thermal-Hydraulic Core Analysis Hakim Ferroukhi
4 Validation Of Atucha-2 PHWR Helios And Relap5-3D Model By Montecarlo Cell And Core Calculations Carlo Parisi

8D Multi-Physics Reactor Simulations - I Tuesday / 10:20 - 12:00
Chairs: Tom Downar (univ. Michigan), Carlo Parisi (Univ. Pisa)
1 HEMERA: A 3D Computational Tool For Analysis Of Accidental Transients Antonio Sargeni
2 Effect of CASMO-5 Cross-section Data and Doppler Temperature Definitions on LWR Reactivity Initiated Accidents Gerardo M Grandi
3 Stress Analysis Of Coated Particle Fuel In The Deep-Burn Pebble Bed Reactor Design Brian Boer
4 Consistent Comparison of Full Core PWR CEA with the Method Of Characteristic Code DeCART and the Coarse Mesh Nodal Code PARCS Mathieu Hursin

8E Multi-Physics Reactor Simulations - II Tuesday / 13:30 - 15:10
Chairs: Maria Avramova (PSU), Yann Perin (GRS)
1 Prototype Coupling Of The CFD Software ANSYS CFX With The 3D Neutron Kinetic Core Model DYN3D Soeren Kliem
2 New Developments Of The MCNP/CTF/NEM/NJOY Code System – Monte Carlo Based Coupled Code For High Accuracy Modeling Federico Puente-Espel
3 Implicit Time-Integration Method For Simultaneous Solution Of A Coupled Non-Linear System Justin Watson
4 Bond Graph Based Coupled Reactor Simulations Eugeny Sosnovsky

8F Multi-Physics Reactor Simulations - III Wednesday / 08:00 - 10:05
Chairs: Brian Boer and Antonio Sargeni
1 COBRA-TF / QUABOX-CUBBOX: Code System For Coupled Core And Subchannel Analysis Yann Périn
2 Improvements To The NEM/THERMIX Coupled Code Analysis Of High Temperature Reactors Kostadin Ivanov
3 Development And Optimization Of Coupling Interfaces Between Reactor Core Neutronics And Thermal-Hydraulic Codes Maria Avramova
4 On Delayed Neutron Effects At The Starting Of Accelerator Driven Systems To The Nominal Power Rubens Souza Santos
5 Coupled TORT-TD/CTF Capability For High-Fidelity LWR Core Calculations Maria Avramova

8G Developments in Probabilistic Risk Assessments Thursday / 08:00 - 10:05
Chairs: Cesare Frepoli (Westinghouse), Hongwu Cheng (Vattenfall)
1 Evaluation Of Aleatory And Epistemic Uncertainties In Level 2 Probabilistic Safety Analysis By Means Of Bayesian Monte Carlo Methods Axel Hoefer
2 Fast Sensitivity Ranking And Reliability Analysis Of Passive Thermal Hydraulic Safety System By Automatic Differentiation John A Arul
3 Application Of The PRA Methodology For Optimization Of NPPs Safety Management Bronislav Vinnikov
4 Functional Reliability Analysis Of Safety Grade Decay Heat Removal System Of PFBR By Augmentation Of Approximate Linear Response Surfaces Sajith T Mathews
5 Application Of SMAP Methodology To A 10% Power Up-Rate For Zion NPP SBO Transient Fabrice Fouet

8H Safety Analysis and Thermal-Hydraulics Thursday / 13:30 - 15:10
Chairs: Kurshad Muftuoglu (GE), Axel Hoefer (AREVA)
1 Analysis Of Steam Generator Tube Rupture Event In HTR-MODUL ReactorOR Alex Matev
2 Pressure Vessel SBLOCA simulation with TRACE5. Application to LSTF (ROSA V) Sergio Gallardo
3 Simulation of a Cold Leg SBLOCA with TRACE5. Application to LSTF (ROSA V) Sergio Gallardo
4 Application And Licensing Of Westinghouse Realistic Large Break Loca Evaluation Model (ASTRUM) For Maanshan Units 1 And 2 Nuclear Power Plant Cesare Frepoli
5 OECD/NRC Benchmark Based On NUPEC PWR Subchannel And Bundle Tests (PSBT) Maria Avramova

9A Research Reactor Facilities and Benchmarking Wednesday / 13:30 - 15:10
Chairs: Frederik Reitsma (PBMR), John Bess (INL)
1 Research Activities in the ZED-2 Critical Facility Alex M. Rauket
2 Large-Scale Irradiated Fuel Experiments At PROTEUS Research Program Gregory Perret
3 Benchmark Evaluation Of The Start-Up Core Reactor Physics Measurements Of The High Temperature Engineering Test Reactor John D. Bess
4 Calculation Of The Core Parameters Measured During The Commissioning Of The OPAL Reactor Eduardo A. Villarino

9B Special Session on The Test, Research and Training Reactor (TRTR) 2009 meeting Tuesday / 15:30 - 18:00
Chairs: David Nigg (INL), Frederik Reitsma (PBMR)
1 Selected Studies Of Past Operations At The ORNL High Flux Isotope Reactor Trent Primm
2 Washington State University Reactor HEU to LEU Conversion: A Comparison of HEU vs. LEU Fuel Behavior Don E. Wall
3 LEU Conversion Of The Nist Research Reactor: Maintaining Core Geometry To Avoid A Startup Core Robert E. Williams
4 Improved Computational Characterization Of The Thermal Neutron Source For Neutron Capture Therapy Research At The University Of Missouri David W. Nigg
5 Control Rod Malfunction At The NRAD Reactor Thomas L. Maddock
6 The AFRRI Triga Reactor: A Summary Of Applications In Mouse Studies G. David Ledney

9C Operational Support Analyses Wednesday / 15:30 - 17:35
Chairs: Jim Kuijper (NRG), Alireza Haghighat (UFL)
1 Startup Reactivity Accountability Attributed To Isotopic Transmutations In Irradiated Beryllium Reflector Of The High Flux Istotope Reactor Ivan Maldonado
2 Refined Control Rod Worth Estimation By Kinetics Equations With Included Photoneutrons Silva Kalcheva
3 Dose Rate Assessment For The HFR Repair Steven C. van der Marck
4 Study Of RHF Conversion In LEU Fuel Neutronic Calculations With MCNPX And VESTA Yoann Calzavara
5 Studies On The Transition To The Equilibrium Core Of The Jules Horowitz Reactor Corinne D'aletto

9D Accelerator and Spallation Physics Thursday / 15:30 - 17:35
Chairs: Pierre D'hondt (SCKCEN), Frederik Reitsma (PBMR)
1 Preliminary Analyses For Accelerator-Driven System With High-Energy Protons In Kyoto University Critical Assembly Jae-Yong Lim
2 Reactivity Determination Techniques in ADS Systems for the Incineration of Radioactive Wastes Manuel Fernández-Ordóñez
3 Set-Up Of A Deterministic Model For The Analysis Of The Guinevere Experience Giancarlo Bianchini

9E Physics Tests, Measurements and Evaluation Thursday / 10:20 - 12:00
Chairs: Hans Gougar (INL), Jim Kuijper (NRG)
1 KAMINI Fast Neutron Beam Attenuation Measurements in Boron Carbide Shield and their Prediction by Monte Carlo Modelling Prabhakara Chappidi Reddy
2 Delayed Neutron Measurements of Induced Fission Rates in Burnt LWR Fuel Samples at the PROTEUS Zero-Power Reactor Facility Kelly A. Jordan
3 Fission Rate Measurements in Spent Fuel via Gamma-Ray Spectrometry of Short-Lived Fission Products Induced in a Zero Power Reactor Hanna Kröhnert
4 Evaluation of Gold Activation Detectors on the Epithermal Neutron Beam at the LVR–15 Reactor Zdena Lahodová

10A Integral Experiments and Facilities for Safety Research - I Monday / 13:30 - 15:10
Chairs: Pierre D'hondt (SCKCEN), Frederik Reitsma (PBMR)
1 Benchmark Evaluation of the Initial Isothermal Physics Measurements at the Fast Flux Test Facility John Bess
2 Analysis of Core Physics Experiment on BWR 10x10 MOX Fuel Assemblies Toru Yamamoto
3 Experimental Validation of Reaction Rate Distributions in an SCWR-Like Fuel Lattice at PROTEUS Dominik Rätz
4 Triga Reaction Rate Benchmark Luka Snoj

10B Integral Experiments and Facilities for Safety Research - II Tuesday / 10:20 - 12:00
Chairs:
1 An Improved Benchmark Model for the BIG TEN Critical Assembly Russell D Mosteller
2 A Solution for the Telegrapher’s Equation with External Source: Application to YALINA - SC3A and SC3B Bruno Merk
3 Subcriticality Measurement by the Imaginary Source Multiplication Method with Multi-Detectors Shinichi Kawaguchi
4 Benchmark-Experiments with HEU and Tungsten at FKBN-2 Facility performed in RFNC-VNIITF Andrey V. Serikov

10C Integral Experiments and Facilities for Safety Research - III Tuesday / 13:30 - 15:10
Chairs: David Nigg (INL), Jim Kuijper (NRG)
1 Spectral Indices of the IPEN/MB-01 Reactor: A Nuclear Data Validation Adimir dos Santos
2 Power Distribution Gradients in WWER-440 Standard and Low Leakage Type Cores with Possible Influence on Fuel Failure Ján Martin Mikuš
3 Status of ERANOS-2 Code System Validation for Sodium Fast Reactor Applications Jean Tommasi
4 Sodium Void Validation with ERANOS on Zero Power Facility Experiments Jean Tommasi

11A Verification and Validation - I Wednesday / 10:20 - 12:00
Chairs: Blair Bromley (AECL), Takanori Kitada (Osaka Univ.)
1 Benchmarking TransLAT for Fission Product Generation David J Sweeney
2 Development Of A “Best Representativity” Method For Measurement Data Analysis – Application To Critical Experiment Simulating PWR At The Toshiba Nca Facilitiy Takuya Umano
3 SCALE 6 Analysis of HTR-10 Pebble-Bed Reactor For Initial Critical Configuration Eva E Sunny
4 Qualification Of The French APOLLO2.8/CEA2005V4 Code Package On Absorber Clusters In 17X17 PWR Type Lattices Through The Cameleon Program Patrick D Blaise

11B Verification and Validation - II Wednesday / 13:30 - 15:10
Chairs: Serkan Yilmaz (GE), Patrick Blaise (CEA)
1 MCNPX Burnup Simulation Of The Isotope Correlation Experiment Yan Cao
2 Confirmation Of The Similarity Between Critical Experiments And Real Cores By Using Representativity Factor In LWR Cell Takanori Kitada
3 Karma 1.1 Benchmark Calculations For The Numerical Benchmark Problems And The Critical Experiments Kyung-Hoon Lee
4 Coupling Of WIMS-AECL And ORIGEN-S For Depletion Calculations Geoffrey WR Edwards

11C Standards and Benchmarks Wednesday / 15:30 - 17:35
Chairs: Hans Gougar (INL), Bismark Tyobeka (IAEA)
1 High Order Finite Difference Approximations To The One-Group Neutron Diffusion Equation In 1D Heterogeneous Media Part I: Theory In Plane Media Barry D Ganapol
2 High Order Finite Difference Approximations To The One-Group Neutron Diffusion Equation In 1D Heterogeneous Media Part II: Implementation And Application Barry D Ganapol
3 The OECD/NEA/NSC PBMR 400 MW Coupled Neutronics Thermal Hydraulics Transient Benchmark: Transient Results Frederik Reitsma
4 Results of the IAEA CRP5 - Benchmark analysis related to the PBMR-400, PBMM, GT-MHR, HTR-10 and the ASTRA Critical Facility Frederik Reitsma
5 Current Status And Results Of The Pbmr "Pebble Box" Benchmark Within The Framework Of The IAEA CRP5 Frederik Reitsma

11D Uncertainty Analysis in Modeling - I Thursday / 10:20 - 12:00
Chairs: Pino Palmiotti (INL), Ivan Kodeli (Jožef Stefan Institute)
1 Sensitivity and Uncertainty of the Neutronic Parameters of BWR Ringhals-1 TRACE/PARCS Stability Prediction Ivan A Gajev
2 Uncertainty Associated With The In-Core Kinf Criterion Methodology For Fuel Storage Criticality Safety Analyses John C Hannah
3 Sensitivity Analyses For Small Fast Reactor Nuclear Characteristics With A Discrete Ordinate Transport Calculation Method Masatoshi Kawashima
4 Sensitivity and Uncertainty Analysis with New Covariance Data of Minor Actinides for AFC Developments Do Heon KIM

11E Uncertainty Analysis in Modeling - II Thursday / 13:30 - 15:10
Chairs: Maria Avramova (PSU), Carlo Parisi (Univ. Pisa)
1 Evaluation And Uncertainty Analysis Of The KRITZ-2 Critical Benchmark Experiments Ivan A. Kodeli
2 Application Of Global Sensitivity Analysis Approach To Exercise I-2 Of The OECD LWR UAM Benchmark Federico Puente Espel
3 Cross-Section Covariance Propagation For LWR Fuel Cells In One And Two Dimensions Carlo Parisi
4 Comparison Of Uncertainties Quantification Methods For Fast Reactor Neutronics Cristian Rabiti

12A Radiation Applications and Nuclear Safeguards - I Wednesday / 15:30 - 17:35
Chairs: Staffan Svärd (Uppsala Univ.), Rob Flammang (Westinghouse)
1 A Methodology For Determination Of Detector Response For Inspection Of A Spent Fuel Pool William J. Walters
2 Modeling Of The Cherenkov Light Emission From Nuclear Fuel Assemblies With Partial Defects Staffan J. Svärd
3 MANCINTAP: A Numerical Tool For The Analysis Of Neutron Induced Activations And Their Radiological Effects In Complex 3D Geometries Michele Frignani
4 Krško Neutron Streaming Analysis And Measurement For Concrete Missile Shield Removal Jianwei Chen

12B Radiation Applications and Nuclear Safeguards - II Thursday / 15:30 - 17:35
Chairs: Staffan Svärd (Uppsala Univ.), Rob Flammang (Westinghouse)
1 Verification of a Hybrid Adjoint Methodology in TITAN for Single Photon Emission Computed Tomography Katherine K. Royston
2 Early Detection of Primary System Pipe Leaks Petros Hovhannisyan
3 A Time-Dependent Calculational Model For Evaluation Of Plutonium Proliferation Protection Evgeny Kulikov
4 Recent Progress In The Practical Calculation Maintenance Of Commercial Production Of Cobalt-60 At Leningrad NPP Alexander Elshin

13A Nuclear Power and Sustainable Development Tuesday / 15:30 - 17:35
Chairs: Kevin W. Hesketh (UK National Nuclear Lab), Sudhinder THAKUR (Nuclear Power Corporation of India (NPC)
1 United Kingdom Nuclear Fuel Cycle Scenario Assessment Mr Robert W. Gregg
2 Multi Criteria Analysis For The Long Term Planning Of The Mexican Electrical System Expansion Cecilia Martin-del-Campo
3 Brazilian Nuclear Renaissance In A Sustainable Development Scenario Marcio Dias
4 Sustainable Development in India- A case for Nuclear Power Sudhinder Thakur
5 The Status and Prospect of Nuclear Power Development in China Mr. Tianmin Xin