1. No category

MONDAY, MAY 4
TECHNICAL SESSIONS
TRACK 1.
Water-Cooled Reactor
Programs and Issues
3:50pm
4:10pm
4:30pm
4:50pm
5:10pm
3:30pm >> 5:10pm
TRACK 2.
High Temperature Reactors
TRACK 3.
TRACK 4.
Fast Neutron and Other
Innovative Reactors
Operation, Performance and
Reliability Management
TRACK 5.
Plant Safety Assessment
and Regulatory Issues
5.12 Gas
Room 4
Room 10
3.08-I Sodium-cooled Fast Reactor - General
3.10 Lead-cooled Fast Reactor
Room 16
4.01 Human Performance
Session Chair: Tetsushi Hino, Hitachi Ltd.,
Japon
Session Chairs: Dominique Hittner, AREVA,
France; Fu Li, INET, China
Session Chair: Daniele Verwaerde, EDF,
France
Session Chair: Stefano Passerini, Argonne
National Laboratory, USA
Session Chair: Bernard Carluec, AREVA NP,
France
Session Chair: Seung Jun Lee, KAERI, South
Korea
15050 The Spectral Shift Control Reactor as an Option for Much Improved Uranium Utilisation in Single
Batch SMRs, B.A. Lindley, G.T. Parks (University
of Cambridge)
15090 Updated Status of Chinese 2*250MWt
HTR-PM Demonstration Plant, Zuoyi Zhang, Yujie
Dong, Fu Li (INET,Tsinghua University)
15031 Development of Risk Assessment
Methodology against Natural External Hazards for
Sodium-Cooled Fast Reactors: Project Overview
and Strong Wind PRA Methodology,
Hidemasa Yamano, Hiroyuki Nishino, Kenichi
Kurisaka, Yasushi Okano, Takaaki Sakai (JAEA),
Takahiro Yamamoto, Yoshihiro Ishizuka, Nobuo
Geshi, Ryuta Furukawa, Futoshi Nanayama
(National Institute of Advanced Industrial Science
and Technology), Takashi Takata, Emiko Azuma
(Osaka University)
15126 Experimental Platforms in Support of the
ASTRID Program: Existing or Planned Facilities,
O. Gastaldi, G. Rodriguez, L. Ayrault, J. Dumesnil, F. Dujet, C. Journeau, C. Latge, E. Sanseigne,
F. Serre, I. Tkatschenko, G. Willerrmoz (CEA)
15173 Thermal Hydraulic Analysis of Alfred
Bayonet Tube Steam Generator, M. Caramello
(Politecnico di Torino), M. Gregorini (Ansaldo
Nucleare S.p.A), M. De Salve, C. Bertani (Politecnico di Torino), A. Alemberti (Ansaldo Nucleare
S.p.A), B. Panella (Politecnico di Torino)
15035 A Study on Human Performance Enhancement Plan in Maintenance Field by Survey on
Actual Condition of Human Performance Tools,
Jeongjin Park, Hyeonjong Jung, Younggab Kim
(KHNP-CRI)
15023 3RIP Trip Test Simulation of Lungmen
ABWR under Different Power and Flow Conditions,
Shuming Yang (Institute of Nuclear Engineering and
Science, National Tsing Hua University), Hao-Tzu
Lin, Jong-Rong Wang (Institute of Nuclear Energy
Research, Atomic Energy Council), Chunkuan Shih,
Shao-Wen Chen (Institute of Nuclear Engineering
and Science, National Tsing Hua University)
15318 On The Functional Failure Concept and
Probabilistic Safety Margins: Challenges in Application for Evaluation of Effectiveness of Shutdown
Systems, Dumitru Serghiuta, John Tholammakkil
(Canadian Nuclear Safety Commission)
15033 SIMMER-III Parametric Studies of FuelSteel Mixing and Radial Mesh Effects on Power
Excursion in ESFR ULOF Transients, Xue-Nong
Chen, Andrei Rineiski, Lena Andriolo, Rui Li,
Werner Maschek (KIT)
15141 Studies of S-CO2 Power Plant Pipe
Selection and General Layout for Small Modular
Sodium-cooled Fast Reactor, Min-Seok Kim,
Yoon-Han Ahn, Jeong Ik Lee (Korea Advanced
Institute of Science and Technology)
15288 Spatial Neutronics Modelling to Evaluate
the Temperature Reactivity Feedbacks in a Leadcooled Fast Reactor, Stefano Lorenzi, Antonio
Cammi, Lelio Luzzi (Politecnico di Milano)
15207 Model-based System Engineering to
Evaluate I&C Systems Human Performance in
Nuclear Power Plants, Patricia Alves Franca de
Mesquita, David Kessel, Jaecheon Jung (Kepco
International Nuclear Graduate School)
15080 RELAP/SCDAPSIM/MOD3.5 Development
of Severe Accident Models for Heavy Water Reactors Including CANDU and Atucha-2 Analia Bonelli,
Oscar Mazzantini (Licensing, Nuclear Safety and
Core Design, UG-CNAII-IVCN Nucleoeléctrica
Argentina S.A), Daniel Dupleac (Politehnica Universityof Bucharest), Elena Dinca (CNCAN National
Commission for Nuclear Activities), L.J. Siefken,
C.M. Allison, J.K. Hohorst (Innovative Systems
Software)
15348 Modelling of Stratification and Mixing of
a Gas Mixture under the Conditions of a Severe
Accident with Intervention of Mitigating Measures,
M. Andreani, M. Sharabi (Paul Scherrer Institut
(PSI)), A. Bleyer, J. Malet (IRSN), F. Dabbene
(CEA), D. Visser (NRG), S. Benz, Z. Xu (KIT), Z.
Liang (AECL), S. Kelm (FZJ), A. Filippov (IBRAE),
A. Zaytsev (IPPE), M. Kamnev, O. Tyurikov (JSC
Afrikantov), C. Boyd (US NRC)
15388 The MYRRHA Project in Belgium: Status
after the Two First Years of Basic Engineering
Work, Didier De Bruyn, Hamid Aït Abderrahim,
Peter Baeten, Paul Leysen (SCK•CEN)
15251 Development of Simulation Model and
Acceptance Test for Barakah Unit 1 (APR1400
Simulator), Mun-soo Kim, Jin-Hyuk Hong,
Myeong-Soo Lee (Korea Hydro Nuclear Power/
Central Research Institute)
15246 The Model Establishment and Assessment
of Transients for Kuosheng (BWR/6)NPP after
SPU with TRACE/FRAPCON/FRAPTRAN, Fei-Hao
Huang, Chunkuan Shi, Jong-Rong Wang (Institute
of Nuclear Engineering and Science, National Tsing
Hua University), Hao-Tzu Lin (Institute of Nuclear
Energy Research, Atomic Energy Council, R.O.C.),
Wei-Keng Lin, Shao-Wen Chen (Institute of Nuclear
Engineering and Science, National Tsing Hua
University)
1.01 Fuel Use Improvement
Room 15
3:30pm
>
PERIOD 1
2.01 Special Session on HTR-PM Project
15553 Exploring the Feasibility of a Homogeneous
Thorium-Plutonium Cycle for the I2S-LWR Design,
D. Kotlyar, G.T. Parks, E. Shwageraus (University
of Cambridge)
3.01-I Sodium-cooled Fast Reactor - Safety
Room 8
Room 17
5.10-I Codes/Methodologies/Benchmarks
Room 6
Session Chair: Martin Zimmermann, PSI,
Switzerland
15502 Development of RBWR (Resource-renewable BWR) for Recycling and Transmutation of
Transuranium Elements (1) – Overview and Core
Concept, Tetsushi Hino, Takeshi Mitsuyasu, Takuji
Nagayoshi, Masaya Ohtsuka (Hitachi, Ltd.), Kumiaki Moriya (Hitachi-GE Nuclear Energy, Ltd.)
15139 The Progress of HTR Fuel Research and
Manufacture in China, Bing Liu, Changsheng
Deng, Youlin Shao, Jie Zhang, Hongsheng Zhao,
Xiaotong Chen, Yaping Tang, Chunhe Tang (INET,
Tsinghua University)
15052 Sodium Void Map Preparation for the
Safety Analysis of Sodium-cooled Fast Reactors
by Using the Monte-Carlo Code Serpent, Sandro
Pelloni (Paul Scherrer Institut), Manuele Aufiero
(Laboratoire de Physique Subatomique et de
Cosmologie), Sara Bortot, Jiri Krepel, Konstantin
Mikityuk, Anne-Laurene Panadero (Paul Scherrer
Institut), Andreas Pautz (Paul Scherrer Institut;
Ecole Polytechnique Fédérale de Lausanne),
Pierre Sciora (CEA)
15204 Design Study for Reactor System of Fast
Reactor JSFR - Concept of Reactor System -,
Nobuchika Kawasaki, Yoshihiko Sakamoto (Japan
Atomic Energy Agency), Masao Etoh, Yoshihiro
Taniguchi, Yoshio Kamishima (Mitsubishi FBR
Systems, Inc.)
15202 Development of RBWR (Resource-renewable BWR) for Recycling and Transmutation
of Transuranium Elements: (2) Development of
Reactor Internals Shiro Takahashi, Kiyoshi Fujimoto, Noriaki Hamada (Hitachi, Ltd.), Masaaki Tsubaki
(Hitachi-GE Nuclear Energy, Ltd.), Tetsushi Hino,
Masaya Ohtsuka (Hitachi, Ltd.)
15454 Study on Pre-Cooling Transient in Steam
Generator for High Temperature Gas Cooled
Reactor, Yan Wang, Zhihong Liu, Lei Shi
(Tsinghua University), Yanhua Zheng (Tsinghua
University)
15072 On-going Activities in the European
JASMIN Project for the Development and Validation of ASTEC-Na Safety Simulation Code, N.
Girault, L. Cloarec (IRSN), L. Herranz (CIEMAT),
G. Bandini (ENEA), S. Perez-Martin (INR), L.
Ammirabile (JRC)
15325 Evaluation of Design Variants for Improved
Inherent Regulation of Advanced Small Modular
Reactors, R.B. Vilim, S. Passerini (Argonne
National Laboratory)
15415 Human Factors Verification and Validation
Process of the Human System Interface for
Chinese Nuclear Power Plants: Lessons Learned
from New Designs, Pedro Trueba Alonso, Luís
Fernandez Illobre, Fernando Ortega Pascual
(Tecnatom, S.A.)
15326 Development of Complex Simulation Suite
“VEB” and Application Area Expansion, Evgeny
Obraztsov, Denis Kapitsa, Ilya Kremnev, Timofey
Korokhov, Vladimir Kukhtevich, Vladimir Bezlepkin
(JSC ATOMPROEKT)
15229 Validation of the SERPENT and TRACE
Codes Using the SHRT-17 and SHRT-45R Lossof-flow Tests Performed in the EBR-II Reactor,
Youpeng Zhang, Konstantin Mikityuk (PSI)
15331 IAEA NAPRO Coordinated Research
Project: Physical Properties of Sodium, S.
Passerini, C. Gerardi, C. Grandy (ANL), O.E.
Azpitarte (CNEA), E. Bubelis (KIT), M. Chocron
(CNEA), A. Gerschenfeld (CEA), M.L. Japas
(CNEA), S. Jayaraju (Nuclear Research and
consultancy Group), C.H. Latge (CEA), B. Long
(China Institute of Atomic Energy), E. Marinenko
(Institute of Physics and Power Engineering), H.
Ohira (JAEA), S. Perez-Martin (KIT), F. Roelofs
(Nuclear Research and consultancy Group), P.
Selvaraj (IGCAR), Y. Zagorulko (IPPE), S. Monti
(International Atomic Energy Agency)
15003 Lessons Learned from Gen II NPP Staffing
Approaches Applicable to New Reactors, Charles
Thomas Goodnight (Goodnight Consulting, Inc.)
15363 HYMIX Benchmarking Tests: Code-to-code
Comparison, T. Yudina, A. Filippov, A. Kiselev
(Nuclear Safety Institute of the Russian Academy of
Sciences), A. Bleyer, A. Bentaib, J. Malet (IRSN), M.
Andreani, D. Paladino, S. Guentay (PSI), R. Gehr
(Institute for Reactor Safety and Technology, RWTH
Aachen University), S. Kelm (Forschungszentrum
Jülich), H.-J. Allelein (Institute for Reactor Safety
and Technology, RWTH Aachen University; Forschungszentrum Jülich), S. Benz (KIT), T. Jordan
(KIT), Z. Liang (AECL), T. Popova (FSUE State
Research Center of Russian Federation – IPPE)
15067 Effect of Heat Transfer Correlations on
the Fuel Temperature Prediction of SCWRs,
E.-G. Espinosa-Martínez (Universidad Autónoma
Metropolitana-Iztapalapa), C. Martin-del-Campo,
J.-L. François (Universidad Nacional Autónoma
de México), G. Espinosa-Paredes (Universidad
Autónoma Metropolitana-Iztapalapa)
15468 Changes in Nuclear Plant Staffing Requirements Due to Cumulative Impacts of Plant
Aging, Fukushima, and Developing Regulatory
Requirements, Charles Thomas Goodnight
(Goodnight Consulting, Inc.)
Room 7
Session Chair: Michele Andreani, Paul Scherrer
Institut, Switzerland
15381 Analysis of Stratification and Mixing of a
Gas Mixture under Severe Accident Conditions with
Intervention of Mitigating Measures, Jeanne Malet,
Ahmed Bentaib, Pascal Lemaitre, Emmanuel Porcheron (IRSN), Zhe Liang (AECL), Jerome Brinster,
Frederic Dabenne (CEA), Aleksandr Filippov,
Arkady Kisselev, Tatiana Yudina (IBRAE), Alexey
Zaytsev (IPPE), Stephan Kelm (JRC), Zhanjie Xu
(KIT), Christopher Boyd (US NRC), Dirk Visser
(NRG), Mikhail Kamnev, O. Tyurikov (OKBM),
Michele Andreani, Salih Guentay, Guillaume Mignot,
Domenico Paladino (PSI)
15405 Simulation of Unsteady Inhomogeneous
Mixing of Multicomponent Compressible Gas with
the Condensation on the Walls at Considerable
Intervals of Time, Alexey Zaitsev, Mikhail Zaitsev,
Anton Kanaev, Alexander Danilin (Nuclear Safety
Institute)
MONDAY, MAY 4
TECHNICAL SESSIONS
PERIOD 1
3:30pm >> 5:10pm
TRACK 7.
TRACK 6.
3:30pm
3:50pm
4:10pm
4:30pm
4:50pm
5:10pm
TRACK 8.
Thermal Hydraulics Analysis
and Testing
Reactor Physics and Analysis
Fuel Cycle and
Waste Management
TRACK 9.
Materials and Strucural
Issues
TRACK 10.
Nuclear Energy and Climate
Change Mitigation
TRACK 12.
Plant Licensing and
International Regulatory Issues
6.01 Nuclear Data, Monte-Carlo,
VV&UQ
6.08-I Multi-physics Reactor
Simulation
7.01 Containment/Systems Analysis
7.06-I Reactor Thermal Hydraulics
7.10-I Multiphase General
8.01 Gen-II and Gen-III Fuel Developments
9.01-I Structural Material
10.02 Non-electrical and Co-generation Applications of Nuclear Energy
12.01 International / Regulatory
Organizations
Room 12
Room 13
Room 9
Room 11
Room 14
Room 3
Room 1
Room 2
Room 5
Session Chair: Yannick Peneliau, CEA,
France
Session Chair: Anne Nicolas, CEA,
France
Session Chair: Frédéric Dabbene, CEA,
France
Session Chair: Bernard Faydide, CEA,
France
Session Chairs: Françoise Touboul,
CEA, France; Fanny Balbaud, CEA,
France
Session Chair: Augustin Alonso, Madrid
Polytechnic University, Spain
Session Chair: Jukka Laaksonen,
Rusatom Overseas, Finland
15150 JEFF-3.2 Library Validation - Impact
of the New Library for Fast Neutrons SFR
Benchmarks, Y. Peneliau, G. Noguere, O.
Litaize, O. Serot, O. Bouland, P. Archier,
D. Bernard, P. Leconte, C. De Saint
Jean (CEA, Cadarache), C. Jouanne, M.
Coste-Delclaux, S. Mengelle (CEA, Saclay)
15300 Finite Volume Thermal-hydraulics
and Neutronics Coupled Calculations,
Vitor V. Araújo Silva (CNEN/CDTN;DEN,
Universidade Federal de Minas Gerais), A.A.
Campagnole dos Santos, Amir Z. Mesquita
(CNEN/CDTN), Álvaro Bernal, , Gumersindo
Verdú (ISIRYM, Universitat Politecnica de
Valencia), Cláubia Pereira (DEN, Universidade Federal de Minas Gerais)
15237 Implementation of Wall Film
Condensation Model for Two-Fluid Model
in Component Thermal Hydraulic Analysis
Code CUPID, Je-Hee Lee, Goon-Cherl Park,
Hyoung-Kyu Cho (Seoul National University)
15460 Coupled MCNP – SAS-SFR Calculations for Sodium Fast Reactor Core at
Steady-state, Alexander Ponomarev, Anton
Travleev, Werner Pfrang, Victor Sanchez
(KIT)
15466 Monte Carlo MSM Correction Factors
for Control Rod Worth Estimates in Subcritical
and Near-Critical Fast Neutron Reactors, J.-L.
Lecouey (LPC Caen, ENSICAEN, CNRS-IN2P3),
A. Kochetkov, A. Krasa, P. Baeten (SCK/CEN), G.
Ban (LPC Caen, ENSICAEN, CNRS-IN2P3), V.
Bécares (CIEMAT), A. Billebaud, S. Chabod (LPSC,
CNRS-IN2P3, UJF, INPG), T. Chevret (LPC Caen,
ENSICAEN, CNRS-IN2P3), X. Doligez (IPNO,
CNRS-IN2P3, Université de Paris-Sud), F.-R. Lecolley, G. Lehaut, N. Marie (LPC Caen, ENSICAEN,
CNRS-IN2P3), F. Mellier (CEA), W. Uyttenhove
(SCK/CEN), D. Villamarin (CIEMAT), G. Vittiglio, J.
Wagemans (SCK/CEN)
15476 Control Rod Worth Measurement
in a Fast Neutron VENUS-F Critical Core,
A. Kochetkov (SCK-CEN), V. Bécares
(CIEMAT), G. Bianchini, M. Carta (ENEA),
X. Doligez (CNRS\Orsay), V. Fabrizio
(ENEA), A. Krasa (SCK-CEN), G. Lehaut
(CNRS\Caen), W. Uyttenhove (SCK-CEN)
15512 Comparison of SCALE and
SERPENT methodology for LWRs
Transport Calculations and Uncertainty
Analysis for Cross Section Perturbation in the Framework of OEDC/NEA
UAM-Benchmark, A. Labarile, N. Olmo,
R. Miró., G. Verdú. (Institute for Industrial,
Radiophysical and Environmental Safety
(ISIRYM) Universitat Politècnica de
València)
Session Chair: Kazuyuki Takase,
Japan Atomic Energy Agency, Japan
Session Chairs: Roald Wigeland, Idaho
National Laboratory, USA; Sou Watanabe,
Japan Atomic Energy Agency, Japan
15006 Thermal Hydraulic Feedback
Experience on the Phenix FBR, Joel Guidez
(CEA)
15071 SPACE Code Analysis for Reflood
Experiment with Two-group Interfacial
Area Transport Equation of Droplet Field,
Byoung-Uhn Bae, Seung-Wook Lee, SungWon Bae, Kyoung-Doo Kim (Korea Atomic
Energy Research Institute)
15114 New Burnable Absorber Design with
157Gd and 167Er for PWRs, Ho Cheol Shin
(Korea Hydro & Nuclear Power Central
Research Institute), Jiwon Choe, Chidong
Kong, Deokjung Lee (Ulsan National Institute
of Science and Technology)
15438 Getting the Most from Feedback
on the Past French SFRs Structural
Materials for ASTRID Components, Martine
Blat-Yrieix, Jean-Michel Augem (EDF),
Céline Cabet, Yves Lejeail, Christian Billey,
Caroline Bisor (CEA), Sophie Dubiez-Le
Goff, Cyril Pudoyer (AREVA)
15152 Nuclear Desalination Techno-Economic Study for Skikda Site, A. Belkaid,
Y. Bouaichaoui (Centre de Recherche Nucléaire de Birine / Commissariat à l’Energie
Atomique Algérie), H. Chibane (Algerian
Energy Company / Ministry of Energy)
15518 Cooperation of Regulators in Reactor
Design Evaluation - Multinational Design
Evaluation Programme (MDEP), Julien Husse
(OECD Nuclear Energy Agency)
15242 Experimental and Numerical Results
for the Erosion Dynamics of a Vertical
Helium-Air Jet Interacting with a Helium
Rich Layer, R. Kapulla (PSI), S. Kelm (Forschungszentrum Jülich GmbH), G. Mignot,
S. Paranjape, D. Paladino (PSI)
15009 The Application of Flownex in the
Propagation of Uncertainties as Applied to
the IAEA MTR-10 MW Steady State Reactor
Core Model, V. Naicker, M. I. Modukanele, P.
G. Rousseau (North-West University)
15107 Two-Phase Flow Instability and
Bifurcation Analysis of Inclined Multiple
Uniformly Heated Horizontal Channels,
Ashish Mani Mishra, Subhanker Paul,
Suneet Singh, Vikas Pandey (Indian
Institute of Technology Bombay)
15174 Multi-scale Calculation of Carbon Diffusion Behavior in Zirconium and Zirconia,
Yu Xu (Institut Physique Nucleaire Orsay;
EDF), Jerome Roques (Institut Physique
Nucleaire Orsay), Christophe Domain (EDF),
Eric Simoni (Institut Physique Nucleaire
Orsay)
15015 Theoretical Evaluation for the Stability of Liquid Sodium Containing a Titanium
Nanoparticle, Ai Suzuki, Kenji Inaba, Yukie
Ishizawa, Ryuji Miura, Nozomu Hatakeyama, Akira Miyamoto (Tohoku University),
Jun-ichi Saito, Kuniaki Ara (Japan Atomic
Energy Agency)
15180 Development of Nuclear Renewable
Oil Shale Systems for Flexible Electricity
and Reduced Fossil Fuel Emissions, Daniel
Curtis, Charles Forsberg (Massachusetts
Institute of Technology), Humberto Garcia
(Idaho National Laboratory)
15034 Cooperation in Reactor Design
Evaluation and Licensing (CORDEL), Barry
Kaufer (WNA)
15493 AZTLAN: Mexican Platform for
Analysis and Design of Nuclear Reactors,
A.M. Gómez Torres, F. Puente Espel (ININ),
E. del Valle Gallegos (IPN), J.L. François
Lacouture, C. Martín del Campo Márquez
(UNAM), G. Espinosa Paredes (UAM)
15309 Complete CFD Analysis of ERCOSAM-SAMARA Exercises: A Step toward
Advanced Modeling of LWR Containment
Under Severe Accident Conditions, A.S.
Filippov, S.Y. Grigoryev, A.E. Kiselev, O.V
Tarasov, T.A. Yudina, I.V. Ivanov (Nuclear
Safety Institute of the Russian Academy of
Sciences)
15349 The Blowdown Load Test for Steam
Generator Steam Line Break Event in
Pressurized-Water Reactor, Jongin Kim,
Duho Hong, Jinseon Kim, Kyoungho Kang
(Doosan Heavy Industries & Constructions)
15112 Analysis of Density Wave Oscillations for Non-uniform Axial Heat Flux
with a Nodalized Reduced Order Model,
Subhanker Paul, Vikas Pandey, Ashish
Mani Mishra, Suneet Singh (Indian Institute
of Technology Bombay)
15529 Beyond Designed Functional Margins
in CANDU Type NPP: Radioactive Nuclei
Assessment in an LOCA Type Accident,
Andrei Razvan Budu, Gabriel Lazaro Pavel
(University Politehnica of Bucharest)
15168 Advancement of Hotlab/Research
Reactor Techniques with Particular
Reference to the Reactor Pressure Vessel
Materials Examination, Evgenii Krasikov
(National Research Centre «Kurchatov
Institute»)
15272 Optimum Design of Co-generation
System for Nuclear Seawater Desalination,
Yong Hun Jung, Yong Hoon Jeong (KAIST)
15365 Recent Achievements of the EUR Organization (European Utility Requirements For
Advanced Light Water Reactors), Guillaume
Jacquart (EDF), Luc Vanhoenacker (GDF Suez
- Tractebel Engineering), Xavier Pouget-Abadie
(EDF), Antoine Guelfi (EDF), Johan Engström
(Vattenfall)
15537 Update on Capabilities Development at CASL, Paul J. Turinsky (NC State
University), Douglas B. Kothe (Oak Ridge
National Laboratory), Douglas E. Burns
(Idaho National Laboratory)
15382 Comparison of the Suppression
Pool Models for the Lungmen ABWR
Containment Analysis Using GOTHIC, YenShu Chen, Yng-Ruey Yuann, Lain-Su Kao
(Institute of Nuclear Energy Research)
15076 Thermal Hydraulic of the Angra 2
PWR, Javier Gonzalez-Mantecon, Antonella
Lombardi Costa, Maria Auxiliadora Fortini
Veloso, Claubia Pereira, Patricia Amelia
de Lima Reis, Adolfo R. Hamers, Maria
Elizabeth Scari (Universidade Federal de
Minas Gerais)
15147 The Preliminary Thermal-hydraulic
Design of One Superheated Steam
Water Cooled Blanket Concept Based
on RELAP5 and MELCOR Codes, Yun
Guo, Guanghuai Wang, Yangli Cheng,
Changhong Peng (University of Science
and Technology of China)
15095 Effective Method of Reactor-grade
Plutonium Burning out in Reactor VVER,
Sergey Tsibulskiy, Vladimir Davidenko
(National Research Centre «Kurchatov
Institute»)
15248 Study on a Suppression of
Sodium-water Reaction in SFR by Applying
Sodium with Suspended Nanoparticles,
Hironori Kanda, Naoki Yoshioka (Mitsubishi
FBR Systems, Inc.), Kuniaki Ara, Jun-Ichi
Saito, Keiichi Nagai (Japan Atomic Energy
Agency)
15400 A Futuristic View of Nuclear
Supported Coal-to-Liquid, P.W. Stoker, F.H.
Conradie (North West University)
15380 Updated IAEA Requirements for Design
of Nuclear Power Plants, Bernard Poulat
(International Atomic Energy Agency)
15020 Premiering SAFE for Safety Added
Fuel Element, P.K. Bhowmik, J.A. Shamim
(Seoul National University), K.S. Suh (Daeduk Precision), K.Y. Suh (Seoul National
University; PHILOSOPHIA)
15278 Mechanical Behaviour of Structural
Materials in Contact with Liquid Sodium,
Ingrid Proriol Serre, Ouadie Hamdane,
Jean-Bernard Vogt (Unité Matériaux et
Transformations)
15532 Studies of S-CO2 Power Cycle
Application for a Large PWR with a
Desalination Capability, Won Woong Lee,
Yong Hun Jung, Yong Hoon Jeong, Jeong
Ik Lee (Korea Advanced Institute of Science
and Technology)
15048 USNRC Regulatory Activities Related to
Small Modular Reactors and non-Light Water
Reactors, Anna Hajduk Bradford (U.S. Nuclear
Regulatory Commission)
15549 A Generalized Correlation for Steam
Condensation Rates in the Presence of
Air under Turbulent Free Convection, A.
Dehbi (PSI)
TUESDAY, MAY 5
TECHNICAL SESSIONS
TRACK 1.
Water-Cooled Reactor
Programs and Issues
8:00am
8:20am
8:40am
9:00am
9:20am
9:40am
8:00am >> 10:00am
TRACK 2.
High Temperature Reactors
1.02-I SMR (Room 15)
2.02 HTR Development Programs and
Large Test Facilities
Session Chair: Andrew Ballard, Mitsubishi
Heavy Industries Ltd., Japon
Room 15
15366 Light-Water Reactors on Offshore Floating
Platforms: Scalable and Economic Nuclear Energy,
J. Buongiorno, J. Jurewicz, M. Golay, N. Todreas
(MIT)
15509 Advanced Offshore Seabed Reactors, K.
Shirvan, G. Haratyk, R. Ballinger, J. Buongiorno, C.
Forsberg, M. Kazimi, N. Todreas (Massachusetts
Institute of Technology)
>
PERIOD 2
TRACK 3.
Fast Neutron and Other
Innovative Reactors
TRACK 5.
Operation, Performance and
Reliability Management
Plant Safety Assessment
and Regulatory Issues
Room 10
3.11 Molten Salt Reactor
4.02 I&C
5.03 PSA/PRA/Safety Philosophy
Room 16
Room 4
Session Chairs: Dominique Hittner, AREVA,
France; Frederik Reitsma, IAEA, Austria
Session Chair: Andrei Rineiski, KIT, Germany
Session Chair: Elsa Merle-Lucotte, LPSCIN2P3-CNRS / UJF / Grenoble INP, France
Session Chair: Charles Goodnight, Goodnight
Consulting, Inc., USA
Session Chair: Jean-Michel Evrard, IRSN,
France
15172 Overview on Design and Development
Aspects of High Temperature Reactors to Support
Future Energy Needs, Frederik Reitsma (IAEA),
Nils Haneklaus (University of California Berkeley)
15292 An Innovative Methodology for Evaluating
Core Thermal Expansion Feedbacks in Transient
Analyses, Lena Andriolo, Andrei Rineiski,
Xue-Nong Chen, Werner Maschek, Fabrizio
Gabrielli (KIT), Fabienne Delage (CEA), Elsa
Merle-Lucotte (CNRS)
15028 Comparison of Several Recycling
Strategies and Relevant Fuel Cycles for Molten
Salt Reactor, Jiri Krepel, Boris Hombourger, Carlo
Fiorina, Konstantin Mikityuk (PSI)
15100 Technical Challenges and Solutions in the
Largest I&C Modernization Program in the World,
Robert Sommacal, Pascale Baranek, Arnaud
Duthou (Rolls-Royce, Civil Nuclear)
15203 Importance Analysis within a Dempster-Shafer Theory of Evidence Framework of
Uncertainty Representation, Chung-Kung Lo
(Ecole Centrale Paris; Institute of Nuclear Energy
Research), N. Pedroni (Ecole Centrale Paris), E.
Zio (Ecole Centrale Paris; Department of Energy,
Politecnico di Milano)
15208 A Study about Effect of Cell Area on
Maximum Pressure in One-dimensional Steam Explosion Code, Texas-V, E.S. Yoon, Sungchu Song,
YongJin Cho (Korea Institute of Nuclear Safety)
15392 ASTEC Code Development, Validation and
Applications for Severe Accident Management
within the CESAM European Project, J.-P. Van
Dorsselaere, P. Chatelard, K. Chevalier-Jabet
(IRSN), H. Nowack (Gesellschaft für Anlagen- und
Reaktorsicherheit (GRS) mbH), L.E. Herranz
(CIEMAT), G. Pascal (JRC/IET), V. Sanchez-Espinosa (KIT)
15294 Pumps Modelling of a Sodium Fast
Reactor Design and Analysis of Hydrodynamic
Behaviour, J. Ordóñez, A. Lázaro, S. Martorell
(Polytechnic University of Valencia)
15096 Optimising the Refuelling Strategy for a
Denatured Molten Salt Reactor, Kien N. Trinh,
Geoffrey T. Parks, Dani Kotlyar (University of
Cambridge), Manuele Aufiero (Laboratoire de
Physique Subatomique et de Cosmologie)
15102 Spinline™, Benefits of a Nuclear Specific
Safety-critical Digital I&C Platform, Arnaud Duthou, Philippe Mouly, Hélène Jegou (Rolls-Royce,
Civil Nuclear)
15319 The Use of Rod-Based Guaranteed
Shutdown State in CANDU Reactors, Dumitru
Serghiuta, John Tholammakkil (Canadian Nuclear
Safety Commission)
15216 A Study on Ex-vessel Steam Explosion for a
Flooded Reactor Cavity of Reactor Scale, Sungchu
Song, Eisung Yoon, Yunil Kim, Yongjin Cho (Korea
Institute of Nuclear Safety)
15401 Overview of Recent Methods for the
Modeling of the Uncertainties on the Calculations
of Consequences of a Nuclear Power Plant Severe
Accident, K. Chevalier-Jabet (IRSN), X. Zheng
(JAEA), A. Mabrouk (IRSN), Y. Maruyama (JAEA),
J. Baccou (IRSN)
15120 Extension of the FAST Code System for
the Modelling and Simulation of MSR Dynamics,
Matteo Zanetti, Antonio Cammi, Lelio Luzzi
(Politecnico di Milano), Jiří Křepel, Konstantin
Mikityuk (PSI)
15146 A New MV Bus Transfer Scheme for
Nuclear Power Plants, Choong-koo Chang
(KEPCO International Nuclear Graduate School)
15332 The RISMC Approach to Perform
Advanced PRA Analyses, D. Mandelli, C. Smith,
T. Riley, J. Nielsen, A. Alfonsi, C. Rabiti, J. Cogliati
(Idaho National Laboratory)
15307 Protection of French Nuclear Power Plants
against Flooding Risks, Jean Barbaud (EDF)
15426 Overview of Ongoing and Planned R&D
Works on Delayed Releases and FCVS Efficiencies, Laurent Cantrel (IRSN), Luis Herranz (CIEMAT), Serge Guieu (EDF), Thierry Albiol (IRSN),
Remi Collet (AREVA), Terttaliisa Lind (PSI), Teemu
Kärkelä (VTT), Christian Mun, Didier. Jacquemain
(IRSN), Mouheb Chebbi (Université de Lorraine)
15176 The Dual Fluid Reactor - A New Reactor and
Safety Concept, Armin Huke, Götz Ruprecht (Institut
für Festkörper-Kernphysik Berlin), Daniel Weißbach
(Institut für Festkörper-Kernphysik Berlin; Instytut
Fizyki, Wydział Matematyczno-Fizyczny, Uniwersytet
Szczeciński), Stephan Gottlieb (Institut für Festkörper-Kernphysik Berlin), Ahmed Hussein (Institut für
Festkörper-Kernphysik Berlin; University of Northern
British Columbia), Konrad Czerski (Institut für
Festkörper-Kernphysik Berlin; Instytut Fizyki, Wydział
Matematyczno-Fizyczny, Uniwersytet Szczeciński)
15253 Application of Artificial Neural Networks
to CPCS Axial Power Distribution Synthesis,
Y.J. Choi, K.W. Shim, Y.H. Park (KNF), P.S.
Seong (Korea Advanced Institute of Science and
Technology)
15421 Peculiar Roles of the Defense in Depth
and the Probabilistic Safety Assessment in NPP
Safety Performances Optimization, G.L. Fiorini
(Nuclear Safety Consultant), S. La Rovere (NIER
Ingegneria), P. Vestrucci (University of Bologna)
15330 Pressure Estimation of SBO ATWS for
Maanshan PWR, Che-Hao Chen (Institute of Nuclear
Engineering and Science, National Tsing Hua
University), Jong-Rong Wang (Institute of Nuclear Engineering and Science, National Tsing Hua University;
Nuclear and New Energy Education and Research
Foundation), Hao-Tzu Lin (Institute of Nuclear Energy
Research, Atomic Energy Council), Chunkuan Shih
(Institute of Nuclear Engineering and Science, National Tsing Hua University; Nuclear and New Energy
Education and Research Foundation)
15448 The Establishment and Analysis of TRACE
Model for Ultimate Response Guideline of Chinshan
Nuclear Power Plant, Jhin-Jhong Huang (Institute
of Nuclear Energy Research; Department of
Engineering and System Science, National Tsing
Hua University), Jong-Rong Wang (Institute of
Nuclear Engineering and Science, National Tsing
Hua University), Chunkuan Shih, Shao-Wen Chen
(Department of Engineering and System Science;
Institute of Nuclear Engineering and Science, National Tsing Hua University), Lih-Yih Liao, Hao-Tzu Lin
(Institute of Nuclear Energy Research)
15450 Physical Assessment of the Load-following
and Starting Procedures for the Molten Salt Fast
Reactor, Elsa Merle-Lucotte, Daniel Heuer, Axel
Laureau, Mariya Brovchenko, Michel Allibert,
Manuele Aufiero, Pablo Rubiolo (LPSC-IN2P3CNRS / Université Grenoble Alpes)
15371 Issues in Fault-Tolerant Technique
Reliability of Digital I&C Systems, Seung Jun Lee,
Wondea Jung (Korea Atomic Energy Research
Institute)
15461 Probabilistic Risk Assessment (PRA) Update in Light of the Accident at Fukushima Daiichi
Nuclear Power Station, Keisuke Maeda, Hiroshi
Abe, Naoki Hirokawa, Chikahiro Satou (TEPCO
Systems Corporation)
15524 Fuel Cycle Analysis of a Molten Salt
Reactor for Breed-and-Burn Mode, Boris
Hombourger (PSI ; École Polytechnique Fédérale
de Lausanne), Jiri Jiri Krepel, Konstantin Mikityuk
(PSI), Andreas Pautz (PSI, École Polytechnique
Fédérale de Lausanne)
15546 Generic Test Platform for Representative
Tests of Safety I&C Systems, Benoît Fourestie,
Harry Kuck, Jens Richter, Stephan Rieche, Martin
Waitz (AREVA GmbH)
15463 The GEMINI Initiative: A Step forward
towards Nuclear Cogeneration with HTGR, Michael
Fütterer (JRC), Camille Auriault (LGI), Alexandre
Bredimas (Ultrasafe Nuclear), Gerd Brinkmann
(BriVaTech), Vincent Chauvet (LGI), Don J. Halter
(ConocoPhilllips), Mark Haynes (NGNP Industry
Alliance), Dominique Hittner (AREVA), Tomasz
Jackowski (NCBJ), Bernhard Wiechers, Layla
Sandell (Westinghouse), Alexander Racek (SGL),
Kajetan Rozycki (NCBJ), Rainer Schmitt (SGL),
Farshid Shahrokhi, Finis Southworth (AREVA), Harri
Tuomisto (Fortum)
3.01-II Sodium-cooled Fast Reactor- Safety
15177 The Core Instability Analysis under Ocean
Condition with Neutron Coupling Based on
Multi-Point Models, Yun Guo, Guanghuai Wang,
Changhong Peng (University of Science and Technology of China), Tao Tang (ANHUI ANLI Artificial
Leather Co., LTD.)
15451 Marketing the Next Nuclear S-Curve,
Alexandre Bredimas (Ultra Safe Nuclear
Corporation)
15334 Chemical Interactions Experiments
between Supercritical Carbon Dioxide and Liquid
Sodium, Craig Gerardi, Nathan Bremer, Stephen
Lomperski, James J. Sienicki, Chistopher Grandy
(Argonne National Laboratory)
15456 Dynamic Protection of Reactor Plant Equipment in the Floating Power Unit, M.A. Bolshukhin,
V.P. Kondukov, V.A. Panov, V.L. Patrushev, A.N.
Pakhomov, S.A. Solovyov, Yu.P. Fadeev (JSC
“Afrikantov OKBM”)
15066 Experimental Facility for Development
of High-Temperature Reactor Technology:
Instrumentation Needs and Challenges, Piyush
Sabharwall, James O’Brien, SuJong Yoon (Idaho
National Laboratory), Xiaodong Sun (The Ohio
State University)
15355 A New IAEA Coordinated Research Project
on Radioactive Release from Prototype Fast
Breeder Reactor (PFBR) Under Severe Accident
Conditions, S. Monti (IAEA), P. Chellapandi
(IGCAR), I. Piorio (University of Ontario, Institute
of Technology), D. Zhang (CIAE), D. Blanc, N. Girault (IRSN), F. Serre (CEA), M. Schikorr, M. Flad
(KIT-INR), S.W. Lee (KAERI), I. Ashurko (IPPE),
V. Matuzas (Joint Research Centre, Institute for
Energy and Transport)
15151 Thermal Hydraulic Comparison of Helical
Coil and Bayonet Steam Generators for Small
Modular Reactors, M. Caramello, M. De Salve, C.
Bertani, B. Panella (Politecnico di Torino)
15284 New Technological Experimental Helium
Loops, Jana Kalivodová, Karel Gregor, Jan
Berka, Markéta Kryková, Jan Kysela, Jiří Richter
(Centrum výzkumu Řež s.r.o.), Igor Pioro (University of Ontario Institute of Technology Oshawa)
15356 Unprotected Loss of Flow Simulation on
ASTRID CFV V3 Reactor Core, A. Bachrata
(CEA), F. Bertrand (CEA), D. Lemasson (EDF
R&D)
15559 Pioneering SUPER- Small Unit Passively-safe Enclosed Reactor, Palash K. Bhowmik,
Abhinav Gairola, Jubair A. Shamim (Seoul National
University), Keum S. Suh (Daeduk Precision), Kune
Y. Suh (Seoul National University)
TRACK 4.
Room 17
Room 8
5.06 Vapor / Steam Explosion & Flooding
Room 7
Session Chair: Domenico Paladino, Paul
Scherrer Institute, Switzerland
5.10-II Codes/Methodologies/Benchmarks
Room 6
Session Chair: Martin Zimmermann, PSI,
Switzerland
15516 Simulation of MCCI with Top Flooding with
the TOLBIAC-ICB Code, B. Tourniaire (EDF), A.
Boulin, J.F. Haquet (CEA)
TUESDAY, MAY 5
TECHNICAL SESSIONS
PERIOD 2
8:00am >> 10:00am
TRACK 6.
TRACK 7.
Reactor Physics and Analysis
8:20am
8:40am
Fuel Cycle and
Waste Management
TRACK 9.
Materials and Strucural
Issues
TRACK 10.
Nuclear Energy and Climate
Change Mitigation
10.01 Nuclear Energy and Environment: The Life Cycle of Nuclear
Energy
7.02-I Single Phase CFD
7.04-I Thermal Hydraulics Testing
7.06-II Reactor Thermal Hydraulics
8.02 Gen-II and Gen-III Fuel Management
9.03 Corrosion Issues
Room 12
Room 13
Room 9
Room 11
Room 14
Room 3
Room 1
Session Chair: Christine Poinot, CEA,
France
Session Chair: Kazuyuki Takase, Japan
Atomic Energy Agency, Japan
Session Chair: Bernard Faydide, CEA,
France
Session Chair: Cesare Frepoli, FPoliSolutions LLC, USA
Session Chairs: T. K. Kim, ANL, USA; Luc
Van den Durpel, AREVA, France
Session Chairs: Céline Cabet, CEA,
Session Chairs: Shannon M. Bragg-SitFrance ; Ingrid Proriol Serre, Unité Maté- ton, INL, USA
riaux et Transformations, France
15098 Analysis of Vibration-induced
Neutron Noise using One-dimension
Noise Diffusion Theory, Amélie Rouchon,
Richard Sanchez (CEA Saclay)
15070 Thermal-hydraulics/Thermal-mechanics Temporal Coupling for Unprotected
Loss of Flow Accidents Simulations on a
SFR, Cyril Patricot, Grzegorz Kepisty, Karim
Ammar, Guillaume Campioni, Edouard
Hourcade (CEA)
15019 Numerical Investigations of Free-Surface Flows in Spallation Targets for Acceleration-Driven Systems Using TransAT., S.
Thomas (ASCOMP USA Inc.), D. Lakehal
(ASCOMP USA Inc.; ASCOMP Gmbh)
15002 Experimental Investigation on Heat
Transfer Deteriorations of Supercritical
Water in Tube, Hongbo Li (China Nuclear
Power Technology Research Institute),
Weiguo Yang (China General Nuclear Power
Corporation), Meng Zhao, Hanyang Gu
(Shanghai Jiao Tong University), Donghua
Lu, Fei Wang (China Nuclear Power Technology Research Institute)
15061 Validation of MARS-KS Code for
SBO (Station Blackout) Transient with
Operation of the PAFS (Passive Auxiliary
Feedwater System), Byoung-Uhn Bae,
Seok Kim, Yu-Sun Park, Kyoung-Ho Kang
(Korea Atomic Energy Research Institute)
15104 Scale Economies in Monitored
Retrievable Storage, Geoffrey Scott Rothwell
(Nuclear Energy Agency of the Organization
for Economic Cooperation and Development)
15407 Study of the Oxidation Mechanism’s
of 316LN Steel in Liquid Sodium, Matthieu
Rivollier, Jean-Louis Courouau (CEA),
Marie-Laurence Giorgi (CNRS), François
Jomard (CNRS, UMR8635, Groupe d’Etude
de la Matière Condensée), Michel Tabarant,
Cécile Blanc (CEA), Sylvain Vaubaillon
(CEA)
15038 Climate Change: Assessment of the
Vulnerability of Nuclear Power and Cost of
Adaptation, Henri Paillère (OECD/NEA),
Jean-Yves Caneill (EDF Group), Sanna Syri
(Aalto University)
15051 Modular Construction of Nuclear Power
Plants in Korea and Technical Issues, Tae
Il Kim, Keun-Kyeong Kim, Jae-Joon Yoon,
Go Eun Han (Korea Hydro & Nuclear Power
Co.,LTD.)
15198 Application Evaluation of Vanadium
Fixed-incore Detector, Hyeongseog Kim,
Haechan Lee, Younduk Nam, Taeyoung
Yoon (KEPCO Nuclear Fuel, Korea),
Kyoon-ho Cha, Kyung-ho Roh (KOREA
Hydro & Nuclear Power)
15124 Multiscale and Multisolver Pin Power
Reconstruction Approach in a Reactor Core
Calculation, A. Targa (Ecole Polytechnique;
CEA Saclay), J.-C. Le Pallec (CEA Saclay),
P. Le Tallec (Ecole Polytechnique)
15022 Heat Transfer and Pressure Drop
Tests in NANO for Fusion-Fission Hybrid
System, Jubair Ahmed Shamim, Palash
Kumar Bhowmik (Seoul National University),
Kune Y. Suh (Seoul National University;
PHILOSOPHIA Inc.)
15007 Mixing Model for a Downcomer during a Small-Break Loss-of-Coolant Accident
for Use in Fracture-Mechanics Analyses,
Richard Trewin (AREVA GmbH)
15149 Preliminary Accident Analysis of
Flexblue® Underwater Reactor, Geoffrey
Haratyk (DCNS), Vincent Gourmel (DCNS)
15313 Solutions for Management of Defective Fuel Assemblies, V. Vo Van, I. Morlaes
(Used Fuel and Recycling Solutions,
AREVA)
15417 Joint Dissolution and Oxidation
Behavior of 316LN Steel at 550°C in Liquid
Sodium Containing Low Concentration of
Oxygen, Jean-Louis Courouau, Matthieu
Rivollier, Véronique Lorentz, Michel
Tabarant (CEA)
15057 Life Cycle Assessment of the Mark
1 Pebble-Bed, Fluoride-Salt-Cooled,
High-Temperature Reactor, Nicolas Zweibaum, Charalampos Andreades, Sea Hong,
Per F. Peterson (University of California,
Berkeley)
15106 Review of Nuclear New Build in
Relation to Project Structure, Supply Chain and
Financing, Jan-Horst Keppler, Marco Cometto
(OECD/NEA)
15449 Validation of a Lattice Physics
Code GALAXY with New Resonance
and Fast Transport Calculation Method,
Kazuya Yamaji, Hiroki Koike, Yohei Kamiyama, Kazuki Kirimura, Shinya Kosaka,
Hideki Matsumoto (Mitsubishi Heavy
Industries, Ltd.)
15226 Application of the New GeN-Foam
Multi-physics Solver to the European
Sodium Fast Reactor and Verification
against Available Codes, Carlo Fiorina,
Konstantin Mikityuk (PSI)
15258 Numerical Evaluation of SmCo
Permanent Magnet Flowmeter Measuring
Sodium Flow Using FLUENT/MHD Module,
Uiju Jeong (Hanyang University), Tae-Joon
Kim (Korea Atomic Energy Research
Institute), Hong Hyun Son, Gwang Hyeok
Seo (Hanyang University), Ji-Young Jeong
(Korea Atomic Energy Research Institute),
Sung Joong Kim (Hanyang University)
15116 Scaling Distortions Analysis of the
CREST Test Facility, Chuanxin Peng,
Yuanfeng Zan, Yan Zhang, Zhigang Huang,
Wenbin Zhuo, Xiao Yan (Nuclear Power
Institute of China)
15196 Evaluation for LBLOCA of OPR1000
Using KINS Realistic Evaluation Methodology, Byung Gil Huh, Dong-Gu Kang, Jun
Soo Lee, Kwang-Won Seul, Taesuk Hwang
(Korea Institute of Nuclear Safety)
15230 The Choice of the Fuel Assembly for
VVER-1000 in a Closed Fuel Cycle Based
on REMIX-technology, Evgenii Bobrov,
Pavel Alekseev, Alexander Chibinyaev,
Pavel Teplov, Anatoliy Dudnikov (National
Research Centre «Kurchatov Institute»)
15480 Evaluation of the Chemical Compatibility of SiC/SiC Composite Materials in
Nuclear Environments, J. Braun, C. Sauder
(CEA), F. Balbaud (CEA), C. Gueneau, F.
Rouillard (CEA)
15110 Thermodynamic Exergy Analysis
for Small Modular Reactor in Nuclear
Hybrid Energy Systems, Lauren Boldon
(Rensselaer Polytechnic Institute), Piyush
Sabharwall, Cristian Rabiti, Shannon M.
Bragg-Sitton (Idaho National Laboratory), Li
Liu (Rensselaer Polytechnic Institute)
15137 Strategies for Establishing Domestic
Regulatory Infrastructure in an Entrant Country
- Kenya, Hilda K. Mpakany, MyungSub Roh
(KINGS)
15351 Recent Advances In Modeling
of Nuclear Fuels: Analysis of Recently
Proposed Accident Tolerant Fuel Concepts,
Cetin Unal, Jack Galloway (Los Alamos
National Laboratory)
15266 Computatinal Fluid Dynamics Analysis for Predicting External Wind Pressure
Distribution around Stand Alone and cluster
of Natural Draft Cooling Towers, J.S. Bharj,
R.R. Sahaya, M. Singhal, P.K. Malhotra,
S.G. Ghadge (Nuclear Power Corporation of
India Limited)
15159 Nucleate Boiling Heat Transfer
Analysis on Horizontal U-shaped Heat
Exchanger Submerged in Pool Using MARS
Code, Seong-Su Jeon, Soon-Joon Hong,
Da-Hee Park, E-Den Kim (FNC Technology
Co., Ltd.), Hyoung-Kyu Cho, Goon-Cherl
Park (Seoul National University)
15406 Cooling the Intact Loop of Primary
Heat Transport System Using Shut Down
Cooling System after Events Such as
LOCA, Diana Laura Icleanu, Iulia Nicoleta
Jianu (Polytechnic University of Bucharest)
15239 Modelling of Heat and Mass Transfer
in Spent Fuel Cooling Ponds, Reaz Hasan,
Jenna Tudor, Ahmed Ramadan (Northumbria University)
15484 Carbon Activity Measurement by
Using Ferrite Iron Foil and Carburization/
Decarburization Modeling of FMS in Liquid
Sodium Environment at 550°C, Sang Hun
Shin, Jeong Hyeon Lee, Jeong Ki Lee,
Ji Hyun Kim (Ulsan National Institute of
Science and Technology)
15201 Climate Change: How NPP Can
Help Kenya’s Power Generation Sector to
Participate in Climate Change Mitigation,
Aminata Dia, ChoongKoo Chang (KINGS)
15453 Professional Education in the
Framework of the EURATOM FP7 GENTLE
Project, J.L. Kloosterman (Delft University of
Technology (TU Delft)), R.J.M. Konings (Delft
University of Technology (TU Delft); EC, ITU),
D. Manara (EC, ITU), V.H. Sanchez (KIT), M.
Ricotti (POLIMI), R. Tamboer (TU Delft), A.H.
Tkaczyk, J. Hyvärinen (TU)
15496 AREVA Main Steam Line Break
Fully Coupled Methodology Based on CATHARE-ARTEMIS, L. Denis, L. Jasserand,
D. Tomatis, M. Segond, C. Royère, J.-Y.
Sauvage (AREVA)
15267 A Numerical Study of Unsteady Fluid
Flow and Force Distribution in a Normal
Square Tube Array Subject to Cross-flow
Induced Vibrations, J. Berland (LaMSID;
EDF), E. Deri, A. Adobes (EDF)
15187 Experimental Study of Downward-Facing Boiling Heat Transfer with Impinging
Coolant Flow, J.W. Chen, H.E. Hsieh, Y.M.
Ferng, C.Y. Hsu, J.R. Wang (National Tsing
Hua University)
15412 Station Blackout Coping Analysis
of 24 Hours Duration for Lungmen ABWR
Plant, Keng-Hsien Hsu, Yng-Ruey Yuann,
Chin-Tsu Lin, Lain-Su Kao (INER)
15259 Performances and Costs Assessment of an Air Cooled Two-stage Rankine
Cycle for Large Power Plants Operating
with Different Working Fluids, Bo Liu,
Franck David (EDF), Christophe Coquelet
(MINES ParisTech, PSL Research University, CTP - Centre for Thermodynamic
of Processes), Renaud Gicquel, Philippe
Riviere (MINES ParisTech, PSL Research
University, CES - Centre for Energy
Efficiency of Systems)
15528 Status of New Generation IV Projects
for Europe - Economical Integration, Gabriel
Lazaro Pavel, Petre Ghitescu (University
Politehnica of Bucharest)
15467 Release of WIMS10: A Versatile
Reactor Physics Code for Thermal and
Fast Systems, B.A. Lindley, T.D. Newton,
J.G. Hosking, P.N Smith, D.J. Powney, B.
Tollit, P.J Smith (Amec Foster Wheeler)
9:40am
Infrastructure Issues for Nuclear
Power Plant Programs
6.08-II Multi-physics Reactor
Simulation
Room 2
9:00am
9:20am
TRACK 11.
6.02-I Deterministic Methods
Session Chair: Paul J. Turinsky, NC
State University, USA
8:00am
TRACK 8.
Thermal Hydraulics Analysis
and Testing
15194 Effect of Wettability and Capillary
Wicking Changes Induced by Oxidation on
the Pool Boiling Critical Heat Flux, Hong
Hyun Son, Uiju Jeong, Gwang Hyeok Seo,
Gyoodong Jeun Jeun, Sung Joong Kim
(Hanyang University)
15548 Corrosion Behavior of Surface
Treated Ferritic/Martensitic Steel in Liquid
Sodium Environment, Jeong Hyeon Lee,
Sang Hun Shin, Jeong Ki Lee, Ji Hyun Kim
(UNIST)
11.01 Infrastructure Issues
Room 5
Session Chair: Franck Lignini, AREVA,
France
TUESDAY, MAY 5
TECHNICAL SESSIONS
TRACK 1.
Water-Cooled Reactor
Programs and Issues
3:00pm
3:20pm
3:40pm
4:00pm
4:20pm
4:40pm
>
PERIOD 3
3:00pm >> 4:40pm
TRACK 2.
TRACK 3.
High Temperature Reactors
TRACK 4.
Fast Neutron and Other
Innovative Reactors
Operation, Performance and
Reliability Management
TRACK 5.
Plant Safety Assessment
and Regulatory Issues
1.04 Stakeholders’ Assessment
2.03 HTR Physics
2.05 Materials
3.01-III Sodium-cooled Fast Reactor
- Safety
3.08-II Sodium-cooled Fast Reactor
- General
4.03 Aging and Asset Management
5.01-I Systems (Reliability, Assessment, Use)
5.04-I Hydrogen
5.09 Corium/Debris
Room 15
Room 16
Room 2
Room 4
Room 10
Room 17
Room 6
Room 7
Room 8
Session Chair: Jean-Philippe Frontigny,
AREVA, France
Session Chairs: Frederik Reitsma, IAEA,
Austria; James W. Sterbentz, INL, USA
Session Chairs: Céline Cabet, CEA,
France; Olivier Gastaldi, CEA, France
Session Chair: Daniel Blanc, IRSN,
France
Session Chair: Waldemar Geissler,
AREVA, Germany
Session Chair: Giovanni Bruna, IRSN,
France
Session Chair: Mike Kuznetsov, Karlsruhe Institute of Technology, Germany
Session Chair: Paride Meloni, ENEA,
Italy; Felice de Rosa, ENEA, Italy
15235 The EUR Assessment Process,
Methodology and Highlights of the
Compliance Analysis for the EU-APWR
Standard Design, Luca Facciolo (Vattenfall AB), Pekka Nuutinen (Fortum), Daniel
Welander (Vattenfall AB)
15497 Validation of the Physics Analysis
used to Characterize the AGR-1 TRISO
Fuel Irradiation Test, James W. Sterbentz,
Jason M. Harp, Paul A. Demkowicz, Grant
L. Hawkes, Gray S. Chang (Idaho National
Laboratory)
15274 Testing of High Temperature Materials within HTR Program in Czech Republic,
Jan Berka, Jana Kalivodová (Research
Centre Rez)
15352 Purge Simulations on the KASOLA
Sodium Loop: Sensitivity Study and Code-to
Code Comparison, M. Haselbauer, W. Jaeger (KIT), H.V. Hristov, T. Hollands (GRS),
W. Hering (KIT)
15041 In Service Inspection and Repair
of Sodium Cooled ASTRID Reactor Prototype, F. Baque (CEA Cadarache), F. Jadot
(CEA Cadarache), R. Marlier (AREVA NP),
J.-F. Saillant (AREVA NDE Solutions), V.
Delalande (EDF R&D)
15043 Study of Aging Effects in PWR
Power Plants Components, Diogo da Silva
Borges, Deise Diana Lava, Maria de Lourdes
Moreira, Antonio Cesar Ferreira Guimarães
(Instituto de Engenharia Nuclear)
15148 Experimental Activities on
Stratification and Mixing of a Gas Mixture
under the Conditions of a Severe Accident
with Intervention of Mitigating Measures
Performed in the ERCOSAM-SAMARA
Project, F. Dabbene, J. Brinster, D. Abdo
(CEA), E. Porcheron, P. Lemaitre (IRSN),
G. Mignot, R. Kapulla, S. Paranjape (PSI),
M. Kamnev, A. Khizbullin (JSC “Afrikantov
OKB Mechanical Engineering”)
15157 Development and Application of
Surrogate Models for Assessment of Ex-Vessel
Debris Bed Dryout Probability, Sergey E.
Yakush (Institute for Problems in Mechanics),
Nazar T. Lubchenko (Massachusetts Institute of
Technology), Pavel Kudinov (Royal Institute of
Technology (KTH))
15215 Design of the EUR-compliant
EU-APWR, Andrew Ballard, Shigemitsu
Otsuka, Michitaka Kikuta (Mitsubishi Heavy
Industries Ltd.)
15315 Approach to the Development of
Effective 3D Models for Neutron-Physical
Calculations of ASTRA Critical Facility with
the Use of Experimental Information, A.L.
Balainin, V.F. Fomichenko, E.S. Boyarinov,
P.A. Glushkov, G.V. Fomichenko, N.P. Moroz
Kompaniets, V.A. Nevinitsa, A.A. Zimin
(National Research Center “Kurchatov
Institute”)
15444 Anisotropic Behaviour of Grahite
Matrix for HTGR Fuel Compact, Sunghwan
Yeo, Sungok Kim, Moon Sung Cho, YoungWoo Lee KAERI)
15373 Status of the French R&D Program
on the Severe Accident Issue to Develop
GENIV SFRs, F. Serre, F. Bertrand, C.
Journeau, C. Suteau (CEA), D. Verwaerde,
D. Schmitt (EDF –R&D), B. Farges (AREVA
NP)
15383 Performance Test of Under Sodium
Viewer in MONJU, Kosuke Aizawa,
Yoshinori Togashi, Koei Sasaki, Yoshitaka
Chikazawa (JAEA), Masaru Fukuie, Noboru Jinbo (Toshiba Corporation)
15291 Extending PSA Models Including
Ageing and Asset Management, S.
Martorell, I. Martón (Universitat Politècnica
de València, Department of Chemical and
Nuclear Engineering), A.I. Sánchez (Universitat Politècnica de València, Department
of Statistics and Operational Research), S.
Carlos (Universitat Politècnica de València,
Department of Chemical and Nuclear
Engineering)
15026 Verification of SAMG Entry Condition
for APR1400, Junghyun Yun (Korea
Hydro&Nuclear Power Co. Ltd.), Taewan
Kim, Jonghyun Kim (KEPCO International
Nuclear Graduate School)
15357 Main Outcomes from the EUROATOM-ROSATOM ERCOSAM SAMARA
Parallel Projects for Hydrogen Safety of
LWR, Domenico Paladino (PSI), Arkadi
Kiselev (Nuclear Safety Institute of the
Russian Academy of Sciences)
15160 Effect of Corium Non-Homogeneity on
Nordic BWR Vessel Failure Mode and Timing,
Andrei Goronovski, Walter Villanueva, Pavel
Kudinov (KTH), Chi-Thanh Tran (VINATOM)
15402 Overview of Advanced Heavy
Water Reactors from Canada and India
and IAEA-coordinated HWR Technology
Collaborations, Matthias Krause (IAEA)
15470 Assessment of Burnup Calculation
Instabilities in Various HTR Models, Grzegorz Kępisty, Jerzy Cetnar (AGH University
of Science and Technology)
15376 Flammability Diagrams of H2/CO/
CH4 Mixtures Diluted with Helium or Carbon
Dioxide, A. Commandini, J. Biet, M. Idir,
N. Chaumeix (CNRS-ICARE), A. Bentaib
(IRSN)
15552 PWR Circuit Contamination
Assessment Tool: Use of OSCAR Code for
Engineering Studies at EDF, M. Benfarah,
M. Zouiter, T. Jobert (EDF), F. Dacquait, M.
Bultot, J.-B. Genin (CEA, Cadarache)
15324 A Passive System Reliability Analysis for a Station Blackout, Acacia Brunett,
Matthew Bucknor, David Grabaskas, Tanju
Sofu, Austin Grelle (Argonne National
Laboratory)
15360 Experimental Investigation of H2-Air
Deflagration in the Presence of Longitudinal
Concentration Gradients, Mike Kuznetsov
(Karlsruhe Institute of Technology), Joachim
Grune (Pro-Science, Ettlingen), Sergey
Kudriakov, Etienne Studer (CEA, Saclay)
15271 A Simplified Geometrical Model for Transient Corium Propagation in Core for an LWR
with Heavy Reflector, L. Saas, R. Le Tellier, S.
Bajard (CEA)
15099 Licensing Experience with
SPINLINE Digital I&C Platform, Helene
Jegou, Arnaud Duthou, Julien Bach
(Rolls-Royce, Civil Nuclear), Mark
Burzynski (Rolls-Royce Instrumentation
& Controls)
15111 Verification of a Sensitivity and
Uncertainty Analysis Code Based on GPT
Using MHTGR-350 Benchmark, Tae Young
Han, Hyun Chul Lee, Jae Man Noh (Korea
Atomic Energy Research Institute)
15105 Findings of the Second Round of
Fluoride Salt High Temperature Reactor
Materials Irradiation Tests at the MIT
Research Reactor, David Carpenter, Michael
Ames, Gordon Kohse, Yakov Ostrovsky,
Lin-wen Hu (MIT)
Session Chair: Hiroaki Ohira, Japan
Atomic Energy Agency, Japan
15386 Safety Analyses for Sodium-Cooled
15424 Distributed Load Resting Vessel for
Fast Reactors with Pelletized and SphereFast Reactor, Didier Costes (Consultant)
packed Oxide Fuels within the FP-7 European Project PELGRIMM, Werner Maschek,
Lena Andriolo, Claudia Matzerath Boccaccini
(KTI), Fabienne Delage (CEA), Sara Bortot
(PSI), Janne Wallenius (KTH), Alessandro
Del Nevo, Carlo Parisi, Giulia Abbate (Italian
National Agency for New Technologies,
Energy and Sustainable Economic Development), Damien Schmitt (EDF , R&D)
15393 Fuel-sodium Interaction Modelling
with the MC3D Code, Mitja Uršič, Matjaž
Leskovar (Jožef Stefan Institute), Renaud
Meignen (Institut de Radioprotection et de
Sureté Nucléaire)
15439 ASTRID, The SFR GENIV Technology
Demonstrator Project: Where Are We, Where Do
We Stand For?, Jacques Rouault, Eric Abonneau
(CEA), David Settimo (EDF), Jean-Marie Hamy
(AREVA), Hiroki Hayafune (JAEA), René Gefflot
(AIRBUS Defence & Space), René-Paul Benard
(ALCEN/SEIV), Olivier Mandement (ALSTOM),
Thomas Chauveau (BOUYGUES), Grégoire
Lambert (COMEX NUCLEAIRE), Philippe Audouin
(JACOBS), Haruo Mochida (MFBR), Toru Iitsuka
(MHI), Masaru Fukuie (TOSHIBA), John Molyneux
(ROLLS-ROYCE), Jean-Luc Mazel (VELAN)
15440 Japan-France Collaboration on the
Astrid Program and Sodium Fast Reactor,
Jacques Rouault, Pierre Le Coz, JeanClaude Garnier (CEA), Jean-Marie Hamy
(AREVA), Hiroki Hayafune (JAEA), Toru
Iitsuka (MHI), Haruo Mochida (MFBR)
15008 CSNI Post-Fukushima Activity on
Filtered Containment Venting Systems:
Status in OECD Countries and Guidance
for Improvements and Future Designs,
D. Jacquemain (IRSN), S. Guentay (PSI), S.
Basu (USNRC), M. Sonnenkalb (Gesellschaft für
Anlagen- und Reaktorsicherheit), L. Lebel (AECL),
H.-J. Allelein (Lehrstuhl für Reaktorsicherheit
und –technik, RWTH-Aachen), B. Liebana
(IBERDROLA Genaracion Nuclear), B. Eckardt
(AREVA NP GmBH), L. Ammirabile (EC, Joint
Research Centre)
15455 Overview of Spot Experimental
and Analytical Activities with KUPOL, M.
Kamnev, O. Tyurikov, A. Khizbullin (JSC
“Afrikantov OKBM”), D. Paladino, M.
Andreani (Paul Scherrer Institut)
15378 EU-ERCOSAM-SAMARA PROJECT- Scaling from Nuclear Power Plant
to Experiments, S. Benteboula (CEA), J.
Malet, A. Bleyer, A. Bentaib (IRSN), D. Paladino,
S. Guentay, M. Andreani (PSI), I. Tkatschenko, J.
Brinster F. Dabbene (CEA), S. Kelm, H.-J. Allelein
(Forschungszentrum Jülich), D. Visser (Nuclear
Research and Consultancy Group), S. Benz, T.
Jordan (KIT), R. Liang (AECL), A. Kiselev, T. Yudina,
A. Filippov (Nuclear Safety Institute of the Russian
Academy of Sciences), A. Khizbullin, M. Kamnev
(JSC “Afrikantov OKB Mechanical Engineering”), A.
Zaytsev, A. Loukianov (SSC RF-IPPE)
15367 Prediction of Corium Debris Characteristics in Lower Plenum of a Nordic BWR in
Different Accident Scenarios Using MELCOR
Code, Viet-Anh Phung, Sergey Galushin,
Sebastian Raub, Andrei Goronovski, Walter
Villanueva, Kaspar Kööp, Dmitry Grishchenko,
Pavel Kudinov (KTH)
TUESDAY, MAY 5
TECHNICAL SESSIONS
PERIOD 3
3:00pm >> 4:40pm
TRACK 6.
TRACK 7.
Reactor Physics and Analysis
3:20pm
3:40pm
4:00pm
4:20pm
4:40pm
7.02-II Single Phase CFD
Fuel Cycle and
Waste Management
7.06-III Reactor Thermal Hydraulics
7.12 LOCA
8.03 UNF and Waste Management
TRACK 9.
Materials and Strucural
Issues
9.01-II Structural Material
TRACK 12.
Plant Licensing and
International Regulatory Issues
12.02 Instrumentation & Control / Equipment
/ System Applications
6.02-II Deterministic Methods
6.05-I Reactor Analysis
Room 13
Room 9
Room 11
Session Chair: Deokjung Lee, UNIST, South
Korea
Session Chair: Frédéric Damian, CEA, France
Session Chairs: Christophe Calvin, CEA,
France; Kazuyuki Takase, Japan Atomic
Energy Agency, Japan
Session Chair: David Pialla, CEA, France
Session Chair: Koroush Shirvan, MIT, USA
Session Chairs: Charles Forsberg, MIT, USA;
Luc Van den Durpel, AREVA, France
15213 Enhancement of Direct Whole Core Calculation Code nTRACER with WIMS-based Library and
Comparative Analyses, Meer Bacha, Chang Hyun
Lim, Han Gyu Joo (Seoul National University)
15060 Neutronic Feasibility Study of a Soluble
Boron-Free PWR with the BigT Burnable Absorbers, Mohd-Syukri Yahya, Yonghee Kim (Korea
Advanced Institute of Science and Technology),
Chang Kyu Chung (KEPCO E&C)
15056 Analysis of the Interaction of Round Jets
with Stratified Light Gas Layers with a Simple
Turbulence Model, A. Krakovich (Soreq NRC), U.
Bieder (CEA)
15036 Simulation of Reactivity Initialized Transients at Different Power Levels for Molten Salt
Reactor Using Modified TRACE, Xun He, Rafael
Macián-Juan (Technische Universität München),
Marcus Seidl (E.ON Kernkraft GmbH)
15017 Analysis on Postulated Double Ended
Guillotine Pipe Break in Reactor Inlet Header
For KAPP-3&4 Using Computer Code RELAP-5/
Mod3.2, P. Krishna Kumar, H.P. Rammohan
(Nuclear Power Corporation of India Ltd.)
15010 Selection a Tool To Support Decision
Making For Site Selection For High Level Waste,
J.G. Madeira (Celso Suckow Fonseca Federal
Center for Technological Education), Antônio
Carlos M. Alvim Alvim), Vivian B. Martins, Nilton
A. Monteiro (Federal University of Rio de Janeiro)
15162 Comparison between Measured and
Predicted Properties of the Samples from Decommissioned RPVs, E.A. Krasikov (National Research
Centre «Kurchatov Institute»)
15016 Regulatory Experience on the Smart Transmitters of SKN 3&4, Youngmi Kim, Choongheui
Jeong (Korea Institute of Nuclear Safety)
15127 An Equivalent Correction of U-238
Resonance Up-scattering in 3-D Reactor Simulator
ASTRA, C.O. Park, C.K. Lee, H.C. Lee, J.Y. Yoon,
S.W. Park, B.J. Cho (KEPCO Nuclear Fuel)
15384 An Automatic System to Search for the
Optimal Loading Pattern of Boiling Water Reactors, Po-Feng Lin, Chien-Hsiang Chen, Lain-Su
Kao (Institute of Nuclear Energy Research)
15277 Numerical Simulation of Rib-Roughened
Flow in Advanced Gas Cooled Reactor, Vineet
Vishwakarma, Sanjeev Kumar, Arun Kumar Saha,
Prabhat Munshi (Indian Institute of Technology
Kanpur)
15128 OECD/NEA Main Steam Line Break
Benchmark Problem Simulation Using the SPACE
Code, Yo-Han Kim, Seyun Kim, Dong-Hyuk Lee,
Sang Jun Ha (KHNP Central Research Institute)
15024 A Study of Different Cases of VVER
Reactor Core Flooding in a Large Break Loss
of Coolant Accident, Yu.A. Bezrukov, V.I. Schekoldin, S.I. Zaitsev, A.N. Churkin, E.A. Lisenkov
(OKB «GIDROPRESS»)
15232 The Study of the National Context in
Support of Planning Geological Disposal in
Romania, Veronica Andrei (Romanian Association
for Nuclear Energy (AREN)), Ilie Prisecaru
(University Politehnica of Bucharest)
15308 Mechanisms for Neutron Damage in
Graphite from Low to High Temperatures from
First Principles, Malcolm I. Heggie, Christopher D.
Latham, Alice J. McKenna, Thomas P. Trevethan,
Phillipa J.L. Young (University of Surrey)
15227 Development of Quadruped Robot for Disaster Site: Improvement of Stable Walking Control on
Uneven Terrain, Naotaka Suganuma, Yusuke Mitsuya, Takafumi Sonoura, Kenji Matsuzaki, Takuya
Uehara, Norihito Nakamura (Toshiba Corporation)
15339 Mutual Self-shielding in the Subgroup
Method, Nathan Andrew Gibson, Benoit Forget
(Massachusetts Institute of Technology)
15385 Azimuthal Power Disequilibrium Estimate
through Control Rod Worth Measurement for
GEN III+ PWRs, Federico Rocchi, Roberto
Pergreffi (ENEA), Franck Boreicha, Antonio
Sargeni, Giovanni Bruna (IRSN)
15327 Uncertainty and Sensitivity Analysis of
the TALL-3D Experiment Using Thermal-Hydraulic Coupled Codes, Clotaire Geffray, Rafael
Macián-Juan (Technische Universität München),
Angel Papukchiev (Gesellschaft für Anlagen- und
Reaktorsicherheit mbH), Dmitry Grishchenko,
Pavel Kudinov (KTH)
15290 Fuel Rod Uncertainty Analysis of Kuosheng NPP with TRACE/FRAPTRAN/DAKOTA
codes in SNAP interface, S.W. Chen, H.C.
Chang, W.K. Lin, W.Y. Li, C. Shih, J.R. Wang
(National Tsing Hua University), H.T. Lin (Institute
of Nuclear Energy Research)
15169 Notes on the Implementation of an Improved Bottom-Up Reflood Entrainment Model for
a Large Break LOCA Evaluation Model, Cesare
Frepoli, Joseph W. Fricano (FPoliSolutions LLC),
Reiko Narutomi, Tetsuya Teramae (Mitsubishi
Heavy Industries, LTD.)
15430 Preliminary Assessment of Radiation Impact from Conceptional Interim Storage Facilites
for PWR Spent Nuclear Fuel in South Korea,
Hoseog Dho, Taeman Kim, Changteal Baeg
(Korea Radioactive Waste Ageny), Gilyong Cha,
Soonyoung Kim (Radiation Core Technologies,
Co. Ltd.)
15418 Helium Behavior in Implanted B4C Boron
Carbide, V. Motte, D. Gosset (CEA), S. Miro (CEA),
S. Doriot (CEA), S. Surble (CEA), N. Moncoffre
(CNRS-IN2P3, IPNL, Université Lyon I)
15545 AREVA Advanced Safety I&C Solutions and
Licensing Experience for New Nuclear Builds and
Modernization Projects, Benoît Fourestie (AREVA
GmbH), Philippe Hilsenkopf, Philippe Paris (AREVA
NP), Johannes Pickelmann, Steffen Richter
(AREVA GmbH)
15328 Development of a Multi-Scale Thermal-Hydraulic Model of the TALL-3D Facility
and Validation with Experimental Data, Clotaire
Geffray, Rafael Macián-Juan (Technische Universität München), Angel Papukchiev (Gesellschaft
für Anlagen- und Reaktorsicherheit mbH), Dmitry
Grishchenko, Pavel Kudinov (KTH)
15370 Evaluation of Accident Mitigation
Procedures with Isolation Condensers for LWR
by Reactor Simulation Analyses, Hiroki Kokami,
Yuhei Hamada, Shuichiro Miwa, Hiroto Sakasita,
Michitsugu Mori (Hokkaido University)
15481 Influence of the Austenitic Stainless Steel
Microstructure on the Void Swelling under Ion
Irradiation, Baptiste Rouxel, Caroline Bisor, Yann
Decarlan, Arnaud Courcelle, Alexandre Legris (CEA
Saclay)
15556 An Approach to Merge PSA-based Assumptions and BEPU Method, Sebastián Martorell,
Aurelio Lázaro, Isabel Martón, Francisco Sanchez,
José. F. Villanueva, Ana I. Sánchez, Sofía Carlos
(Universtitat Politècnica de València)
Room 12
3:00pm
TRACK 8.
Thermal Hydraulics Analysis
and Testing
15543 Solving the Neutron Slowing down Equation
and Computing Self-Shielded Cross Sections,
Bertrand Mercier (Conservatoire National des
Arts & Métiers), Peng Jinghan Arthur (Institut
Franco-Chinois de l’Energie Nucléaire, Sun Yat-sen
University)
15464 CFD Simulation of Natural Convection in
a Passive Moderator Cooling System of an Advanced Nuclear Reactor, Eshita Pal, Jyeshtharaj
B. Joshi (Homi Bhabha National Institute), A.K.
Nayak, P.K. Vijayan (Bhabha Atomic Research
Centre)
Room 14
15183 Simulation Study of Pressure Evolution in
the Helium Gap of In Pile Section of CALLISTO
Test Facility in the Case of LBLOCA and Closed
Blocked Safety Valve Using the Computer Code
RELAP5/SCDAP3.2, Hadjam Ahmed (Nuclear
Research Center of BIRINE), Souidi Ferhat
(University of Science and Technology Houari
Boumediene USTHB), Loubar Ahcene (Nuclear
Research Center of BIRINE), Weber Marcel
(Nuclear Research Center SCKCEN)
15442 Comparison of CATHARE Results with the
Experimental Results of Cold Leg Intermediate
Break LOCA Obtained during ROSA-2/LSTF Test
7, Piotr Mazgaj (EDF; Institute of Heat Engineering, Warsaw University of Technology), Jean-Luc
Vacher (EDF), Sofia Carnevali (CEA)
Room 3
Room 1
Session Chairs: Didier De Bruyn, SCK•CEN,
Belgium; Y. De Carlan, CEA, France
15486 Investigation of the Relationships between
Mechanical Properties and Microstructure in Fe-9%
Cr ODS Steel, B. Hary, T. Guilbert (Service de
Recherches en Métallurgie Appliquée, CEA Saclay),
T. Baudin (Institut de Chimie Moléculaire et des
Matériaux d’Orsay), Y. de Carlan, P. Wident (CEA
Saclay)
Room 5
Session Chairs: Françoise De Bois, AREVA,
France
>
WEDNESDAY, MAY 6 PERIOD 4
TECHNICAL SESSIONS
TRACK 1.
Water-Cooled Reactor
Programs and Issues
8:00am
8:20am
8:00am >>10:00am
9:20am
9:40pm
TRACK 4.
Fast Neutron and Other
Innovative Reactors
High Temperature Reactors
Operation, Performance and
Reliability Management
TRACK 5.
Plant Safety Assessment
and Regulatory Issues
1.02-II SMR
2.04 Thermal-hydraulics
2.07 ATHR
3.01-IV Sodium-cooled Fast Reactor
- Safety
3.05-I Sodium-cooled Fast Reactor Neutronics and Fuel
3.07 Sodium-cooled Fast Reactor Technology
4.04-I Equipment Testing and
Maintenance
5.01-II Systems (Reliability, Assessment, Use)
5.04-II Hydrogen
Room 15
Room 16
Room 9
Room 4
Room 10
Room 5
Room 17
Room 6
Room 7
Session Chair: John Sulley,
Rolls-Royce, United Kingdom
Session Chair: C.G. Du Toit, North-West
University, South Africa
Session Chairs: Michael Fütterer, JRC
Petten, The Netherlands; James W.
Sterbentz, INL, USA
Session Chair: Jean Claude Garnier, CEA,
France
Session Chair: Carlo Fiorina, Paul
Scherrer Institut, Switzerland
Session Chair: Janos Gadó, MTA EK,
Hungary
Session Chair: Hiroaki Ohira, Japan
Atomic Energy Agency, Japan
Session Chair: Boris Dimitrov, IRSN,
France
Session Chair: Ahmed Bentaib, IRSN,
France
15108 Sensitivity Study of the Factors
Affecting First-of-a-Kind and Nth-of-a-Kind
Small Modular Reactor Investment Costs,
Lauren Boldon (Rensselaer Polytechnic
Institute), Piyush Sabharwall (Idaho National
Laboratory), Erich Schneider (University
of Texas at Austin), Li Liu (Rensselaer
Polytechnic Institute)
15338 Assessment of the Crossflow Loss
Coefficient in the Very High Temperature
Reactor Core, Sung Nam Lee, Nam-il Tak,
Min Hwan Kim, Jae Man Noh (KAERI)
15118 Achieving Salt-Cooled Reactor Goals:
Economics, Variable Electricity, No Major
Fuel Failures, Charles Forsberg (Massachusetts Institute of Technology)
15280 TRACE Code Application to the
DBA Assessment for Sodium Cooled Fast
Reactors, Andong Shin, Yong-won Choi,
Young Seok Bang (Korea Institute of Nuclear
Safety)
15059 Neutronic Analysis of a Small
B&BR in View of Burnup-Dependent
Fuel Swelling, Donny Hartanto, Yonghee
Kim (Department of Nuclear & Quantum
Engineering, KAIST)
15068 Preliminary Studies of Na-CO2 Interaction Byproduct Cleaning Agent for SFR
Coupled to S-CO2 Power Cycle, Hwa-Young
Jung (KAIST); Div. Fast Reactor Technology
Demonstration, (KAERI), Jeong Ik Lee
(KAIST), Myung-Hwan Wi (Div. Fast Reactor
Technology Demonstration, (KAERI), Hong
Joo Ahn (Div. Nuclear Chemistry Research,
(KAERI)
15083 Replacement of Fine Particle
Purification Filter of the PHT Purification
System, Dong Suk Lee (Korea Hydro &
Nuclear Power)
15445 Assessment of the Penetration Weld
Failure for APR 1400, Jaehoon Jung, Sang
Mo An, Kwang Soon Ha, Hwan Yeol Kim
(Korea Atomic Energy Research Institute)
15312 Containment Hydrogen Concentration
Monitoring: Considerations From AP1000®
Plant Projects, Ryan D. Griffin (Westinghouse
Electric Company LLC), Zoran Vujic (Westinghouse Electric Germany GmbH), William
Turkowski (Westinghouse Electric Company
LLC)
15064 Exploratory Studies of Small
Modular Reactors Using the ASTEC
Code, Mirco Di Giuli (University of
Bologna), Marco Sumini, Giacomino
Bandini (ENEA, UTFISSM-SICSIS),
Lionel Chailan (Institut de Radioprotection
et Sûreté Nucléaire (IRSN))
15167 A Methodology for the Characterization of the Effective Thermal Conductivity in
the Near-wall Region of a Packed Pebble
Bed, P.G. Rousseau, C.G. Du Toit, M. De
Beer (North-West University)
15073 The Effects of Variations of UO2 Fuel,
FLiBe and Graphite Moderator Composition
and Proportions on a Small Fluoride Saltcooled, High-temperature Reactor, Hassan
Mohamed, Geoffrey T. Parks, Eugene
Shwageraus (University of Cambridge)
15358 Evaluation of the Behaviors of the
SFR-v2 and CFV-v1 Cores during an ULOF
with SIMMER-III, S. Poumerouly (EDF),
D. Ribot (Ecole des Mines de Paris), A.
Bachrata (CEA)
15091 Low Void Effect (CFV) Core
Concept Flexibility : from Self-breeder to
Burner Core, L. Buiron (CEA), L. Dujcikova
(University of Technologyin Bratislava)
15132 Large Electro-magnetic Pump Design
for Application in the Astrid Sodium-Cooled
Fast Reactor, Tetsu Suzuki, Hidetsugu
Matsuzawa (Advanced System Design &
Engineering Dept., Toshiba Corporation
Power Systems Company), Rie Aizawa
(Plant project engineering Dept., Toshiba
Corporation Power Systems Company), Guy
Laffont, Olivier Gastaldi (CEA Cadarache)
15101 Key Developments of a Rod Control
System, Marc Pouillot, Hélène Jegou,
Arnaud Duthou (Rolls-Royce, Civil Nuclear)
15446 Experimental Investigation on
APR1400 In-Core Instrumentation Penetration Failure during a Severe Accident,
Sang Mo An, Jaehoon Jung, Kwang Soon
Ha, Hwan Yeol Kim (Korea Atomic Energy
Research Institute)
15490 CSNI Post-Fukushima Activity on
Hydrogen - Part I: Hydrogen Management,
Z. Liang (Canadian Nuclear Laboratories), M.
Sonnenkalb (Gesellschaft für Anlagen- und
Reaktorsicherheit), A. Bentaib (Institut de
Radioprotection et de Sûreté), M. Sangiorgi
(European Commission - Joint Research
Centre)
15433 Safety Improvement in Building
Layout Design to Meet the Safety Design
Criteria for the Generation IV SFR, Atsushi
Katoh, Yoshitaka Chikazawa, Kunihiko
Nabeshima (JAEA), Mikinori Iwasaki, You
Akiyama, Takeaki Ohya (MFBR)
15144 3-D Fuel Shuffling for Reduced
Peak Burnup and Increased Uranium
Utilization of Breed-and-Burn Reactors,
Jason Hou (University of California, Berkeley), Staffan Qvist (Uppsala University),
Ehud Greenspan (University of California,
Berkeley)
15236 ASTRID SFR Prototype Steam Generator Design Evolution Related to Safety
and Cost Issues, Antony Woaye Hune,
Alain Gerber, Jean-Philippe Pirus, Laurent
Soucille (AREVA NP), Gilles Rodriguez,
François Beauchamp (French Commission
for Atomic Energy and Alternative Energy)
15387 Next Generation of Optical Front
Ends for Numerical Services, Marc Fullenbaum, Alain Durieux, Guilhem Dubroca,
Philippe Fuss (Sodern)
15534 Experimental Validation of the
Concept of Long-term Passive Cooling System of Emergency Cooldown Tank, Myoung
Jun Kim (Kookmin University, Korea), Joo
Hyung Moon, Youngmin Bae, Young In Kim
(Korea Atomic Energy Research Institute),
Hee Joon Lee (Kookmin University, Korea)
15491 CSNI Post-Fukushima Activity on
Hydrogen - Part II: Computer Codes and
Validations, Z. Liang (Canadian Nuclear
Laboratories), M. Sonnenkalb (Gesellschaft für
Anlagen- und Reaktorsicherheit), A. Bentaib
(Institut de Radioprotection et de Sûreté),
M. Sangiorgi (European Commission - Joint
Research Centre)
15488 Improved Modelling of Sodium-Spray
Fires and Sodium-Combustion Aerosol
Chemical Evolution, Emmanuel Mathe
(IRSN), Martin Kissane (IRSN, current affiliation OECD Nuclear Energy Agency), Denis
Petitprez (PC2A, University of Lille 1)
15165 Development and Validation of
the TOPAZ Design Option for Minimizing
the Void Effect in Large SFR Cores, Anne-Claire Scholer, Denis Verrier (AREVA)
15293 Three-dimensional Multi-Physics
Model of the European Sodium Fast Reactor
Design Applied to DBA Analysis, Aurelio Lázaro, Jose Ordoñez (Universtitat Politècnica
de Valencia), Przemyslaw Stanisz (Faculty
of Energy and Fuels, AGH University of
Science and Technology), Luca Ammirabile,
Haileyesus Tsige-Tamirat (Joint Research
Centre - Institute for Energy and Transport),
Sebastián Martorell (Universtitat Politècnica
de Valencia)
15012 Replacement of Upper Core Structure in Experimental Fast Reactor Joyo: (1)
Existing Damaged Upper Core Structure
Jack-up Test, Hiromichi Ito, Nobuhiro
Suzuki, Tetsuhiko Kobayashi, Hirotaka
Kawahara, Akinori Nagai (JAEA), Ryuta
Sakao, Chotaro Murata, Jyunya Tanaka,
Yasunori Matsusaka, Takahiro Tatsuno
(Mitsubishi Heavy Industries, LTD.)
15550 Comparison of Containment Dousing
System Response for a CANDU 6 Station
Blackout Sequence Using MAAP4-CANDU
(v4.0.7) and GOTHIC (v7.2B), Sergei M
Petoukhov (Canadian Nuclear Laboratories), Tuan Hoang Nguyen (Candu Energy
Incorporated)
15113 Introduction to Integrated Test Facility for
Assessment of Containment Integrity in Severe
Accident Conditions, Young Su Na, Seong-Ho
Hong, Seong-Wan Hong (Korea Atomic Energy
Research Institute)
15245 Assessment of Similarity for The
Radial Expansion Experiment Model at the
BFS Facility, Sunghwan Yun, Sang-Ji Kim
(Korea Atomic Energy Research Institute)
15362 Status of the Sodium Gas Heat
Exchanger (SGHE) Development for
the Nitrogen Power Conversion System
Planned for the ASTRID SFR Prototype,
L. Cachon, F. Vitillo, C. Garnier, X.
Jeanningros, E. Rigal, F. Le Bourdais, S.
Madeleine, O. Gastaldi, G. Laffont (French
Alternative Energies and Atomic Energy
Commission)
15013 Replacement of Upper Core Structure in Experimental Fast Reactor Joyo:
(3) Development of In-Vessel Observation
Techniques for UCS Replacement, Eiji
Okuda, Jun Sasaki, Nobuhiro Suzuki,
Misao Takamatsu, Akinori Nagai (Japan
Atomic Energy Agency)
8:40am
9:00am
TRACK 3.
TRACK 2.
15171 Sustainability of Thorium-Uranium in
Pebble-bed Fluoride Salt-cooled High Temperature Reactor, Guifeng Zhu (Shanghai
Institute of Applied Physics, Chinese Academy of Sciences; Graduate University of
Chinese Academy of Sciences), Yang Zou,
Hongjie Xu (Shanghai Institute of Applied
Physics, Chinese Academy of Sciences; Key
Laboratory of Nuclear Radiation and Nuclear
Energy Technology, Chinese Academy of
Sciences)
15261 Feasibility Study on Core Cooling
Systems for Research Reactor, In Sub
Jun, Soo Hyung Yang (Korea Atomic
Energy Research Institute)
15027 A System CFD Model of the Heat
Transfer in a Prismatic Block of a VHTR,
C.G. Du Toit, P.G. Rousseau, P. Sambureni,
L.A. Le Grange (North-West University)
15414 Assessment of the Density Lock
as a Passive Safety Feature for a Small
Modular Reactor, Tian Zhang (RWTH
Aachen University; Forschungszentrum
Juelich GmbH), Francesco Tantillo
(RWTH Aachen University; Forschungszentrum Juelich GmbH), Stephan
Kelm (Forschungszentrum Juelich
GmbH), Hans-Josef Allelein (RWTH
Aachen University; Forschungszentrum
Juelich GmbH)
15283 Optimization of Lower Plenum Structure for Mixing Promotion during Normal
Operation Conditions - High Temperature
Test Facility at Oregon State University, M.J.
Gradecka, B.G. Woods (Oregon State University), P. Furmański (Warsaw University of
Technology)
15185 Role and Status of Scaled Experiments in the Development of FluorideSalt-Cooled, High-Temperature Reactors,
Nicolas Zweibaum, Lakshana Huddar
(University of California, Berkeley), Joel T.
Hughes (University of New Mexico), Michael
R. Laufer (University of California, Berkeley),
Edward D. Blandford (University of New
Mexico), Raluca O. Scarlat (University of
Wisconsin), Per F. Peterson (University of
California, Berkeley)
15427 Depressurized Loss of Coolant
Accident Mitigation Method Framework at
Oregon State University High Temperature
Test Facility, Izabela Gutowska (Warsaw
University of Technology), Brian Woods
(Oregon State University), Piotr Furmański
(Warsaw University of Technology)
15190 Thermophysical Property Sensitivity
Study of LiF-BeF2 and NaFZrF4 Coolants
on Thermal Hydraulic Licensing Limits for
a Fluoride Salt Cooled High Temperature
Test Reactor, R.R. Romatoski, L.W. Hu,
C.W. Forsberg (Massachusetts Institute of
Technology)
15390 Development of «Balance of
Plant» Simulator of the DMS for Co-Generation, Tomohiko Ikegawa, Kazuaki
Kito (Hitachi, Ltd., Hitachi Research
Laboratory), Koji Nishida (Hitachi-GE
Nucelar Energy, Ltd.)
15021 Replacement of Upper Core Structure in Experimental Fast Reactor Joyo:
(2) Development of Cover Gas Recycling
System with Precise Pressure Control, Hiroshi Ushiki, Eiji Okuda, Nobuhiro Suzuki,
Katsu Ohta, Hirotaka Kawahara, Misao
Takamatsu (JAEA)
WEDNESDAY, MAY 6 PERIOD 4
TECHNICAL SESSIONS
TRACK 5.
Plant Safety Assessment
and Regulatory Issues
8:20am
8:40am
9:00am
9:20am
9:40pm
TRACK 6.
6.02-III Deterministic Methods
Room 12
Session Chair: Christophe Herer, IRSN,
France
TRACK 8.
TRACK 7.
Reactor Physics and Analysis
5.13 Ongoing Programs and
Regulatory Issues
Fuel Cycle and
Waste Management
Thermal Hydraulics Analysis
and Testing
8.04 Gen-IV and Advanced Fuel and
Waste Management
TRACK 9.
Materials and Strucural
Issues
9.04 Fuel/clad Material
Room 13
7.04-II Thermal Hydraulics Testing
Room 11
7.13-I Advanced Concepts
Session Chair: Jean-François Vidal, CEA,
France
Session Chair: Cecilia Martin-del-Campo,
Universidad Nacional Autónoma de México,
Mexico
Session Chair: Cesare Frepoli, FPoliSolutions
LLC, USA
Session Chair: Stefano Passerini, Argonne
National Laboratory, USA
Session Chairs: Vladimir Kuznetsov, IAEA,
Austria; Temitope Taiwo, Argonne National
Laboratory, USA
15408 Post-Fukushima Severe Accident Research
Activities at NRC Addressing Near Term Task Force
Recommendations, Sudhamay Basu, Hossein
Esmaili, Allen Notafrancesco, Donald Algama,
Richard Lee (United States Nuclear Regulatory
Commission)
15075 Explicit Modeling of a VVER-1000 Radial
Reflector by a Ring of Assembly-Size Nodes,
Emiliya Georgieva (Risk Engineering Ltd.; KIT),
Kostadin Ivanov (The Pennsylvania State University), Robert Stieglitz (KIT)
15254 IAEA ADS Benchmark Analysis of KUCA
Experiments: Phase I, Wonkyeong Kim, Deokjung
Lee (UNIST), Cheol Ho Pyeon (Nuclear Engineering Science Division, (KURRI)
15209 Supplementation and Validation of Heat
Transfer Model in MARS-LMR for Sodium-Air
Heat Exchanger in Sodium-cooled Fast Reactor,
Chiwoong Choi, Kwiseok Ha (KAERI)
15040 MHD Instability Analysis of a Large Scale
Electromagnetic Pump for the PEMDYN Facility,
L. Goldsteins (CEA Cadarache; Grenoble Institute
of Technology (INPG); University of Latvia (UL)),
L. Buligins (University of Latvia (UL)), Y. Fautrelle
(Grenoble Institute of Technology (INPG)), C.
Biscarrat (CEA Cadarache), E. Platacis (Institute
of Physics University of Latvia (IPUL))
15483 Heterogeneous World Model and
Collaborative Scenarios of Transition to Globally
Sustainable Nuclear Energy Systems, Vladimir
Kuznetsov, Galina Fesenko (International Atomic
Energy Agency)
15045 Hydrogen Uptake of Zircaloy-4 during
Reaction in Nitrogen/Steam Atmosphere in the
Temperature Range of 600 - 1100°C, M. Grosse,
M. Steinbrueck (Karlsruhe Institute of Technology),
L. Ott (INP ENSIACET), A. Kaestner (Paul Scherrer
Institut)
15423 The Solution on the Revision of Current RIISI Program with New Evidence of Seismic Hazard,
Wei-Chang Chen, Chun-Chang Chao (Institute of
Nuclear Energy Research)
15154 Research on an Iterative Pin Power
Reconstruction Method in Core Simulator of
COSINE Code Package, Xiaoyu Hu, Changhui
Wang, Guoping Quan, Su Wang, Yixue Chen
(State Nuclear Power Software Development
Center), Yongping Wang (Xi’an Jiaotong
University)
15270 Preliminary Analysis of Basic Reactor
Physics of the Dual Fluid Reactor Concept, Xiang
Wang (Technical University Munich), Marcus Seidl
(E.ON Kernkraft GmbH), Rafael Macian-Juan
(Technical University Munich)
15224 Improvement of APR+ Core Inlet Flow Distribution with a Partially Blocked LSSBP, Kihwan
Kim, Dong-Jin Euh, In-Cheol Chu, Hae-Seob
Choi, Tae-Soon Kwon (KAERI)
15178 Validation of APROS Code against
Experimental Data from a Lead-bismuth Eutectic
Thermal-hydraulic Loop, Ignas Mickus (KTH), Jari
Lappalainen (VTT Technical Research Centre of
Finland), Pavel Kudinov (KTH)
15337 Promising Fuel Cycle Options for R&D Results, Insights, and Future Directions, Roald A.
Wigeland (Idaho National Laboratory)
15117 Some Anomalies in the Fission Products Release from Microfuel at Deep Burnup, A.S. Ivanov,
A.A. Rusinkevich (NIC «Kurchatov Institute»)
15264 Performance Validation of Advanced
Safety Features of APR+, Tae-Soon Kwon,
Kyoung-Ho Kang, Dong-Jin Euh, Hung-Gil Chun
(KAERI)
15222 Pre-test Analyses for the Experimental
Sodium Loop KASOLA with ASTEC-Na and
Benchmarking with Other Codes, G. Bandini, S.
Ederli, C. Parisi (ENEA), P. Balestra (ENEA), M.
Haselbauer, S. Perez-Martin, W. Hering (KIT),
L.E. Herranz (CIEMAT), C. Berna, A. Escriva, J.L.
Munoz-Cobo (UPV)
15346 Tradeoffs in Fuel Cycle Performance for
Most Promising Options, T. Taiwo, T.K. Kim, B.
Feng, N. Stauff, E. Hoffman, F. Ganda (ANL), M.
Todosow, N. Brown, G. Raitses (BNL), J. Gehin,
J. Powers (ORNL), G. Youinou, H. Hiruta, R.
Wigeland (INL)
15311 Out-of-pile Study of Lanthanide Migration
in U-Zr Alloy Fuel, Yeon Soo Kim, T. Wiencek, E.
O’Hare, J. Fortner (Argonne National Laboratory), T.
Ogata (CRIEPI), B.O. Lee (KAERI)
15379 Experimental Measurements and CFD
Evaluation of Wall Heat Flux Partitioning during
Subcooled Flow Boiling of R-11 within Vertical Annulus, Y. Bouaichaoui (Birine Nuclear Research
Center; LTPMP/FGMGP/USTHB), R. Kibboua
(LTPMP/FGMGP/USTHB), A. Belkaid (Birine
Nuclear Research Center)
15429 Uncertainty and Sensitivity Analysis of
AP1000 LBLOCA Using SNAP/RELAP5-DAKOTA, Mian Xing (State Nuclear Power Reseach
Institute), Xiao Hu (State Nuclear Power Technology Research & Development Center), Fei Li,
Likai Fei, Linsen Li, Yaodong Chen (State Nuclear
Power Reseach Institute), Jianping Jing (Nuclear
and Radiation Safety Center)
15343 Systems Using Water-cooled Reactor
Technology to Achieve Fast Reactor Performance, F. Ganda (ANL), N.R. Brown (BNL), B.
Feng (ANL), H. Hiruta (INL), T.K. Kim (ANL), G.
Raitses (BNL), T.A. Taiwo (ANL), M. Todosow
(BNL), R. Wigeland, G.J. Youinou (INL), G. Zhang
(University of California, Berkeley)
15558 An Investigation into Interaction between the
Fission Product Silver and Silicon Carbide, Han Liu,
Xin Geng, Nadia Rohbeck, Mingwen Bai, Ping Xiao
(University of Manchester)
Room 8
8:00am
8:00am >> 10:00am
6.05-II Reactor Analysis
Room 14
Room 3
Room 1
Session Chairs: Martine BLAT, EDF R&D,
France; P.R. Vasudeva Rao, IGCAR, India
15478 Study of Space-energy Effects in Subcritical
Reactor within a Time-dependent Multi-group
1-Dimensional Diffusion Approach, G. Lehaut, J.-L.
15510 Control Room Habitability Assessment and
In-leakage Test for Korean NPP, Dong Soo Song,
Jong Beom Lee, Sang Jun Ha, Je Jeoong Seong
(KHNP (Korea Hydro Nuclear Power Ltd) Central
Research Institute)
15287 Development Status of the Reactor Core
Physics Analyses Code in COSINE Project,
Changhui Wang, Xiaoyu Hu, Guoping Quan,
Su Wang, Hui Yu, Zhanquan Liu, Yixue Chen
(SNPTC)
15523 Study of Wood’s Metal Freezing Characteristics in Order to be Used as Water Stopper
Material, Radu Secareanu, Ilie Prisecaru (University
«Politehnica» Bucharest)
15416 Evaluation of Relevant Information for Optimal Reflector Modeling through Data Assimilation Procedures, Jean-Philippe Argaud, Bertrand
Bouriquet, Thomas Clerc, Flora Lucet-Sanchez,
Angelique Poncot (EDF R&D)
Lecouey, N. Marie (LPC Caen, IN2P3/CNRS), P. Baeten (StudieCentrum voor Kernenergie-Centre d’Etude de l’Energie
Nucléaire), G. Ban (LPC Caen, IN2P3/CNRS), V. Bécares
(Centro de Investigationes Energeticas MedioAmbientales
y Tecnologicas), A. Billebaud, S. Chabod (Laboratoire de
Physique Subatomique et de Cosmologie, CNRS-IN2P3/
UJF/INPG), T. Chevret (LPC Caen, IN2P3/CNRS), X. Doligez
(Institut de Physique Nucléaire d’Orsay, CNRS-IN2P3/University), A. Kochetkov, A. Krasa (StudieCentrum voor Kernenergie-Centre d’Etude de l’Energie Nucléaire), F.-R. Lecolley
(LPC Caen, IN2P3/CNRS), F. Mellier (CEA), W. Uyttenhove
(StudieCentrum voor Kernenergie-Centre d’Etude de
l’Energie Nucléaire), D. Villamarin (Centro de Investigationes
Energeticas MedioAmbientales y Tecnologicas), G. Vittiglio, J.
Wagemans (StudieCentrum voor Kernenergie-Centre d’Etude
de l’Energie Nucléaire)
15492 Dynamics of Subcritical Reactor Driven by
Proton Linac, Anna Golovkina, Igor Kudinovich,
Dmitri Ovsyannikov, Yuri Svistunov (Saint-Petersburg State University)
15447 Measurement of Heat Transfer Effectiveness during Collision of a Leidenfrost Droplet with
a Heated Wall, Jun-Seok Park, Hyungdae Kim
(Kyung Hee University), Sung Won Bae, Kyung
Doo Kim (KAERI)
15303 Dynamic Characteristics of Liquid Film
Flow from Direct Vessel Injection of APR1400,
Han-Sol Kim (Handong Global University), JongRok Kim, Dong-Jin Euh (KAERI), Jae-Young Lee
(Handong Global University)
15316 Progress in Thorium Fuel Cycle Technology Devoted to Molten Salt Reactor System, Jan
Uhlir, Martin Marecek (Research Centre Rez),
Martin Straka, Lorant Szatmary (UJV Rez)
15320 Performance of Promising Thorium Fuel
Cycles, M. Todosow, N. Brown (Brookhaven
National Laboratory), F. Heidet, E. Hoffman, T.
Taiwo (Argonne National Laboratory), J. Powers,
J. Gehin (Oak Ridge National Laboratory), R.
Wigeland (Idaho National Laboratory)
15018 Analysis of the Transient Behavior of PWR
Cladding during the Cooling Phase in Simulated
LOCA Experiments, Hsingtzu Wu, Yutaka Udagawa,
Takafumi Narukawa, Tomoyuki Sugiyama, Masaki
Amaya (JAEA)
15262 Analysis of Onset of Oxidation During Hypothesized Severe Accidents of Korean Optimized
Power Reactor 1000, Yongjae Lee, Seongwon
Seo (Hanyang University), Hwan-Yeol Kim (Korea
Atomic Energy Research Institute), Sung Joong
Kim (Hanyang University)
TRACK 10.
Nuclear Energy and Climate
Change Mitigation
10.03 The Role of Nuclear Power in the
Future Mix: Technico-economical Aspects
Room 2
Session Chairs: Sama Bilbao y Leon, Virginia
Commonwealth University, USA
15342 Analysis of Reactor Capital Costs and
Correlated Sampling of Economic Inputs, F. Ganda,
T. K. Kim, T. Taiwo (ANL), R. Wigeland (INL)
15037 Update of the IEA/NEA Nuclear Technology
Roadmap: What is the Role for Nuclear Energy in
a 2 Degree Scenario, Henri Paillère (OECD/NEA),
Cecilia Tam, Uwe Remme (IEA)
15323 Nuclear in a Broader Energy Context Transition Issues and Results, Arantzazu Cuadra,
Vatsal Bhatt, Nicholas Brown, Michael Todosow
(Brookhaven National Laboratory)
15513 The Role of Nuclear Power in the European
Energy Mix, Bernard Bonin, Henri Safa (CEA,
Direction de l’Energie Nucléaire, Direction Scientifique), Axel Laureau, Elsa Merle-Lucotte (PHELMA/
Grenoble INP and LPSC/IN2P3/CNRS), Joachim
Miss, Danylo Matselyuk, Yann Richet (IRSN),
François-Marie Bréon (Laboratoire des Sciences du
Climat et de l’Environnement)
15521 Why Nuclear Energy is Essential to Reducing Anthropogenic Greenhouse-Gas Emission
Rates, Agustin Alonso (Politecnica de Madrid),
Barry W. Brook (University of Tasmania), Daniel
A. Meneley (University of Ontario Institute of
Technology), Jozef Misak (UJV-Rež), Tom Blees
(Science Council for Global Initiatives), Jan B. van
Erp (Illinois Commission on Atomic Energy, former)
>
WEDNESDAY, MAY 6 PERIOD 5
TECHNICAL SESSIONS
TRACK 1.
TRACK 2.
1.05 Continuous Improvement
2.06 Applications
Water-Cooled Reactor
Programs and Issues
3:10pm
3:30pm
3:50pm
4:10pm
TRACK 3.
TRACK 4.
Fast Neutron and Other
Innovative Reactors
3.05-II Sodium-cooled Fast Reactor - Neutronics and Fuel
Operation, Performance and
Reliability Management
TRACK 5.
Plant Safety Assessment
and Regulatory Issues
3.12 Fast Reactor - General
Room 4
4.04-II Equipment Testing and Maintenance
5.07 Reflood and Fuel Coolant Interaction
Room 10
Session Chairs: Carl Sink, Office of Nuclear
Energy, USA; Henri Paillère, NEA, France
Session Chair: Laurent Buiron, CEA, France
Session Chair: Didier De Bruyn, SCK•CEN,
Belgium
Session Chair: Moez Benfarah, EDF, France
Session Chair: Seong-Wan Hong, KAERI,
South Korea
15140 Coupled Analysis of Passive Safety Injection
and Containment Filtered Venting for Passive Decay Heat Removal, Sang Ho Kim, Jae Hyun Ham,
Soon Heung Chang, Yong Hoon Jeong (Korea
Advanced Institute of Science and Technology)
15163 Coupling of a HyS Decomposition Reactor
to a High Temperature Nuclear Reactor, Werner
Heinrich Kaiser, Martin van Eldik, Pieter Gerhardus Rousseau (North-West University)
15275 The ASTRID Core at the Midtime of the
Conceptual Design Phase (AVP2), Christophe
Venard, Thierry Beck, Alain Conti, David Gentet,
Pierre Lamagnere, Denis Lorenzo, Romain
Lavastre, Pierre Sciora, Annick Tosello (CEA),
Anne-Claire Scholer, Denis Verrier (AREVA-NP),
Damien Schmitt (EDF R&D)
15039 Preliminary Safety Review of the Generation -IV Nuclear Systems, D. Blanc, O. Baudrand,
V. Tiberi, M. Philippe, S. Pignet, H. Bonneville, K.
Tack, K. Herviou (IRSN)
15044 An Analysis of INCORE 3D Code Output’s
Sensitivity in Accordance with the Number of
Measured Thimbles in Kori Unit 1, Sang-il Ahn
(Korea Hydro and Nuclear Power Co.,Ltd.)
15042 Experimental Studies on Fuel Coolant Interactions - The Effect of Melt Temperature, Wang
ZeFeng, Lin Meng, Li YanKai (Shanghai Jiao
Tong University), Wu Zhaoguo (State Nuclear
Power Software Development Center)
15279 Numerical Study of Severe Accidents on
Containment Venting Conditions, Na Rae Lee,
Young Suk Bang, Tong Kyu Park, Doo Yong Lee
(FNC Technology Co., Ltd.), Yu Jung Choi, Sang
Won Lee, Hyeong Taek Kim (Korea Hydro and
Nuclear Power, Central Research Institute)
15078 Fuel-Handling and Re-Fuelling Concept of
the Canadian SCWR, A. Sartipi, M. Gaudet, M.
Yetisir, B. Benson (Canadian Nuclear Laboratories)
15265 Possible Prospects of High-Temperature Reactor Application for High-Viscosity Oil
Production and Refinery, A.V. Bespalov, N.G.
Kodochigov, L.E. Kuznetcov (JSC «Afrikantov
OKBM»)
15305 ASTRID Core Shielding – Design Studies
and Benchmark Analysis, Nicolas Chapoutier, Alix
Janet, Marie Charlotte Ricol, Anne Claire Scholer,
Denis Verrier (AREVA NP), Christophe Venard
(CEA DEN Cadarache)
15065 The European Project ESNII Plus, A.
Vasile, C. Wahide, C. Latge, N. Chauvin (CEA),
P. Baeten, M. Schyns (SCK CEN), M. Frogheri,
L. Mansani (ANSALDO), R. Stainsby (NNL), K.
Mikityuk (PSI), M. Forni (ENEA), Z. Hozer (MTA
EK)
15161 Continuous, On-Line Confirmation of
Feedwater Flow Accuracy for Improved Plant
Safety, Joanna M. Phillips, Ernest Hauser (Cameron - Caldon Ultrasonics Technology Center)
15193 Improvement of Molten Core-Concrete
Interaction Model of the Debris Spreading Analysis Module in the SAMPSON Code, Masataka
Hidaka, Tadashi Fujii, Takeshi Sakai (Hitachi-GE
Nuclear Energy, Ltd.)
15399 Possible In-vessel Corium Progression Way
in the Unit 1 of Fukushima Dai-ichi Nuclear Power
Plant Using a Phenomenological Analysis, Frederic
Payot (CEA), Jean-Marie Seiler (CEA)
15175 Passive IN-Core Cooling System Based on
Hybrid Heat Pipe and Control Rod for Advanced
Nuclear Power Plants, In Cheol Bang, Kyung Mo
Kim, In Guk Kim, Yeong Shin Jeong, Ji Hyun Kim
(Ulsan National Insitute of Science and Technology)
15369 Experience Feedback from Nuclear
Cogeneration, Camille Auriault (LGI Consulting),
Michael Fütterer (JRC Petten), Olivier Baudrand
(IRSN)
15074 Conceptual System Design of a Supercritical CO2 Cooled Micro Modular Reactor,
Seong Gu Kim, Seung Joon Baik, Jangsik Moon,
Hwanyeal Yu, Yong Hoon Jeong, Yonghee Kim,
Jeong Ik Lee (KAIST)
15206 Eddy Current Testing System for Bottom
Mounted Instrumentation Welds, Noriyasu
Kobayashi, Souichi Ueno, Naotaka Suganuma,
Tatsuya Oodake, Takeshi Maehara, Takashi
Kasuya, Hiroya Ichikawa (Toshiba Corporation)
15281 Fuel Coolant Interaction Studies in the
Frame of CEA Programs: Impact of Material
Effect and Hydrogen Production on Steam Explosion, Pascal Piluso, N. Cassiaut-Louis, P. Fouquart, V. Tyrpekl, T. Alpettaz (CEA), C. Gueneau,
S. Gossé, C. Brayer (CEA), A. Quaini (CEA)
15422 Some Consequences of Material Interactions
for In-Vessel Melt Retention, Florian Fichot, Laure
Carénini (IRSN)
15220 Review of Issues Relating to the Enhancement of Critical Heat Flux in Nuclear Reactors,
S.M.K. Hasan, M.A.Z. Chowdhury, M.A.R. Sarkar
(Bangladesh University of Engineering and
Technology)
15473 Application of the High-temperature
Gas-cooled Reactor to Produce Tritium for Fusion
Reactors, Hiroyuki Nakaya, Hideaki Matsuura,
Kazunari Katayama (Kyushu University), Minoru
Goto, Shigeaki Nakagawa (JAEA)
15462 Justification of Wear Resistance of Equipment at NPPs with Liquid-Metal Coolants, V.V.
Makarov, A.V. Afanasiev, V.V. Denisov, V.S Neevin
(OKB GIDROPRESS)
15514 AOA/CRUD Mitigation Techniques
Through Core Redesign, Koroush Shirvan (MIT)
15465 Integration of New Experiments into the
Reflood Map, W. Hering, Ch. Homann, J. Stuckert
(KIT)
15477 Integrated Conjugate Heat Transfer Analysis
Method for In-Vessel Retention with External Reactor Vessel Cooling, Jong Woon Park, Jae-Ho Bae,
Wook-Cheol Seol (Dongguk University)
15525 Parametric Study with the AREVA Fuel
Risk Assessment Tools Applied at a Generic
US PWR, Mike G. Pop, Larry Lamanna, John
Riddle, Brian Lockamon, Laura Owen, Al Hoornik
(AREVA Inc.)
15515 Results of FCI Tests under Reactor
Flooded Conditions in TROI, Seong-Wan Hong,
Young-Su Na, Seong-Ho Hong, Jinho Song
(Korea Atomic Energy Research Institute)
Session Chair: Jean-Philippe Frontigny,
AREVA, France
2:50pm
High Temperature Reactors
Room 16
Room 15
2:30pm
2:30pm >> 4:10pm
15181 Verification for the Representative Sampling
of ACP1000 NPP Gaseous Effluent: Test and
Analysis, Xin-Fang Dong, Hang Li (CIAE), Shihai
Ding, Yong Wang (CNPE)
15361 European Benchmark on the ASTRID-like
Low-void-effect Core Characterization: Neutronic
Parameters and Safety Coefficients, Sara Bortot
(PSI), Francisco Alvarez-Velarde (CIEMAT), Emil
Fridman (HZDR), Ignacio Garcia Cruzado, Nuria
Garcia Herranz (UPM), Francisco Martin-Fuertes
(CIEMAT), Konstantin Mikityuk, Anne-Laurene
Panadero, Sandro Pelloni (PSI), Alexander
Ponomarev (KIT), Pierre Sciora (CEA), Armin
Seubert (GRS), Haileyesus Tsige-Tamirat (JRC),
Alfredo Vasile (CEA)
15458 Mapping of Sodium Void Worth and Doppler Effect for Sodium-cooled Fast Reactor, Jiri
Krepel, Sandro Pelloni, Sara Bortot, Anne-Laurène Panadero, Konstantin Mikityuk (PSI)
15531 Power Profile Optimization of Sodiumcooled CANDLE Core by Using Thorium Fuel,
Ryosuke Miura, Naoyuki Takaki (Tokyo City
University)
Room 17
15547 Strategy for Mitigation Open Phase
Conditions (OPC) in the Electrical System, Waldemar Geissler, Wolfgang Schoenberger, Jimmy
Lorange (AREVA GmbH)
Room 6
5.08 In Vessel Retention
Room 7
Session Chairs: Jiří Žďárek, ÚJV Řež, a. s.,
Czech Republic; Jean-Pierre Van Dorsselaere,
IRSN, France
WEDNESDAY, MAY 6 PERIOD 5
TECHNICAL SESSIONS
TRACK 6.
Reactor Physics and Analysis
6.05-III Reactor Analysis
2:50pm
3:10pm
3:30pm
3:50pm
4:10pm
TRACK 7.
TRACK 8.
Thermal Hydraulics Analysis
and Testing
7.09 Two-Phase CFD
Fuel Cycle and
Waste Management
7.10-II Multiphase General
7.13-II Advanced Concepts
8.05 Waste Management Technologies
Room 3
TRACK 9.
Materials and Strucural
Issues
9.05 Mechanical Behavior
Room 1
TRACK 10.
Nuclear Energy and Climate
Change Mitigation
10.04 The Role of Nuclear Power in the
Future Mix: Synergy between Nuclear
Power and Renewables
TRACK 12.
Plant Licensing and
International Regulatory Issues
12.03 Reactor Applications
Room 9
Room 12
Room 14
Session Chair: Juan Luis François, National
Autonomous University of Mexico, Mexico
Session Chair: Christophe Calvin, CEA,
France
Session Chair: Kazuyuki Takase, Japan
Atomic Energy Agency, Japan
Session Chair: David Pialla, CEA, France
Session Chairs: Jan Uhlir, Research Centre
Rez, Czech Republic; Sou Watanabe, Japan
Atomic Energy Agency, Japan
Session Chair: Philippe Chapelot, CEA,
France
15097 Neutron and Gamma-ray Deep Penetration
Calculation through Concrete Shield for Wolsong
Unit 1 of CANDU Reactor, Sung Hyun Shin, Chang
Joo Hah, Chang Lak Kim (KINGS)
15004 Nitrogen Hold up Estimation in Mercury-nitrogen Loop by Enhanced Version of FLUENT
and Limited View Tomography Algorithm, Sanjeev
Kumar, Mayank Goswami, Prabhat Munshi (IIT
Kanpur)
15250 TRACE Assessments of Christensen Subcooled Boiling Experiments for Review of SPACE
Code Capabilities, Aeju Cheong, Andong Shin,
Young Seok Bang, Nam Duk Suh (Korea Institute
of Nuclear Safety)
15398 Evaluation of Self-controllability for a Loss
of Reactor Coolant Flow of SMART Plant, KyooHwan Bae, Young-Jong Chung, Hyung-Rae Kim,
Keong-Koo Kim (KAERI)
15241 Safety Operation of Chromatography
Column System with Discharging Hydrogen
Radiolytically Generated, Sou Watanabe, Yuichi
Sano, Kazunori Nomura, Yoshikazu Koma,
Yoshihiro Okamoto (JAEA)
15014 Measuring Sensors for Comprehensive
Vibration Assessment Program of The APR1400
Reactor Vessel Internals, Do-Young Ko, Eung-Se
Oh (Korea Hydro & Nuclear Power Co., Ltd. Central Research Institute)
15077 Refueling and Fuel Transportation using
a Barge for the Offshore Floating Nuclear Power
Plant, G. Srinivasan (CB&I), M. Golay, J. Buongiorno, N. Todreas (MIT)
15093 Qualification Program of the ASTRID SFR
Project: Definition, Methodology and Associated
Risk Evaluation & Management, Gilles Rodriguez
(CEA), Jean-Francois Dirat (AREVA-NP), Amael
Traina, Mickael Christofari (SONOVISION)
15234 Evaluation of SFR Deformed Core Reactivity,
M. Gentili, B. Fontaine, G. Rimpault (CEA)
15156 CFD Model for Simulation of Subcooled
Nucleate Flow Boiling and Coupling with STHCode for Analysis of IVR Coolability, M. Sonntag,
X. Cheng (KIT)
15498 Analysis of Capability of the Cobra-En
Code to Reproduce a Nine-Rod Bundle Mixing
Tests, Adolfo R. Hamers, Claubia Pereira, Maria
Auxiliadora Fortini Veloso (Universidade Federal
de Minas Gerais), Marcelo Veloso (Centro de
Desenvolvimento da Tecnologia Nuclear), Patricia
A. L. Reis (Universidade Federal de Minas
Gerais)
15410 Validation of Plant Dynamics Analysis
Code Using Shutdown Heat Removal Test-17
Performed at the EBR-II, Hiroaki Ohira, Norihiro
Doda, Hideki Kamide (JAEA), Takashi Iwasaki,
Masaki Minami (NESI Inc.)
15133 Improvement of Adsorption Properties of
Zeolites and Their Characterization, Hitoshi Mimura, Md. Shakilur Rahman (Tohoku University),
Isao Yamagishi (JAEA), Minoru Matsukura (Union
Showa), Ayako Kuroda Kuroda (Seibu Giken)
15088 Operability Assessment for the Components Having Unidentified S-PWHT Records in
an Operating Nuclear Power Plant, Kyoungsoo
Lee, Hongdeok Kim, Sangkyu Park, Jaegon
Lee (Central Research Institute/Korea Hydro &
Nuclear Power Co. Ltd.)
15115 Variable Electricity and Steam from Salt, Helium, and Sodium Cooled Base-Load Reactors with
Gas Turbines and Heat Storage, Charles Forsberg
(MIT), Pat McDaniel (University of New Mexico), B.
Zohuri (Galaxy Advanced Engineering)
15218 Application of Objective Provision Tree to
Development of Standard Review Plan for Sodiumcooled Fast Reactor Nuclear Design, Moo-Hoon
Bae, Namduk Suh (Korea Institute of Nuclear
Safety (KINS)), Bongsuk Kang, Huichang Yang
(TÜV Rheinland Korea Ltd.)
15472 Characteristic Analyses on the Coolant
Channel Blockage of a Pool-type Lead-bismuth
Cooled Small Modular Reactor Utilizing Natural
Circulation, Sangrok Park, Yong-Hoon Shin, Il
Soon Hwang (Seoul National University)
15244 The Assessment of Radionuclides
Migration and Diffusion Characteristics through
Groundwater for Decommissioning of Nuclear
Power Plant, Shih-Feng Wen (National Tsing Hua
University), Chih-Hung Lin (NTHU Center for
Energy and Evironmental Research), Yuh-Ming
Ferng (National Tsing Hua University)
15145 An Investigation of Major Influences on the
Seismic Response of APR1400 Reactor Vessel
Internals, Young Jin Byun, Jung Gyu Kim, Ki
Kwang Sung, Dae Hee Lee (KEPCO Engineering
& Construction)
15125 Variable Electricity from Base-load Nuclear
Power Plants Using Stored Heat, Charles Forsberg
(MIT), Erich Schneider (University of Texas at
Austin)
15508 European Passive Plant (EPP) Program
Support of AP1000® Plant Licensing in the UK, Kathryn J. Demetri, Julie Gorgemans (Westinghouse
Electric Company)
15551 Passive Decay-Heat Removal in the Fixed
Bed Nuclear Reactor (FBNR), Erika C. Solano D.,
Gloria Maribel Luna A., Roque A. Santos, David
E. Vaca C. (Escuela Politecnica Nacional)
15143 Integrated Methodologies for Tracers Use
in Radioactive Waste Management, Raffealla
Testoni (Politecnico di Torino), Riccardo Levizzari
(Italian National Agency for New Technologies,
Energy and Sustainable Economic Development,
Saluggia Research Centre), Mario De Salve
(Politecnico di Torino)
15184 High-Temperature CANDU Fuel Bundle
Behaviour Experiment: Preliminary Results, C..
Thiriet, R.S. Dickson, K.D. Colins (Atomic Energy
of Canada Limited)
15136 Integrated Nuclear-Renewable Energy
Systems: Regional Opportunities, Shannon M.
Bragg-Sitton, Richard Boardman (Idaho National
Laboratory), Mark Ruth, Owen Zinaman (National
Renewable Energy Laboratory), Charles Forsberg
(Massachusetts Institute of Technology)
15479 IAEA/INPRO Preliminary Study on
Legal and Institutional Issues for Transportable
Nuclear Power Plants, Vladimir Kuznetsov
(International Atomic Energy Agency), Zoran
Drace (Consultant)
15130 Treatment of TMSR-SF1 Radioactive
Liquid Waste, Shuai Wang, Qiang Qin, Hongjun
Ma, Liubin He, Yanbo Qiao, Zhenghua Qian,
Xueyang LIu, Hongyu Wang (Shanghai Institute
of Applied Physics)
15192 Development of RBWR (Resource-renewable BWR) for Recycling and Transmutation
of Transuranium Elements: (3) Vibration Analysis
of Fuel Assembly, Yuichi Koide, Shigeyuki
Koyama (Hitachi, Ltd.)
15555 Can Nuclear Power and Renewables Be
Friends?, D.T. Ingersoll, C. Colbert, Z. Houghton, R.
Snuggerud (NuScale Power), J.W. Gaston (Energy
Northwest), M. Empey (UAMPS)
Room 13
2:30pm
2:30pm >> 4:10pm
15257 Flexblue Core Design: Optimisation of Fuel
Poisoning for a Soluble Boron Free Core with Full
or Half Core Refuelling, Jean-Jacques Ingremeau
(DCNS), Maxence Cordiez (Chimie PARISTECH)
15195 Multi-dimensional Verification for the
Modification of Two-Fluid Momentum Equation on
Dispersed Flows, Seung-Jun Lee, Byoung Jae
Kim, Ik Kyu Park, Kyung Doo Kim, Han Young
Yoon (Korea Atomic Energy Research Institute)
15082 Feasibility Study of the Design of
Homogeneously Mixed Thorium-Uranium Oxide
and All-Uranium Fueled Reactor Cores for Civil
Nuclear Marine Propulsion, Syed Bahauddin Alam,
Benjamin A. Lindley, Geoffrey T. Parks (University
of Cambridge)
15425 CFD Results for Temperature Dependence
Water Cooling Pump NPSH Calculations, Mikhail
P. Strongin (Xylem Inc.)
15471 Recent Advances in Modeling and Validation of Nuclear Thermal-hydraulics Applications
with NEPTUNE_CFD, M. Guingo, C. Baudry,
M. Hassanaly, J. Lavieville, N. Mechitoua, N.
Merigoux, . Mimouni (EDF), D. Bestion, P. Coste,
C. Morel (CEA)
15504 Thermophysical Characterization of Al2O3
and ZrO2 Nanofluids as Emergency Cooling
Fluids of Future Generations of Nuclear Reactors,
Marcelo S. Rocha, Eduardo L.L. Cabral, Gaianê
Sabundjian, Helio Yoriyaz, Larissa Otubo, Delvonei A. Andrade, Ana Cecília S. Lima, Antônio
Belchior-Jr, Adelk C. Prado, Julian M.B. Shorto,
Tufic Madi-Filho, Benedito D. Baptista-Filho, Roberto N. Mesquita (Nuclear and Energy Research
Institute - IPEN/CNEN-SP), Gherhardt Ribatsky
(University of São Paulo - USP-SC)
15530 Application of Nuclear Reactor Safety
Analysis Code MARS for Fusion Blanket
Thermal-Hydraulic Analysis, Jeong-Hun Lee,
Geon-Woo Kim, Goon-Cherl Park, Hyoung-Kyu
Cho (Seoul National University), Kihak Im (National Fusion Research Institute), Hyoung-Kyu Cho
(Seoul National University)
Room 5
Room 2
Session Chair: Jose Reyes, NuScale Power,
USA
Session Chair: Françoise De Bois, AREVA,
France