Conference Agenda

An Overview of Ongoing and Planned R&D Activities in the Field of Experimental Two-phase Thermal-hydraulics at CEA IRESNE

Jimmy Martin, Philippe Aubert, Stéphane Bantiche, Manon Bottin, Jérôme Brinster, Florence Bruna, Julien Carré, Sidonie Clément, Christine Coquelet-Pascal, Jean-Philippe Descamps, Fabrice François, Sébastien François, David Guénadou, Anthony Laurent, Matthieu Manzoni, Bastien Menc, Damien Moulin, Rémy Savoyet, Ludovic Sou, Mathilde Talluau, Eric Verloo

French Alternative Energies and Atomic Energy Commission (CEA), France

Experiment Investigation of Condensation Effect on an Integral Facility

Zijiang Yang, Di Liu, Zhanfei Qi, Kemei Cao

Shanghai Nuclear Engineering and Design Corporation, China, People's Republic of

Validation on Condensation Heat Transfer Models of SPACE and MARS-KS based on Condensation Experiment Facility for Small Modular Reactor Passive Safety System

Hyo Jun An¹, Jae Hyung Park¹, Taeseok Kim², Geunyoung Byeon¹, Yujin Kim¹, JinHo Song¹, Sung Joong Kim^1,3

1: Department of Nuclear Engineering, Hanyang University, Korea, Republic of; 2: Jeju National University, Korea, Republic of; 3: Institute of Nano Science and Technology, Hanyang University, Korea, Republic of

Erosion of a Stratified Containment Atmosphere by a Vertical Jet after Interacting with a Horizontal Disk

Domenico Paladino¹, Ralf Kapulla¹, Guillaume Mignot², Sidharth Paranjape³, Simon Suter¹, Myeong-Seon Chae¹, Yago Rivera¹, Nabil Ghendour¹, Christiph Hug¹

1: Paul Scherrer Institut, Switzerland; 2: Oregon State University, United States of America; 3: OST – Ostschweizer Fachhochschule, Switzerland

Experimental Study on Flow-induced Vibration of Plate-type Fuel Assembly

Shuai Liu, Bing Ren, Jie Ding, Jie Zhang, Jingya Sun, Yu Dang, Fujun Gan, Heting Sun, Chaozhu Zhang

Shanghai Nuclear Engineering Research and Design Institute Co.Ltd., China, People's Republic of

Uncertainty Quantification of Calculated Fuel Temperature for the AGR-5/6/7 Irradiation Experiment

Cam Binh Pham, Grant Hawkes, Nancy Lybeck, Courtney Otani, Paul Demkowicz

Idaho National Labaratory, United States of America

Experimental Study of Two-phase Flow in a Four-by-four Unheated Rod Bundle for Validation of Thermal-hydraulics Simulation Codes

Muhammad Ilham, Taku Nagatake, Shinichiro Uesawa, Ayako Ono

Japan Atomic Energy Agency, Japan

Assessment of Spacer Grid Effects and Flow Development in a Triangular Rod Bundle: A PIV-DNS Cross-Comparison

Danila Trane¹, Mattia Grespan¹, Enrico Stalio², Diego Angeli¹

1: Department of Sciences and Methods for Engineering, University of Modena and Reggio Emilia, Italy; 2: Department of Engineering Enzo Ferrari, University of Modena and Reggio Emilia, Italy

Evaluation on Two Different Mixing Vanes by PIV Experiment in 5x5 Rod Bundle

Junya Inoue¹, Yoshitaka Mizutani¹, Yasushi Hirai¹, Tatsuya Sasakawa¹, Shigeo Hosokawa²

1: Nuclear Fuel Industries, Ltd., Japan; 2: Kansai University, Japan

Three-dimensional Turbulent Flow Measurements in a 6 × 6 Fuel Rod Bundle

Anis Rezaiguia², Roberto Capanna¹, Charles Fort¹, Emmanuel Lo Pinto², Guillaume Ricciardi², Philippe Bardet¹

1: George Washington University, United States of America; 2: CEA, DES, IRESNE, Nuclear Technology Departement, France

Three-dimensional Void fraction Distribution of Transient Boiling Two-phase Flow in a Heated 5×5 Rod Bundle During Depressurization Process

Shota Ueda¹, Takahiro Arai¹, Masahiro Furuya¹, Riichiro Okawa¹, Atsushi Ui¹, Wataru Sakuma²

1: Central Research Institute of Electric Power Industry, Japan; 2: Mitsubishi Heavy Industries, Ltd., Japan

Investigation of the Post-CHF Heat Transfer Modeling based on the Large Scale RBHT Reflood Data Compilation and Assessment

Yue Jin¹, Andrew Ireland², Stephen Bajorek², Kirk Tien², Chris Hoxie², Fab-Bill Cheung³

1: University of Missouri, United States of America; 2: U.S. Nuclear Regulatory Commission, United States of America; 3: The Pennsylvania State University, United States of America

Two-phase Critical Flow Experiments at LUT University

Lauri Pyy, Juhani Hyvärinen, Markku Puustinen, Giteshkumar Patel

LUT University, Finland

Integral Effect Test and SPACE-CAP Code Calculation for the Transient in the RCS and Containment during Small Break LOCA

Byoung-Uhn Bae, Jae Bong Lee, Yusun Park, Seok Cho, Jun-Yeong Jung, Kyoung-Ho Kang

Korea Atomic Energy Research Institute, Korea, Republic of

Natural Circulation Interruption Phenomena during Asymmetric Cooldown Operation in ATALS Test Facility

Seok Cho, Byoung-Uhn Bae, Yu-Sun Park, Jae-Bong Lee, Jong-Rok Kim, Kyoung-Ho Kang

Korea Atomic Energy Research Institute, Korea, Republic of

System Behavior Analysis of PATRIOT at SBO Scenario: A Scaled-Down IET Facility Using R134a Refrigerant

Ik Jae Jin¹, Do Yeong Lim², In Cheol Bang¹

1: Ulsan National Institute of Science and Technology (UNIST), Korea, Republic of; 2: Texas A&M University, United States of America

Performance of SMART100 Passive Safety System Validated in Thermal-Hydraulic Integrated Effect Test Using SMART-ITL

Hwang Bae, Jin-Hwa Yang, Byong Guk Jeon, Sung Uk Ryu, Hyun-sik Park, Sung-Jae Yi, Yoon Gon Bang

KAERI, Korea, Republic of

Transient Rod Temperature Distributions on a Rod Bundle Near Critical Heat Flux Measured by Optical Fiber Sensors

Takahiro Arai, Riichiro Okawa, Atsushi Ui, Masahiro Furuya, Tsugumasa Iiyama, Shota Ueda, Kenetsu Shirakawa

Central Research Institute of Electric Power Industry, Japan

Development of Turbulent Mixing Parameter for Subchannel Analysis in Hexagonal Rod Bundles

Kannan Iyer, Roopesh Wadhera

Indian Institute of Technology Jammu, India

Void Fraction Measurement on Flow Boiling in 7x7 Rod Bundle based on the WMS with Rod Electrodes

Hao Xie, Jinbiao Xiong

Shanghai Jiao Tong University, China, People's Republic of

Measurement and Analysis of Interfacial Parameters in Two-Phase Flow in a 5×5 Rod Bundle Channel

Shouxu Qiao, Quanbo Li, Jiaxing Ren, Fangdong Wang, Hongyang Wei, Puzhen Gao, Ruifeng Tian, Sichao Tan

Harbin Engineering University, China, People's Republic of

Effect of Pulsating Flow on Evolution of the Velocity Boundary Layer in a 5×5 Rod Bundle Channel

Shouxu Qiao, Xin Li, Songsheng Gao, Shuangcheng Li, Xiaoyong Yu, Ruifeng Tian, Sichao Tan

Harbin Engineering University, China, People's Republic of

Subcooled Flow Boiling Characteristics in a Hexagonal Fuel Sub-assembly with Plate Type Spacers Operating at Low Pressure Conditions

Ayush Kumar Rao, Harish Pothukuchi

Indian Institute of Technology Jammu, India

Further Verification of the High-precision Subchannel Program ATHAS-H

Kui Gao, Yixiang Zou, Jianqiang Shan

Xi'an Jiaotong University, China, People's Republic of

The Estimation of Uncertainty based on Various Fuel Burn-Up Condition in Loss of Coolant Accident Using SUPER Code

Seung-Chan Lee

Korea Hydro & Nuclear Power Co. Central Research Institute, Korea, Republic of

NCGDENSE Program: Advancing the Understanding of Non-Condensable Gases in Nuclear Reactor Coolant Systems

Sharandeet Singh, Giteshkumar Patel, Lauri Pyy, Juhani Hyvärinen

LUT University, Finland

BWR-6 LOCA Modeling with TRACE

Konstantin Nikitin, Ivor Clifford, Hakim Ferroukhi

PSI, Switzerland

Evaluation of the Effect of Flow Channel Deformation with Ballooning of Multiple Fuel Rods in Bundle during LBLOCA

Yunseok Lee, Taewan Kim

Incheon National University, Korea, Republic of

Optical Kerr Effect Gated Ultrafast Imaging of Bubbly Flows

Daniel Andrew Hunter, Philippe Matthieu Bardet

The George Washington University, United States of America

A Characterization of the Two-phase Frictional Pressure Drop within a Cylindrical Mini-channel in the Laminar and Turbulent Regimes

Jimmy Martin, Romuald Mallet, Yann Kervegant, Sylvain Chareyre

French Alternative Energies and Atomic Energy Commission (CEA), France

High-Resolution Miniaturized Impedance Sensor for Two-Phase Flow Measurement

Sergio Chiva, Oscar Prades, Guillem Monros, Salvador Torro, Raul Martinez, Jaume Luis

Universitat Jaume I, Spain

Measurement of Aerosol Temperature Field based on Background Oriented Schlieren

Bifan Liu, Danling Zhuang, Qian Wang, Junlian Yin

Shanghai Jiao Tong University, China, People's Republic of

Validation of CATHARE Code Against PERICLES High Pressure Reflooding Experiments

Nicolas Piette, Raphaël Préa, Lopez Thibaut

CEA, France

Experimental Investigation on the Uncertainty of Three-sensor Conductivity Probe for Droplet Measurement

Kang Li^1,2, Wenxiong Zhou^1,2, Xubin Tan^1,2, Runzhi Huang^1,2, Mingyue He^1,2, Kexin Qu^1,2, Qiang Lian^1,2, Wan Sun^1,2, Liangming Pan^1,2

1: Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, China, People's Republic of; 2: Department of Nuclear Engineering and Technology, Chongqing University, China, People's Republic of

Preliminary Investigation of a Fiber Optic Technique for Flow Rate Measurement in Horizontal Air-Water Stratified Flow

Hanna Kim¹, Hyewon Lim², Hyungmo Kim¹

1: Mechanical Engineering, Gyeongsang National University, Korea, Republic of; 2: Graduate School of Mechanical and Aerospace Engineering, Gyeongsang National University, Korea, Republic of

Infrared Thermometry Investigation of Flow Boiling Transient Critical Heat Flux under Exponentially Escalating Heat Input on Surfaces with Different Finish and Wettability

Yang Liu, Sebastian Rodriguez Rosero, Florian Chavagnat, Matteo Bucci

Massachusetts Institute of Technology, United States of America

Borescopic Molecular Tagging Velocimetry in PWR Surrogate Bundle

Roberto Capanna¹, Charles Fort¹, Guillaume Ricciardi², Philippe Bardet¹

1: The George Washington University, United States of America; 2: CEA, DES, IRESNE, Nuclear Technology Departement, France

CFD-Grade Measurements of Flow-Debris Interaction and PWR Filter Clogging Behavior using MRI Scanner

Vincent Klempau¹, Markus Rehm², Kristine John¹, Elmar Rieder², Sven Grundmann¹, Martin Bruschewski¹

1: University of Rostock, Germany; 2: Framatome GmbH, Germany

Challenges and Non-Conservatism in Indirect Simulation Heaters for Thermal-Hydraulic Experiments

Bao-Wen Yang¹, Jeremy Silber¹, Eric Yang², Stephanie H. Yang¹, Ray Smith², Yash Yadav², Bin Han³

1: Delta Energy Group New York (DEGNY/GDES), United States of America; 2: CARP Associates USA, LLC, United States of America; 3: Southeast University, China, People's Republic of

Experimental Design and Algorithm Validation of Reactor Chemical and Volume Control System Upper Charging Line Valve Leakage Faults

Jiajun Li, Hengyuan Wei, Dongyang Li, Sichao Tan, Ruifeng Tian

Harbin Engineering University, China, People's Republic of

Basic Design of PCCS Heat Exchanger of Integral Effect Test Facility for i-SMR Validation Test

Jin-Hwa Yang, Byoung-Uhn Bae, Hwang Bae, Kyoung-Ho Kang

Korea Atomic Energy Research Institute, Korea, Republic of

The Improvement and Preliminary Validation of Relap5 Code for Integrated Natural Circulation SMR

Zhanfei QI, Xiumei Zhao, Zijiang Yang, Shengzhe Li, Yue Wu

SNERDI, China, People's Republic of

Integrated Thermo-Mechanics and Thermal-Hydraulics of Zircaloy-4 Cladding Behavior under LBLOCA Conditions Using the ICARUS Facility

Rahmatika Intan Ali^1,2, Jongrok Kim¹, Kihwan Kim¹, Sang-Ki Moon¹, Seok Kim¹, Jae Bong Lee^1,2

1: Korea Atomic Energy Research Institute, Korea, Republic of; 2: KAERI School, University of Science and Technology, Korea, Republic of

A Scaled-Down Approach for Designing a Compact Hydraulic Apparatus for Nuclear Experimental Liquid fuel reactors (CHANEL)

Hyeon Ji Kim, In Cheol Bang

Ulsan National Institute of Science and Technology, Korea, Republic of

Experimental Investigations of Natural Convection in a Differentially-Heated Cavity

Noah LeFrancois, Robert Bowden

Canadian Nuclear Laboratories, Canada

Experimental Study on Mixed-Convection Wall Friction in Vertical Annular Channels under Natural Circulation Flow

Youngchang Ko, Seongbae Park, Sang Gyun Nam, Jae Jun Jeong, Byongjo Yun

Pusan National University, Korea, Republic of

Scaling Criteria for Wall Boundary Conditions of Free Convective Thin Plates with Volumetric Heat Generation

Moon Won Song, Seong Min Kim

Jeonbuk National University, Korea, Republic of

Natural Convection by Flow Boiling in Inclined Channel

Byeonghee Lee, Seok-Gyu Jeong, Junyoung Kang

Korea Atomic Energy Research Institute, Korea, Republic of

Investigation of Cooling Channel Height Control on Two – Phase Flow Behavior in Natural Circulation Systems

Zumaro Zumaro¹, Ceyda Eldem¹, HangJin Jo^1,2

1: Division of Advanced Nuclear Engineering, POSTECH, Korea, Republic of; 2: Department of Mechanical Engineering, POSTECH, Korea, Republic of

Heat Transfer Correlations for Upward Flow Over Curved Surfaces: Forced and Mixed Convection Regimes

Sameer Osman^1,2, Imran Afgan^1,2, Yacine Addad^1,2

1: Khalifa University of Science and Technology, United Arab Emirate; 2: Emirates Nuclear Technology Center (ENTC), United Arab Emirates

Experimental investigation of Upward Flow Boiling in a Narrow Annular Channel

Noor Ahmed, Taiyang Zhang, Caleb S. Brooks

University of Illinois Urbana Champaign, United States of America

Experimental Study of Single-phase Flow and Heat Transfer Characteristics of Narrow Rectangular Channels with Non-uniform Heating

Di Zhu, Shixuan Wang, Shou Feng, Rulei Sun, Sichao Tan, Ruifeng Tian

Harbin Engineering University, China, People's Republic of

Numerical Simulation of Flow Boiling in Narrow Rectangular Channels with a Flow Regime transition Model

Qianqian Ma, Guangliang Chen, Xiang Zhang

Harbin Engineering University, China, People's Republic of

Analytical Approach for Flow Reversal in Narrow Rectangular Channels

Basar Ozar, Jeremy Licht

Argonne National Laboratory, United States of America

Numerical Analysis of the Thermal and Hydraulic Characteristics of Mini Channels Incorporating Inter-Connection Mixing Zones

Armanto Pardamean Simanjuntak, Taemin Ahn, Joohan Bae, Jaeyoung Lee

Handong Global University, Korea, Republic of

Thermal Hydraulic Analysis of PKL Facility During Multi-Steam Generator Tube Rupture (MSGTR)

Omar S. Al-Yahia, Ivor Clifford, Hakim Ferroukhi

Paul Scherrer Institut, Switzerland

Experimental Study of Thermal Radiation in a Large PANDA Vessel with Steam Content Variation

Yago Rivera¹, Ralf Kapulla¹, Nabil Ghendour¹, Domenico Paladino¹, Sidhart Paranjape², Myeong-seon Chae¹, Simon Suter¹, Christopher Hug¹

1: Paul Scherrer Institute, Switzerland; 2: Eastern Switzerland University of Applied Sciences, Switzerland

Experimental Study for Multidimensional ECC Behaviors in Downcomer Annulus with Direct Vessel Injection Mode during the LBLOCA Reflood Phase

Xin Ma^1,2, Jie Wan^1,2, Wan Sun^1,2, Zaiyong Ma^1,2, Luteng Zhang^1,2, longxiang Zhu^1,2, Qiang Lian^1,2, Simiao Tang^1,2, Liangming Pan^1,2

1: Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, China, People's Republic of; 2: Department of Nuclear Engineering and Technology, Chongqing University, China, People's Republic of

Study on the Response of the Internal Structure of In-vessel Pressurizer under Ocean Conditions

Xue He^1,2, Zixuan Quan^1,2, Haoyu Ruan^1,2, Dongyang Li^1,2, Sichao Tan^1,2, Ruifeng Tian^1,2

1: Heilongjiang Provincial Key Laboratory of Nuclear Power Plant Performance and Equipment, Harbin Engineering University, China, People's Republic of; 2: Key Laboratory of Advanced Nuclear Energy Technology of Ministry of Industry and Information Technology, Harbin Engineering University, China, People's Republic of

Experimental and Numerical Investigations of Thermal Radiation Effects in the Medium-Scale LINX Facility

Nabil Ghendour, Abdelouahab Dehbi, Ralf Kapulla, Domenico Paladino, Yago Rivera Durán, Wilhelm-Martin Bissels, Myeongseon Chae, Simon Manuel Suter, Christoph Hug

Paul Scherrer Institute (PSI), Switzerland

Two-phase Flow Structure in a Header and Feeder Pipe System under Simulated Large Break Loss-of-coolant Accidents

Zhuoran Dang, Lan-Qin Yuan, Jun Yang, Liqian Li

Canadian Nuclear Laboratories, Canada

Design and Analysis of a Gas Sparging Mass Transfer Experiment for Tritium Removal in Molten Salt Reactor Applications

Andrew S Hutsell, Ryan P Mcguire, Ethan M Villareal, Jeremy I Lopez, Lane B Carasik

Virginia Commonwealth University, United States of America

Downscaling of a Prototypical Reactor Cavity Cooling System for a Molten Salt gFHR for Laboratory-scale Experimentation

Minghui Chen, Khaled Talaat

The University of New Mexico, United States of America

Loss-of-Forced-Circulation Experiments in a Reduced-Scale Integral Effects Test Facility to Verify Inherent Safety of the Kairos Power Fluoride Salt Cooled High Temperature Reactor

Griffen Latimer, Seth Cadell, Craig Gerardi, Lambert Fick, Jadyn Reis, Ka-Yen Yau

Kairos Power, United States of America

Integral Effect Tests and System Thermal Hydraulics Code Analyses on the Decay Heat Removal Systems of the STELLA 2 Facility

Yong-Hoon Shin, Seungjoon Baik, Yong Bum Lee, Jung Yoon, Hyeonil Kim, Jewhan Lee

Korea Atomic Energy Research Institute, Korea, Republic of