Conference Agenda

Identification of Boiling Regime Based on Hydrodynamic Behavior and Heat Transfer Characteristics of Single Droplet-Heated Wall Collision

Ahyeong Cho, Hyungdae Kim

Kyung Hee University, Korea, Republic of

Modeling of Distribution Parameter and Drift Velocity for Microgravity Two-phase Flow

Xu Han^1,2, Aijie Li^1,2, Shixun He^1,2, Xiaobo Zeng^1,2, Di Wu^1,2, Jie Cheng^1,2, Jianjun Wang^1,2

1: College of Nuclear Science and Technology, Harbin Engineering University, China, People's Republic of; 2: Heilongjiang Provincial Key Laboratory of Nuclear Power System and Equipment, Harbin Engineering University, China, People's Republic of

Geometric Effects of Inverted U-bend on Two-phase Transport

Zhengting Quan, Alicja Stoppel, Seungjin Kim

Purdue University, United States of America

A Simulant of R134a-Ethanol Flow for Investigating Steam-water Annular Flow under High-pressure and High-temperature Conditions

Huacheng Zhang¹, Yutaro Umehara¹, Shoji Mori¹, Naoki Horiguchi², Hiroyuki Yoshida²

1: Kyushu University, Japan; 2: Japan Atomic Energy Agency, Japan

One-group Interfacial Area Transport in Vertical Two-phase Flow with Inverted U-bend

Zhengting Quan, Seungjin Kim

Purdue University, United States of America

Mechanistic Model of Heat Transfer Coefficient in AnnularTwo-Phase Flow

Roman W. Morse¹, Gustavo Aguiar¹, Kristofer M. Dressler², Jean-Marie Le Corre³, Evan T. Hurlburt⁴, Matteo Bucci¹

1: Massachusetts Institute of Technology, United States of America; 2: University of Wisconsin-Madison, United States of America; 3: Westinghouse Electric Sweden, Sweden; 4: Naval Nuclear Lab, United States of America

Visualization Analysis of Performance of Boiling Heat Transfer on Micro-cavity Surface According to Cavity Diameter

Do Yeon Kim¹, Seon Ho Choi³, Su Cheong Park², Dong In Yu¹

1: Pukyong National University, Korea, Republic of; 2: Dong-a University, Korea, Republic of; 3: Pohang Accelerator Laboratory, Korea, Republic of

Experimental Research of Wicking Degradation Effect on Boiling Heat Transfer Characteristics with Nanostructured Surface

Jian Zhou, Longchang Tang, Wei Xu, Xiaojing Liu

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

Visual Study of Subcooled Boiling based on Femtosecond Laser Modified Surface

Mingze Cao^1,2, XIao Yan¹, Dianchuan Xing¹, jianjun Xu¹, Yanlin Wang¹, Tianzhou Xie²

1: Nuclear Power Institute of China, China, People's Republic of; 2: State Key Laboratory of Advanced Nuclear Energy Technology, China, People's Republic of

Heat Transfer Enhancement for Nucleate Boiling via Microlayer Evaporation on Micro-pillar Arrayed Surface

Wei Ding¹, Jinming Zhang¹, Uwe Hampel^1,2

1: Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Germany; 2: Technische Universität Dresden, Germany

Hydrodynamic and Thermal Investigation of Oxide Layer Microscale Surface Features on Nucleate Boiling

Matthew Val Meyers¹, Patrick Lewis², Ryan Tunstall², Edward Smith³, Giovanni Giustini¹, Alex Skillen¹

1: University of Manchester, United Kingdom; 2: Rolls Royce, United Kingdom; 3: Brunel University, United Kingdom

Assessment of Correlations for Point of Net Vapor Generation using Direct Visual Observation

Taiyang Zhang¹, Joseph L. Bottini²

1: The Ohio State University, United States of America; 2: United States Military Academy, United States of America

Measurement of Interfacial Phenomena Near CHF in High Pressure Water Flows Using High-Speed X-Ray Radiography

Yang Liu, David Novog

McMaster University, Canada

Personal Experiences in the Two Kinds of Experiments to Confirm Reliability of Passive Systems for Nuclear Reactors

Hideo Nakamura

Japan Atomic Energy Agency, Japan

Numerical Investigation of Boiling Phenomena and Vibration Instabilities in Helical Cruciform Fuel for Water-cooled SMRs

Youyeon Choi, Koroush Shirvan

Massachusetts Institute of Technology, United States of America

Performance Evaluation and Validation of Load Following in the NuScale Concept Based URI-SMR Experimental Facility

Joo Hyung Seo, In Cheol Bang

UNIST, Korea, Republic of

Preliminary Assessment of Heat Transfer Performance in Helical CoilSteam Generators

Yu Jung Choi, Jaehwan Park, Kyoung-uk Lee

KHNP, Korea, Republic of

Predictability Evaluation of SPACE Code for the Condensation Model in the Nearly Horizontal Tube

Hae Min Park, Jong Hyuk Lee

KAERI, Korea, Republic of

Experimental Study and Optimized Design of Printed-circuit Heat Exchanger with Straight Channel from Laminar to Turbulent Conditions for Recuperators in Gas Brayton Cycles

Sungkun Chung¹, Gibbeum Lee², Jae Eun Cha², HangJin Jo¹

1: Pohang University of Science and Technology (POSTECH), Korea, Republic of; 2: Korea Atomic Energy Research Institute (KAERI), Korea, Republic of

Experimental Study and Modeling of Post-CHF Heat Transfer in Support of LWR Safety Analysis and Licensing Review

Xiaodong Sun¹, Kyung Mo Kim^1,2, Qingqing Liu^1,3, Stephen Bajorek⁴, Joseph Kelly⁴

1: University of Michigan, United States of America; 2: Korea Institute of Energy Technology (KENTCH), Korea, Republic of; 3: Mississippi State University, United States of America; 4: The U.S. Nuclear Regulatory Commission, United States of America

Comparative Analysis of RELAP5 and STARCCM+ Simulations for Microchannel Heat Exchangers: A Case Study of the E-SMR Primary Heat Exchanger

Andrea Missaglia^1,4, Giorgio Khalil Youssef², Marco Caramello³, Emilio Baglietto⁴, Fabio Giannetti², Stefano Lorenzi¹, Marco Ricotti¹

1: Politecnico di Milano, Italy; 2: Sapienza University of Rome, Italy; 3: Ansaldo Nucleare, Italy; 4: Massachusetts Institute of Technology, United States of America

Coupled Multi-physics Simulation of Full-core Operation of Soluble-boron-free SMRs Using Sub-channel CFD and SERPENT

Bryan Tan¹, Yu Duan¹, Michael J Bluck¹, Matthew D Eaton¹, Bo Liu²

1: Imperial College London, United Kingdom; 2: Science and Technology Facilities Council, Daresbury Laboratory, United Kingdom

Numerical Evaluation of Parameters Influencing Mixing Characteristics under Boron Dilution Transient in a Scaled PWR Downcomer and Lower Plenum

Lilia Djebara, Hongyang Wei, Sichao Tan, Ruifeng Tian

Harbin Engineering University, China, People's Republic of

Development of the Coupled Code TRACE/PARCS/TWOPORFLOW for SMR Safety Analysis

Alejandro Campos-Muñoz¹, Victor Hugo Sanchez-Espinoza¹, Kanglong Zhang¹, Cesar Queral²

1: Karlsruhe Institute of Technology, Germany; 2: Universidad Politecnica de Madrid, Spain

Efficient Prediction of Turbulent Cross Flow in Helical Coil Steam Generators of SMR via Deep Learning–Driven Reduced-Order Models

Bumjin Cho, Minseop Song

Hanyang University, Korea, Republic of

Utilizing Thermal Inertia of Bedrock as a Passive Heat Sink for Small Modular Reactor

Aleksandr Pomogaev, Juhani Hyvärinen, Giteshkumar Patel, Juhani Vihavainen

Lappeenranta-Lahti University of Technology LUT, Finland

Spacer Grid Rewet during Reflood andModeling Challenges for Thermal-Hydraulic Codes

Stephen M. Bajorek¹, Yue Jin², Fan-Bill Cheung³

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

Bal-Raj Sehgal Memorial Award Lecture: Interface Capturing Simulations for Nuclear Thermal Hydraulics

Igor Bolotnov

North Carolina State University, United States of America

FONESYS Benchmark of Core Interfacial Friction Models in System Codes

Dominique Bestion¹, Francesco D'Auria², Qingling Cai², Jaeseok Heo³, Philipp Schoeffel⁴, Hongsheng Yuan⁵, Amandine Capogna⁶, Sofia Carnevali⁶

1: Consultant, France; 2: UNIPI, Italy; 3: KAERI, Korea, Republic of; 4: GRS, Germany; 5: CNPRI, China, People's Republic of; 6: CEA, France

Giving a Major Role to Bifurcating Events in Pirt and Scaling Analysis for Light Water Reactor Thermalhydraulics

Dominique Bestion¹, Sofia Carnevali², Francesco D'Auria³

1: Consultant, France; 2: CEA, France; 3: UNIPI, Italy

Current and Planned Activities of the FONESYS Network of System Code Developers in Collaboration with the SILENCE Network of Experimentalists

Dominique Bestion¹, Francesco D'Auria², Klaus Umminger³, Jaeseok Heo⁴, Philipp Schoeffel⁵, Sofia Carnevali⁶, Jean Luc Vacher⁷, Pierre Gaillard⁸, Huie Sha⁹, Hongsheng Yuan¹⁰, Geoffrey Waddington¹¹, Jean Marie LeCorre¹²

1: Consultant, France; 2: University of Pisa, Italy; 3: Consultant, Germany; 4: KAERI, Korea, Republic of; 5: GRS, Germany; 6: CEA, France; 7: EDF, France; 8: Framatome, France; 9: SPICRI, China, People's Republic of; 10: CNPRI, China, People's Republic of; 11: CNL, Canada; 12: Westinghouse, Sweden

FONESYS Benchmark of Core-3D-Mixing in System Codes

Dominique Bestion¹, Jaeseok Heo², Huie Sha³, Philipp Schoeffel⁴, Adrien Rodriguez⁵, Hongsheng Yuan⁶, Vincenzo Zingales⁷, Raphael Prea⁵, Lin Wang³, Francesco D'Auria⁷

1: Consultant, Grance; 2: KAERI, Korea, Republic of; 3: SPICRI, China, People's Republic of; 4: GRS, Gernany; 5: CEA, France; 6: CNPRI, China, People's Republic of; 7: UNIPI, Italy

Fonesys Benchmark of Singular Pressure Losses in System Codes

Dominique Bestion¹, Philipp Schoeffel², Nicolas Piette³, Jean Luc Vacher⁴, Jae Jun Jeong⁵, Qingling Cai⁶, Vincenzo Zingales⁶, Jaeseok Heo⁷, Francesco D'Auria⁶

1: Consultant, France; 2: GRS, Germany; 3: CEA, France; 4: EDF, France; 5: Pusan National University, Korea, Republic of; 6: UNIPI-GRNSPG, Italy; 7: KAERI, Korea, Republic of

Using System Code for Scaling Analysis: A New Integrated Tool in the CATHARE Code Applied to a SB-LOCA Transient

Valentin Cottarel¹, Sofia Carnevali¹, Marco Montanini¹, Dominique Bestion²

1: French Alternative Energies and Atomic Energy Commission (CEA), France; 2: Scientific Consultant, France

The CATHARE Code Validation on CRIEPI Core Void Fraction Data

Amandine Capogna¹, Jean-Luc Vacher², Thibaut Lopez¹, Dominique Bestion³

1: CEA, France; 2: EDF, France; 3: Consultant, France

BEEs: A Multiphysics Simulation Engine for Advanced Nuclear Fuel Innovation

Guanghui Su

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

Application of the Repas Methodology to Analyze the Reliability of the EHRS in the Decay Heat Removal Strategy for an SMR

Erik Cilia¹, Gianmarco Grippo¹, Lorenzo Tempesta¹, Marcello Savini¹, Fulvio Mascari²

1: University of Bologna, Italy; 2: ENEA Bologna Research Center, Italy

Experimental Characterization of Upper Plenum Natural Circulation Phenomena Under Steady State Transient Accident Conditions

Tristen Jeda Rogers, Yassin Hassan, Ryan Sanchez

Texas A and M University, United States of America

Characterization of Coupling Interactions between Passive Safety Systems in Deep Pool Heating Reactors

Feng Shou^1,2, Zhang Yankun^1,2, Zhu Di^1,2, Sun Rulei^1,2, Gao Puzhen^1,2, Tian Ruifeng^1,2, Tan Sichao^1,2

1: State Key Laboratory of Marine Thermal Energy and Power, Harbin Engineering University, China, People's Republic of; 2: School of Nuclear Science and Technology, Harbin Engineering University, China, People's Republic of

Novel Heat Transfer Models to Improve the Performance Prediction of Passive Residual Heat Transfer Systems

Tahmineh Adili, Yu Zhang, Iurii Dolganov, Stephan Leyer

University of Luxembourg, Luxembourg

Numerical Analysis of Natural Circulation and Heat Transfer Dynamics in a Horizontal Reactor Assembly Cooled by Helium-Xenon Mixture

Tianshi Wang¹, Jinyu Wang², Zhongchun Li², Dongchuan Su², Xiang Chai¹, Xiaojing Liu¹

1: Shanghai Jiao Tong University, China, People's Republic of; 2: Nuclear Power Institute of China, China, People's Republic of

Towards New Experiments for Natural Convection at High Rayleigh Numbers: Definition, Sizing and Analysis Using CFD

Antoine Morente¹, Juan Uribe¹, Sofiane Benhamadouche¹, Pauline Rotach¹, Michael Montout¹, Jean-Luc Vacher², Myeong-Seon Chae³, Domenico Paladino³

1: EDF R&D, France; 2: DISC - Direction Technique, EDF, France; 3: Paul Scherrer Institut (PSI), Switzerland

Natural Convection Heat Transfer Around the Dome with Various Truncation Angles at High Rayleigh Numbers

Suyeon Park, Donghyuk Park, Bumjin Chung

KyungHee University, Korea, Republic of

Surrogate Modelling of Perturbed Natural Circulation in a Simple Test Loop

Patrick Martin Lewis, Heather Davies, Sophie Brown

Rolls Royce, United Kingdom

Flow Visualization of Local Heating Effects in a Molten Salt Natural Circulation Loop

Thomas Scott Carson, Joseph Seo, Hansol Kim, Yassin Hassan

Texas A&M University, United States of America

Design of a Two-Phase Molten Salt Natural Circulation Loop Based on Scaling Laws and Preliminary Analysis Using OpenFOAM

Won Jun Choi, Jae Hyung Park, Sinho Kim, JinHo Song, Sung Joong Kim

Hanyang University, Korea, Republic of

Steady-State Behaviour of Two-Phase Natural Circulation Systems

Latika Dixit, Vijayan P.K., Satya Sekhar Bhogilla

Indian Institute of Technology Jammu, India

Validation of Thermal Hydraulic Tool for Modeling the Natural Convection of a Molten Salt Flow Loop

Andres Nicolas Fierro Lopez^1,2, Guillaume Giudicelli², Mauricio Tano Retamales², Ethan Rozak¹, Cole Gentry¹, Kevin Clarno¹

1: The University of Texas at Austin, United States of America; 2: Idaho National Laboratory, United States of America

Integrated Multiphysics Framework with Species Transport to Support Advanced Molten Salt Reactor Technologies in Pronghorn

Mauricio Tano, Samuel Walker, Piyush Sabharwall, Ramiro Freile, Rodrigo de Oliveira, David Reger

Idaho National Laboratory, United States of America

High-Fidelity Modelling of the Molten Salt Fast Reactor

Maximiliano Dalinger, Elia Merzari, Saya Lee, Casey Emler

Pennsylvania State University, United States of America

Flow Distribution in a Molten Salt Reactor and its Dependency on Support Grid Designs

Levi Schilter¹, Mark Kimber¹, Jack Crooks², Thomas Provencher², Peter Pizzato²

1: Texas A&M University, United States of America; 2: Zachry Nuclear, Inc., United States of America

CFD-Based Investigation of Flow and Heat Transfer Characteristics of Molten Salt with Internal Heat Source

Hui Deng^1,2, Shanwu Wang¹, Chong Zhou¹, Siqin Hu¹, Shuaiyu Xue¹, Pinyan Huang^1,2, Hongxiang Yu^1,2

1: Shanghai Institute of Applied Physics, Chinese Academy of Sciences Shanghai, China, People's Republic of; 2: University of Chinese Academy of Sciences, China, People's Republic of

Impact of Neutronics-thermal-hydraulics Coupling on the Wall Temperature Fluctuations in Liquid Fuel Reactors

Max Begue¹, Axel Laureau¹, Elsa Merle¹, Julien Vukasin²

1: CNRS / LPSC, France; 2: Orano DRD, France