Conference Agenda

Modeling of the Molten Salt Fast Reactor Transient Behavior based on the Modified Point Reactor Kinetics Model

Thanh Hung Nguyen, Yitung Chen

University of Nevada, United States of America

Development for Integrated System-Level Analysis Capabilities in SAM for Molten Salt Reactors

Rui Hu¹, Travis Mui¹, Robert Salko², Tingzhou Fei¹, Daniel O’Grady¹, Ling Zou¹, Huihua Yang³, Wei Ji³

1: Argonne National Laboratory, United States of America; 2: Oak Ridge National Laboratory, United States of America; 3: Rensselaer Polytechnic Institute, United States of America

Experimental Methodology for Forced Convection Heat Transfer in Molten Salt with Volume Internal Heat Source

Shanwu Wang¹, Hui Deng¹, Pinyan Huang¹, Hongxiang Yu¹, Ying Cao², Chong Zhou¹, Yang Zou¹

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

Influence of an Internal Heat Source on Turbulent Wall cooling Heat Transfer in a Circular Pipe

Dong-Hyuk Park, Bum-Jin Chung

KyungHee University, Korea, Republic of

Effect of Uncertainties in the MSRE Model Part 1: Salt Properties, SPECTRA / SUE Analysis

Marek Stempniewicz, Eric de Geus, Dirk Visser, Christian Fedon, Ferry Roelofs, Fajar Pangukir

NRG, Netherlands, The

Effect of Uncertainties in the MSRE Model Part 2: Delayed Neutron Precursors, SPECTRA / SUE Analysis

Marek Stempniewicz, Eric de Geus, Dirk Visser, Christian Fedon, Ferry Roelofs, Fajar Pangukir

NRG, Netherlands, The

How Good is “Good Agreement”? Considerations when Comparing Experiments with Simulations for Rod Bundles with Wire Spacers

Julio Pacio¹, Ferry Roelofs², Heleen Uitslag-Doolaard², Akshat Mathur², Dillon Shaver³, Elia Merzari⁴

1: Belgian Nuclear Research Centre (SCK CEN), Belgium; 2: Nuclear Research and Consultancy Group (NRG), The Netherlands; 3: Argonne National Laboratory (ANL), United States of America; 4: Pennsylvania State University (PSU), United States of America

Analyzing the Effect of Deformed Pins in LMFR Rod Bundles

Ferry Roelofs¹, Shubham Dalvi¹, Heleen Uitslag-Doolaard¹, Markus Daubner², Karsten Litfin², Manuela Profir³, Vincent Moreau³, Pietro Cioli Puviani⁴, Daniele Martelli⁴, Ivan Di Piazza⁴, Sara Gonzalez Ruiz⁵, Luis Carbonelle⁵, Matilde Fiore⁵, Mushin Can Akkurt⁵, Philippe Planquart⁵, Julio Pacio⁶

1: NRG, Netherlands, The; 2: KIT, Germany; 3: CRS4, Italy; 4: ENEA, Italy; 5: VKI, Belgium; 6: SCK CEN, Belgium

Numerical Simulation of Flow and Heat Transfer Characteristics for LBE in Plate-type Bundle Fuel Assembly with LES-Smagorinsky Lilly Model

Feiran Wang^1,2, Zhengjie Yang^1,2, Jiming Wen^1,2, Bangyang Xia^3,4, Chong Chen^3,4, Xue Zhang^3,4, Gongjian Xie¹, Ruifeng Tian^1,2, Sichao Tan^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 & Equipment, Harbin Engineering University, China, People's Republic of; 3: National Key Laboratory of Nuclear Reaction Technology, China, People's Republic of; 4: State Key Laboratory of Advanced Nuclear Energy Technology, China, People's Republic of

Thermal-hydraulic and Safety Analysis of a Horizontal Assembly in the LFR during Flow Blockage Accident

Di Wu^1,2, Zhibo Gao^1,2, Minyang Gui^1,2, Jiaxin Zhang³, Jie Cheng^1,2, Xu Han^1,2, Xiaobo Zeng^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; 3: Nuclear Power Institute of China, China, People's Republic of

Local Hot Spots of the Wire-wrapped Pin Bundle in the Liquid Metal Cooled Reactors

Taehwan Ahn^1,2, Wilhelm-Martin Bissels², Victor Petrov^1,2, Annalisa Manera^1,2

1: ETH Zurich, Switzerland; 2: Paul Scherrer Institute (PSI), Switzerland

Uncertainty Analysis of Rod Bundle Channel for Lead-Bismuth Reactors Based on Sub-channel Code

Deyan Kong, Di Wu, Jie Cheng, Xu Han, Xiaobo Zeng, Jianjun Wang

Harbin Engineering University, China, People's Republic of

Heavy Liquid-Metal Pool Thermal-Hydraulic Experiments and Simulations

Katrien D. A. Van Tichelen¹, Steven Keijers¹, Fabio Mirelli¹, Julio Pacio¹, Rui Serrano Diogo¹, Mohammed Muaaz Hussain², Fajar Sri Lestari Pangukir², Dirk Cornelis Visser², Ferry Roelofs², Lilla Koloszar³, Silvania Lopes³, Philippe Planquart³

1: SCK CEN, Belgian Nuclear Research Centre, Belgium; 2: NRG Pallas, the Netherlands; 3: von Karman Institute for Fluid Dynamics, Belgium

Particle-Based Approaches to Multiphysics Simulation in Nuclear Safety

Eung Soo Kim¹, Yelyn Ahn¹, Jin Woo Kim¹, Jin Hyun Kim¹, Juryong Park¹, Young Beom Jo², Hee Sang Yoo³

1: Seoul National University, Korea, Republic of; 2: Kyung Hee University, Korea, Republic of; 3: CEA/DES/IRESNE, France

Solidification-Melting Behaviors and Mushy Characteristics of Molten Salt in Filling Horizontal Cold Pipe

HongXiang Yu^1,2, Chong Zhou^1,2, Xiaofeng Yuan¹, Yushuang Chen^1,2, Shanwu Wang¹, Hui Deng^1,2

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

Optimizing Core Stability and Flow in Passive Molten Salt Fast Reactors Using GeN-Foam

Juhyeong Lee¹, Do won Lee¹, Yonghee Kim², Sangtae Kim¹, Sung Joong Kim¹

1: Hanyang University, Korea, Republic of; 2: Korea Advanced Institute of Science and Technology, Korea, Republic of

Thermal-hydraulic Research Progress in Fluoride Salt Cooled Nuclear Reactor Applied in Commercial Ship

Limin Liu, Jiaming Zhang, Hanyang Gu

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

A Coupled OpenFOAM-Modelica Modelling Framework for Analysing MSR Safety-Related Transients

Sophie Deanesi, Stefano Lorenzi

Politecnico di Milano, Italy

Enhanced Multi-Physics Modelling of the MSRE Using GeN-Foam

Shervineh Amirkhosravi¹, Frik van Niekerk¹, Marina du Toit¹, Alessandro Scolaro², Andreas Pautz²

1: North-West University, South Africa; 2: EPFL, Switzerland

Implementation of Molten Salt – Concrete Interactions into a System Thermal-Hydraulic Code SPECTRA

Marek Stempniewicz, Ferry Roelofs, Eric de Geus

NRG, Netherlands, The

Undercooling Conditions in SFR Low Void Core Designs

Sara Perez-Martin

Karlsruhe Institute of Technology, Germany

Development of a Novel OpenFOAM Solver for Tritium Permeation Modeling in Molten Fluoride Salt Systems

Wooseong Park^1,2, Guanyu Su¹, Yong Hoon Jeong²

1: UC Berkeley, United States of America; 2: KAIST, Korea, Republic of

CFD Simulation of Geyser Boiling and Startup Instabilities of a Two-Phase Closed Water Thermosyphon using OpenFOAM

Almanzo Arjuna, In Cheol Bang

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

CFD Modeling of Thermal-hydraulic Behavior in SCWR: Analysis of Trans-critical Transients

Shubham Rajesh Vaidya, Goutam Dutta, Harish Pothukuchi

Indian Institute of Technology Jammu, India

Modelling of Selected SAFARI-1 Research Reactor Transients using RELAP/SCDAPSIM/MOD3.4

Samukeliswe Nozipho Khoza, Rian Hendrik Prinsloo

South African Nuclear Energy Corporation SOC Limited (Necsa), South Africa

A Plan for Developing a Korean Virtual Reactor Platform for SMR Demonstration and Operation

Yun-Je Cho

Korea Atomic Energy Research Institute, Korea, Republic of

SAM Code Performance Improvement by Incorporating a High-order Staggered-grid Finite Volume Method

Ling Zou, Rui Hu

Argonne National Laboratory, United States of America

Comparative Analyses of DRACCAR and TRACE Codes for RefloodingThermal-Hydraulics at Low Pressure or Low Flowrate

Andreas Tatidis, Weimin Ma, Sean Roshan

Royal Institute of Technology (KTH), Sweden

Comparative Analysis of RELAP5 and ANSYS-CFX Simulations for Microchannel Heat Exchangers: A Case Study on the VLF Primary Heat Exchanger

Giorgio Khalil Youssef^1,3, Andrea Missaglia², Marco Caramello³, Stefano Lorenzi², Marco Ricotti², Cristiano Ciurluini¹, Fabio Giannetti¹

1: Sapienza University of Rome, Italy; 2: Politecnico di Milano, Italy; 3: Ansaldo Nucleare, Italy

Comprehensive Evaluation of the Applicability of the Relap5 Boron Transport Module in Reactor Annular Down-comer

Qi Zhang¹, Zhenhai Liu¹, Guangliang Yang¹, Yongzhong Huang¹, Junxian Cao¹, Di Wu², Sichao Tan²

1: Nuclear Power Institute of China, China, People's Republic of; 2: Harbin Engineering University, China, People's Republic of

Performance Evaluation of State-of-the-art drift-flux Model Implemented in AMAGI

Naofumi Tsukamoto¹, Takashi Hibiki²

1: Nuclear Regulation Authority, Japan; 2: City University of Hong Kong, Hong Kong S.A.R. (China)

Benchmarking on the Performance of System Codes to Reproduce a Long SBO Sequence with the Actuation of a Passive Heat Removal System

Jordi Freixa¹, Víctor Martínez-Quiroga¹, Aymane Talha¹, Fares Alblouwy², Maxime Vernassiere³, Guillaume Mianné⁴, Sebastian Buchholz⁵, Jong Hyuk Lee⁶, Buyng-Gil Huh⁷, Omar Al-Yahia⁸, David Blanco de las Muelas⁹, Michael Johansson¹⁰, Miguel Sánchez-Perea¹², Martina Adorni¹³, Simon Schollenberger¹¹, Lars Dennhardt¹¹

1: Universitat Politècnica de Catalunya, Spain; 2: Technical Research Center of VTT, Finland; 3: French Alternative Energies and Atomic Energy Commission (CEA), France; 4: Electricité de France (EdF), France; 5: Gesellschaft für Anlagen- und Reaktorsicherheit gGmbH (GRS), Germany; 6: Korea Atomic Energy Research Institute (KAERI), Korea, Republic of; 7: Korea Institute of Nuclear Safety (KINS), Korea, Republic of; 8: Paul Scherrer Institut (PSI), Switzerland; 9: Polytechnic University of Valencia - Energy Engineering Institute (UPV), Spain; 10: Vattenfall Nuclear Fuel, Sweden; 11: Framatome GmbH; 12: Consejo de Seguridad Nuclear (CSN), Spain; 13: OECD Nuclear Energy Agency (NEA)

Improving the Understanding and Prediction of Mixed Convection of Developing Flow

Zewen Zou, Shuisheng He

University of Sheffield, United Kingdom

Enabling Advanced Gas-cooled Reactor Life Extension by Predicting Through-Life Pressure and Temperature Fields in Graphite Using CFD

Graham Macpherson¹, Carolyn Howlett¹, Ross Higgins¹, David Munn¹, James Pethan², Mike Rabbitt²

1: Frazer-Nash Consultancy, United Kingdom; 2: EDF Nuclear Services, United Kingdom

Cost-Effective Simulation of a Prismatic HTGR Fuel Assembly Using Subchannel CFD

Bo Liu, Wei Wang, Charles Moulinec, Stefano Rolfo

Science and Technology Facilities Council (STFC), United Kingdom

Modeling a Sodium Heat Pipe Experiment at SPHERE Using Sockeye

Joshua Edmund Hansel¹, Zachary Don Sellers¹, Jeremy Lee Hartvigsen¹, Piyush Sabharwall¹, Lise Cecile Madeleine Charlot¹, Elia Merzari²

1: Idaho National Laboratory, United States of America; 2: The Pennsylvania State University, United States of America

Study on Nuclear-thermal-structural Multi-physics Coupling in Solid-state Heat Pipe Reactors Considering Irradiation Effects

Dacai Zhang, Zeguang Li, Zilin Su, Huifu Wang, henglong Lin

Tsinghua University, China, People's Republic of

System Level Modeling of the 200 MW General Pebble Bed Reactor (GPBR200) with SAM

Zhiee Jhia Ooi, Ling Zou, Thanh Hua, Jun Fang, Rui Hu

Argonne National Laboratory, United States of America

Influence of the Intermediate Heat Exchanger Geometry on the Flow in a Model Representative of a Sodium Fast Reactor

David Guenadou, Philippe Aubert, Jean-Philippe Descamps

CEA, France

Advanced AMESIM CODE-Based System Transient Safety Analysis for PGSFR

Seon Gon Kim¹, Je Whan Lee², Jae Ho Jeong¹

1: Chung-Ang University, Korea, Republic of; 2: Korea Atomic Energy Research Institute (KAERI), Korea, Republic of

Applicability Investigation of Reactor Vessel Thermal–Hydraulics Analysis Method for Transient Toward Natural Circulation Condition

Erina Hamase¹, Yasuhiro Miyake², Yasutomo Imai², Norihiro Doda¹, Ayako Ono¹, Masaaki Tanaka¹

1: Japan Atomic Energy Agency, Japan; 2: NDD Corporation, Japan

Assessment of a System-level Numerical Model of the Thermal Hydraulic Experimental Test Article (THETA) Facility Using SAS4A/SASSYS-1

Yeongshin Jeong¹, Lander Ibarra¹, Matthew Weathered¹, Daniel J. O'Grady¹, Acacia J. Brunett¹, Rachel Thomas¹, Tyler Sumner¹, Lisa Momkus², James McCay², Ryan Blanchard², Patrick Everett²

1: Argonne National Laboratory, United States of America; 2: Oklo Inc., United States of America

ATHLET Simulation of the SMR-SFR Primary System: Exploring 0D and Pseudo-3D Flow Modeling

Alexander Ponomarev, Emil Fridman

Helmholtz Zentrum Dresden Rossendorf (HZDR), Germany