Conference Agenda

Experimental Analysis of Non-Condensable Helium and Steam Distribution Due to Condensation in the CIGMA Facility Simulating the Reactor Building

Ari Hamdani, Shu Soma, Satoshi Abe, Yasuteru Sibamoto

Japan Atomic Energy Agency, Japan

Comparison between EDF MAAP5.04 and EPRI MAAP6 Codes on Hypothetical Severe Accidents in an Integral PWR

Jeremy Bittan, Nikolai Bakouta

Electricité de France, France

Severe Accident Progression Analyses of Loss-of-coolant Accidents with Different Break Sizes in a Typical Japanese Four-loop PWR Using MELCOR2.2

Junichi Kaneko, Wataru Kikuchi, Masashi Taira

Nuclear Regulation Authority, Japan

ASTEC V3: A Comprehensive Integral Code for Nuclear Safety Analysis and Research – Overview of Recent Applications and Perspectives

Patrick Drai, Nathalie Girault, Laure Carénini, Laurent Laborde, Julie-Anne Zambaux, Laure Cloarec, Eric Delaume, Florian Fichot, Catherine Marchetto, Sidi Souvi, Olivia Coindreau, François Virot, Matthieu Jobelin, Guillaume Astier, Francois Kremer, Karine Chevalier-Jabet, Loic Bosland, Helene Bloch, Lionel Chailan, Raphael Monod, Michael Johnson, Laurent Foucher, Alexandre Bleyer, Alain Commande, Jean-Jacques Ingremeau, Marton Szogradi

Autorité de Sûreté Nucléaire et de Radioprotection, France

Analyzing Steam Explosions During Severe Accidents in Nordic BWRs with MELCOR-TEXAS Coupling

Govatsa Acharya, Ibrahim Batayneh, Dmitry Grishchenko, Pavel Kudinov

KTH Royal Institute of Technology, Sweden

Progress in Utilizing Macroscopic Models for the Simulation of Passive Systems in the Lumped Parameter Code AC²/COCOSYS

Ivan Bakalov, Claus Spengler, Nils Reinke, Siegfried Arndt

GRS, Germany

Characteristic Features of Fission Product Behavior by CINEMA and MELCOR Codes during Severe Accidents of OPR1000

Se Hee Kwon¹, Juhyeong Lee¹, Joon Young Bae¹, Yujin Kim¹, Joon-Eon Yang¹, JinHo Song¹, Sung Joong Kim^1,2

1: Department of Nuclear Engineering, Hanyang University, Korea, Republic of; 2: Institute of Nano Science and Techonology, Hanyang University, Korea, Republic of

Experimental Investigation of Pressure Drop in Single and Two-Phase Flow Through Sand Packed Beds

Aimad Bouloudenine, Liangxing Li, Shang Shi, Zutao Xiang

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

Using Calibrated Sodium Data for Preliminary Validation of the SRT Code for Advanced Reactors

Dong Hoon Kam¹, Dave Grabaskas¹, Kyle Becker², Mark Anderson², Tyler Starkus¹

1: Argonne National Laboratory, United States of America; 2: University of Wisconsin-Madison, United States of America

An Update of the Models Related to the In-Vessel Retention Strategy in the MAAP6 Code

Nikolai Bakouta, Jeremy Bittan

Electricité de France, France

Progress in the Development of the ContainmentFOAM CFD Package for Analysis of Current and Future LWR Containment Phenomena

Stephan Kelm¹, Allen George², Ruiyun Ji³, Carlos Vazquez-Rodriguez¹, Khaled Yassin¹, G. Vijaya Kumar⁴, Xiongguo Liu¹, Daniel Schumacher¹, Karl Sturm⁵, Leon Thelen¹, Martin Lövenich¹, Claudia Druska¹, Astrid Kuhr¹

1: Forschungszentrum Juelich GmbH, Germany; 2: Forschungszentrum Juelich GmbH and Karlsruhe Institute of Technology, Germany; 3: Forschungszentrum Juelich GmbH and Universität der Bundeswehr Muenchen, Germany; 4: Forschungszentrum Juelich GmbH, Germany and Indian Institute of Technology Madras, India; 5: Forschungszentrum Juelich GmbH and RWTH Aachen University, Germany

Uncertainty and Sensitivity Analysis of MELCOR-Based Source Term Predictions for the PHEBUS FPT-1 Experiment

Han Sol Park, Yeon-Gun Lee

Sejong University, Korea, Republic of

Numerical Investigation on Key Conditions for Metal Containment Vessel of i-SMR during Loss of Coolant Accident

Cheolwoong Kim¹, Jae Hyung Park¹, Hyo Jun An¹, Ok Hyeon Lee¹, Sang Ho Kim³, JinHo Song¹, Joon Eon Yang¹, Sung Joong Kim^1,2, Seokgyu Jeong³, Joon Young Bae¹, Jaehyun Ham³

1: Department of Nuclear Engineering, Hanyang University, Korea, Republic of; 2: Institute of Nano Science & Technology, Hanyang University, Korea, Republic of; 3: Korea Atomic Energy Research Institute, Korea, Republic of

Simulation and Analysis of Containment Behavior during Selected Severe Accident Transients in a Generic Konvoi-type PWR using COCOSYS

Miriam Müer¹, Michael Klauck², Stephan Kelm², Marco K. Koch¹

1: Ruhr-Universität Bochum (RUB), Germany; 2: Forschungszentrum Jülich GmbH (FZJ), Germany

Experiments on Spray System Efficiency and Performance under Severe Accident Conditions

Kevin Marc Dieter¹, Martin Freitag¹, Eike Wolfgang Schmidt¹, Benjamin von Laufenberg¹, Gert Langrock², Friedhelm Funke²

1: Becker Technologies GmbH, Germany; 2: Framatome GmbH, Germany

Impact of the Containment and Reactor Pool Modelling on the Evolution of a Severe Accident in a SMR using ASTEC 3.1

Mirco Di Giuli, Ali Mickael Swaidan, Shizhen Yu, Simon Verdebout, Paul Foucaud

Tractebel (ENGIE), Belgium

Sensitivity Analysis and Experimental Validation of the WISDOM Mecanistic Spray Model in Nuclear Reactor Containments

Antoine Ciechocki, Benoit Normand, Arnaud Chazottes

Université Paris-Saclay, CEA, France

Comparison between System Thermal Hydraulic and CFD Analyses of Atmospheric Mixing in the Dome of a Generic PWR Containment during a Severe Accident Transient

Fajar Sri Lestari Pangukir, Dirk Cornelis Visser, Marek Michal Stempniewicz, Nicolaas Bernardus Siccama, Sina Tajfirooz

NRG PALLAS, Netherlands, The

Efficiency of Electrostatic Precipitator for Removal of Iodine-Containing Particles in Severe Accident Scenarios

Satish Basnet, Atte Jäntti, Olli Sippula, Anna Lähde

University of Eastern Finland, Finland

What is Important and What is Less Important in the Studies of Containment Iodine Behavior at the Severe Accidents

Adolf Rydl¹, Jungsook Clara Wren²

1: INSET s.r.o., Czech Republic; 2: McMaster University, Canada

Experimental Study on the Removal of Iodine Vapor and Iodine-Based Aerosols Inside the Containment of Nuclear Power Plants

Jialong Li^1,2, Jiaxuan Tang^1,2, Luteng Zhang^1,2, Zaiyong Ma^1,2, Wan Sun^1,2, Longxiang Zhu^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

Investigation of Source Term During Severe Accidents in Integral PWR SMRs

Govatsa Acharya, Dmitry Grishchenko, Pavel Kudinov

KTH Royal Institute of Technology, Sweden

Uncertainty and Sensitivity Analysis of Radioactive Source Terms from Intact Containment Category for Nuclear Power Plants Based on the BEPU Method

Jing Sun, Shengsheng Lin, Xuhao Zhang, Yaru Li

China Nuclear Power Engineering Co. LTD., China, People's Republic of

Uncertainty Quantification of a Postulated Severe Accident Scenario in a Generic German PWR

Livia Tiborcz, Thorsten Hollands

Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany

ENSO Contribution to the HORIZON 2020 MUSA Project: In-Vessel Uncertainty Analysis with RELAP/SCDAPSIM/MOD3.4 and IUA2.0 of a Long-term SBO Scenario in a Gen-II PWR

Victor Martinez-Quiroga, Marina Perez-Ferragut

Energy Software Ltd., Spain

ENSO Contribution to the IAEA CRP I31033: Uncertainty Analysis with RELAP/SCDAPSIM/MOD3.5 of a Long-term SBO Scenario in a CAREM-like iPWR

Victor Martinez-Quiroga, Marina Perez-Ferragut

Energy Software Ltd., Spain

Stepwise Uncertainty Analysis Methodology in Severe Accidents

Rafael Bocanegra, Victor Martínez Quiroga, Marina Perez Ferragut

ENSO, Spain

Probability Analysis of Steam Generator Heat Transfer Tube Rupture under Severe Accident

ZhanXiang Huang

University of Science and Technology of China, China, People's Republic of

Fuel Coolant Interaction/Ex- vessel Steam Explosion: An Overview of Experimental Tests Performed at CEA with Prototypic Corium in the Frame of ICE Program

Pascal Piluso¹, Jules Delacroix¹, Andrea Quaini¹, Emmanuelle Bracks¹, René Guinebretière², Denis Menut³, Renaud Meignen⁴, Nicolas Rimbert⁵

1: CEA, France; 2: University of Limoges, France; 3: Synchrotron SOLEIL, France; 4: ASNR, France; 5: University of Lorraine, France

Impact of Advanced Technology Fuel Cladding Materials on the Progression of Severe Accidents in a Generic Natural-Circulation iPWR

Mauricio Exequiel Cazado¹, Zaira Itzel Jimenez Balbuena¹, Laure Carénini², Fabrizio Gabrielli¹, Victor Hugo Sánchez-Espinoza¹

1: Karlsruhe Institute of Technology (KIT), Germany; 2: French Authority for Nuclear Safety and Radiation Protection (ASNR), France

Mitigation of Radioactive Release during Underwater Laser-cutting of Corium after a Severe Accident: An Analytical Study

Luis Herranz¹, Rafael Iglesias¹, Emmanuel Porcheron²

1: CIEMAT, Spain; 2: ASNR, France

Investigation of the Effects of Surface Inclination on the Ablation of a Solid by the Impact of Hot Liquid Jet: Implications for Sodium-cooled Fast Reactor Safety

Asma Djermoune^1,2, Alexandre Lecoanet¹, Nathalie Seiler¹, Nicolas Rimbert², Michel Gradeck²

1: CEA, France; 2: Université de Lorraine, France

Development and Qualification of Advanced Core Catcher for SFR

Prabhat Kumar Shukla^1,2, E. Hemanth Rao¹, Anish Kumar^1,2, Sagar Nagpure¹, G. Muthu Kumar¹, Avinash Kumar Acharya¹, Sanjay Kumar Das¹, B.K Sreedhar¹

1: Indira Gandhi Centre for Atomic Research, India; 2: Homi Bhabha National Institute, India

Quantification of the Influence of Air Entrainment on Triggering of Single Molten Droplet

Cheng Peng¹, Kaiwen Shi¹, Dong Li¹, Dmitry Grishchenko², Pavel Kudinov²

1: Shanghai University of Electric Power, China, People's Republic of; 2: Royal Institute of Technology, Sweden

Numerical Investigation on the Structural Integrity of an Ex-vessel Core Catcher under Guillotine-type RPV Failure Using Smoothed Particle Hydrodynamics

Jin-Woo Kim¹, Hee Sang Yoo^1,2, Tae Hoon Lee¹, Yelyn Ahn¹, Min Chan Kwon¹, Eung Soo Kim¹

1: Seoul National University, Korea, Republic of; 2: French Alternative Energies and Atomic Energy Commission (CEA), France

Analysis of Corium Stratification Effect on Molten Core-Concrete Interaction observed in the MOCKA 3.1 Test

Jun Sung Choi, Tae Hwan Kim, Jin-Woo Kim, Min Jae Kim, Eung Soo Kim, Hyun Sun Park

Seoul National University, Korea, Republic of

Development of the New Jet Breakup Length Correlation Considering the Effect of Vapor Generation Intensity on the Melt Jet Fragmentation

WooHyun Jung¹, Hyun Sun Park²

1: University of Wisconsin, United States of America; 2: Seoul National University, Korea, Republic of

Empirical Feedback on Layout Design Optimization of Reactor Cavity Water Injection Cooling System

Li Peng, Zhe Jiang

China Nuclear Power Engineering Co.,Ltd., China, People's Republic of

URANS Simulation of CANDU Debris Bed Transient Melting in a Severe Accident

Yeshan Sun, Stephen Tullis, Marilyn Lightstone

McMaster University, Canada

Hydrogen Concentration Distribution in the Reactor Building of Fukushima Daiichi NPP Unit-3

Masanori Naitoh, Fumitomo Onishi, Atsuo Takahashi, Toshoharu Mitsuhashi, Achihoro Hamano, Hirotaka Hadachi

Advancesoft Corporation, Japan

Review of Direct Air Capture Applying to the Nuclear System

Seongmin Son, Taejun Song, Joohung Jung

Kyungpook National University, Korea, Republic of

Design Characteristics and Preliminary Performance Analysis on Passive Safety System of i-SMR

Seong-Su Jeon, Younjae Park, Sang Gyun Nam, Jehee Lee, Jan Hruškovič, Soon-Joon Hong, Bub Dong Chung

FNC Technology, Korea, Republic of

Adaptive Decay Heat Estimation for Non-SCRAM Shutdowns: Verification and Application

Evgeny Nikitin

Helmholtz-Zentrum Dresden-Rossendorf, Germany

The Impact of Inventory Fill on Large-Scale RCCS Performance At PassiveBoiloff Conditions

Matthew Jeffrey Jasica, Qiuping Lv, Darius Lisowski

Argonne National Laboratory, United States of America

Investigation of Performance of a Large-Scale Water-Based RCCS Under Varying Decay Heat Loads

Qiuping Lv, Matthew J. Jasica, Darius D. Lisowski, Zhiee J. Ooi, Rui Hu

Argonne National Laboratory, United States of America

Experimental Investigations on Fuel Pin Failure Propagation in Lead-cooled Fast Reactor Cores

Axel Monney^1,2, Victor Petrov^1,2, Annalisa Manera^1,2

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

Study on the Drift Flux Model of Gas-LBE Two-phase Flow in Circular Tubes with Different Diameters

Hong Zhang¹, Yangyong Ou², Di Wang², Lingfeng Wan¹, Wan Sun¹, Liangming Pan¹, LongXiang Zhu¹

1: Chongqing University, China, People's Republic of; 2: China Nuclear Power Technology Research Institute Co., Ltd, China, People's Republic of

Study on the Interfacial Area Concentration of Nitrogen-Lead-Bismuth-Alloy Two-Phase Flow

Lingfeng Wan^1,2, Yong Ouyang³, Di Wang³, Hong Zhang^1,2, Longxiang Zhu^1,2, Zaiyong Ma^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; 3: China Nuclear Power Technology Research Institute, China, People's Republic of

Data-Driven Bubble Transport Prediction and Uncertainty Quantification in LFR During SGTR with Heterogeneous Inputs and Constrained Outputs

Longcong Wang¹, Kejian Dong², Jiyun Zhao²

1: Harbin Engineering University, China, People's Republic of; 2: City University of Hong Kong, Hong Kong S.A.R. (China)

Interaction Mechanism between Lead-bismuth Liquid Metal and Water

Lin Zhang, Chang Deng, Xiaojing Liu

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

Enhancement of Inherent Safety Performance in Lead-Bismuth Fast Reactors Through Secondary-Side Passive Residual Heat Removal System

Rongtian Zeng, Li Ge, Jianqiang Shan

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

Overview of Key Elements of Combustible Gases Management in Containment

Ahmed Bentaib¹, Gonzalo Jiménez², Luis Enrique Herranz³, Nabiha Chaumeix⁴, Stephan Kelm⁵, Ernst-Arndt Reinecke⁶, Matthias Braun⁷, Marco Koch⁸, Ivo Kljenak⁹, Oleksandr Sevbo¹⁰, Zhe {Rita} Liang¹¹

1: IRSN, France; 2: UPM, Spain; 3: CIEMAT, Spain; 4: CNRS-ICARE, Spain; 5: JULICH, Germany; 6: JULICH, Germany; 7: Framatome, Germany; 8: RUB, Germany; 9: JSI, Solvenia; 10: Energorisk, Ukraine; 11: CNL, Canada

Assessment of Monitoring Performance for Hydrogen Concentration in Severe Accidents

Youngsu Na, Jin-Hyeok Kim, Changwan Kang, Seongho Hong

Korea Atomic Energy Research Institute, Korea, Republic of

PARs Interaction with Other Safety Systems during Severe Accidents in Western PWR Containments

Joan Fontanet, Luis Enrique Herranz

CIEMAT, Spain

Validation of the PAR Model REKO-DIREKT in the Framework of the AMHYCO Project

Ernst-Arndt Reinecke, Claudia Druska

Forschungszentrum Juelich GmbH, Germany

Hydrogen Behavior Analysis for Lower Level of BWR Reactor Building during Severe Accident

Tomohisa Yuasa, Miki Saito, Kimitoshi Yoneda

Central Research Institute of Electric Power Industry, Japan

Experimental Study on the Containment Thermal Hydraulic Behaviors by Hydrogen Mitigation and Pressure Control Systems at Severe Accident Conditions

Jongtae Kim, Seongho Hong, Ki Han Park, Jinhyeok Kim, Jeong Yun Oh, Sang Ho Kim

Korea Atomic Energy Research Institute, Korea, Republic of

A Feasibility Study of Physics-Informed Neural Network-Based Severe Accident Analysis Code

Jeesuk Shin¹, Minseo Lee¹, Cheolwoong Kim², Sunwoong Yang³, Joongoo Jeon¹

1: Jeonbuk National University, Korea, Republic of; 2: Hanyang University, Korea, Republic of; 3: Korea Advanced Institute of Science and Technology, Korea, Republic of

Development of Physical Properties Prediction Model Near Critical Point Using Deep Learning

Jubin Kim¹, Sai Raja Gopal Vadlamudi², Eung Soo Kim¹, Hyun Sun Park¹

1: Seoul National University, Korea, Republic of; 2: Helmholtz-Zentrum Dresden-Rossendorf, Germany

Evaluation of RCS and SG Injection Effectiveness in the Extended SBO Scenario of the OPR-1000

Jemo Ryu, Jaehyun Cho

Chung-Ang University, Korea, Republic of

Simulation Study of Coolant Loss Accident in Floating Nuclear Power Platform based on IP200

Lei Yu, Yifan Xu, Genglei Xia, Minjun Peng

Harbin Engineering University, China, People's Republic of

B4C-Stainless Steel Eutectic Characterisation and Boron Migration under Severe Reactor Conditions

Zeeshan Ahmed¹, Ravinder Kumar¹, Hidemasa Yamano², Marco Pellegrini^1,3, Ryo Yokoyama¹, Koji Okamoto¹

1: The University of Tokyo, Japan; 2: Japan Atomic Energy Agency, Japan; 3: Politecnico di Milano, Italy