Schedule at a Glance

Day Time (GMT+8) Room 1 Room 2 Room 3 Room 4
Sept. 6
(Tue.)
13:00 – 13:30 Opening Ceremony (Room 1)
13:30 – 14:10 Plenary I (Room 1)
14:10 – 14:50 Plenary II (Room 1)
14:50 – 15:30 Plenary III (Room 1)
15:30 – 15:50 Break
15:50 – 17:10 Fundamental Thermal-Hydraulics – I Computational Thermal-Hydraulics – I Experimental Thermal-Hydraulics – I Safety and Severe Accidents- I
17:10 – 17:25 Break
17:25 – 18:45 Fundamental Thermal-Hydraulics – II Computational Thermal-Hydraulics – II Experimental Thermal-Hydraulics – II Safety and Severe Accidents- II
18:45 – 19:00 Break
19:00 – 20:20 Fundamental Thermal-Hydraulics – III Computational Thermal-Hydraulics – III Experimental Thermal-Hydraulics – III Safety and Severe Accidents- III
Day Time (GMT+8) Room 1 Room 2 Room 3 Room 4
Sept. 7
(Wed.)
13:00 – 13:30 Keynote Lecture 1 Keynote Lecture 2 Keynote Lecture 3
13:30 – 14:00 Keynote Lecture 4 Keynote Lecture 5 Keynote Lecture 6
14:00 – 14:15 Break
14:15 – 15:35 Special Session I- Decommission Computational Thermal-Hydraulics – IV Thermal-Hydraulics and Safety of Advanced Reactors – I Safety and Severe Accidents- IV
15:35 – 15:50 Break
15:50 – 17:10 Special Session II- Decommission Fundamental Thermal-Hydraulics – IV Thermal-Hydraulics and Safety of Advanced Reactors – II Safety and Severe Accidents- V
17:10 – 17:25 Break
17:25 – 18:45 Special Session III – Spent Fuel Management Experimental Thermal-Hydraulics – IV Small Module Reactors and Micro Reactors – I Safety and Severe Accidents-VI
18:45 – 19:00 Break
19:00 – 20:20 Computational Thermal-Hydraulics – V Plant Operation, Diagnostics, Monitoring and Maintenance Small Module Reactors and Micro Reactors – II Safety and Severe Accidents- VII
Day Time (GMT+8) Room 1 Room 2 Room 3 Room 4
Sept. 8
(Thu.)
13:00 – 15:00 Special Session- Development and Prospect of Nuclear Backend (Room 1) Fundamental Thermal-Hydraulics – V (Room 2)
15:00 – 15:20 Break
15:20 – 17:20 Panel Discussion- SMR and Micro Reactors (Room 1)
17:20 – 18:00 Closing Ceremony (Room 1)

* Please note that the program is subject to change, and will be updated continuously up to the conference.

Sept. 6 (Tue)
Room 1
Plenary Session Sept. 6 (Tue), 13:30 – 15:30, Room 1
Session Chair: Prof. Min Lee (National Tsing Hua University, Taiwan)
Session Co-Chair: Prof. Chin Pan (City University of Hong Kong, China)
Plenary I Advanced Techniques in Reactor Thermal Hydraulics and Safety
Prof. Yassin A. Hassan (Texas A&M University, United States)
Plenary II Prospect and History of Nuclear Energy
Dr. Jason Chao (Nuclear Resilience Group Inc., United States)
Plenary III SMR—ACP100 and Its Multiple Application
Dr. Danrong Song (China National Nuclear Corporation, China)
Fundamental Thermal-Hydraulics – I Sept. 6 (Tue), 15:50 – 17:10, Room 1
Session Chair: Prof. Jiyun Zhao (City University of Hong Kong, China)
Session Co-Chair: Prof. Daeseong Jo (Kyungpook National University, Korea)
N13P042 Ultrasound Vibrational Characteristics of Nucleate Boiling Bubble
Do Yeong Lim, In cheol Bang (Ulsan National Institute of Science and Technology (UNIST), South Korea)
N13P099 Identification of Threshold Parameters in Subcooled Flow Boiling through a Narrow Rectangular under Static and Rolling Conditions
Faraz Aziz, Daeseong Jo (Kyungpook National University, South Korea)
N13P021 Multiscale Numerical Research on Successive Nucleate Boiling Enhancement from Microscale to Nanoscale
Sihong He, Song Ni, Jiyun Zhao (City University Of Hong Kong, China)
N13P015 Enhancement Mechanism Study of Microgroove Surface on Dropwise Condensation Heat Transfer
Jingtan Chen, Wei Deng, Jiyun Zhao (City University Of Hong Kong, China)
N13P022 Enhancing Nucleate Boiling Heat Transfer Performance on Micro/Nano Textured Surfaces with Surfactants
Chung Ki Cheng, Kwun Ting Lau, Shahid Ali Khan, Jiyun Zhao (City University Of Hong Kong, China)
Fundamental Thermal-Hydraulics – II Sept. 6 (Tue.), 17:25 – 18:45, Room 1
Session Chair: Prof. Tomio Okawa (University of Electro-Communications, Tokyo, Japan)
Session Co-Chair: Prof. Jiyun Zhao (City University of Hong Kong, China)
N13P014 A Molecular Dynamics Study of Nucleation Boiling over Wettability Thermo-responsive Surface
Wei Deng, JingTan Chen, Jiyun Zhao (City University Of Hong Kong, China)
N13P019 Investigation of pool boiling heat transfer and bubble dynamic through high-speed infrared thermometry
Song Ni, Kejian Dong, Jiyun Zhao (City University Of Hong Kong, China)
N13P059 Experimental study of bubble behavior from nucleate boiling to CHF for water and NOVEC 649 under the pool boiling condition
Park Ji-hwan, Jo Daeseong, Park Il Seouk (Kyungpook, South Korea)
N13P017 On the Onset of Significant Void in Subcooled Flow Boiling
Tomio Okawa, Yuya Endo, Ryoma Tsujimura, Nguyen Thanh Binh (The University of Electro-Communications, Japan)
N13P164 THE EFFECT OF COOLANT SALINITY ON BUBBLE DYNAMICS OF FILM BOILING AROUND SPHERES
Yucheng Deng, Yan Xiang, Qiang Guo, Weimin Ma (KTH Royal Institute of Technology, Sweden)
Fundamental Thermal-Hydraulics – III Sept. 6 (Tue.), 19:00 – 20:20, Room 1
Session Chair: Dr. Mantas Povilaitis (Lithuanian Energy Institute, Lithuania)
Session Co-Chair: Dr. Takahiro Arai (Central Research Institute of Electric Power Industry, Japan)
N13P170 Suppression of Steam Explosion by Nonionic Surfactant Solution
Takahiro Arai, Masahiro Furuya (Central Research Institute of Electric Power Industry, Japan)
N13P049 Experimental Investigation on the Effect of Jet Cross Section Shape on Fragmentation Characteristics of Molten Fuel Using Simulant Materials
ShaoJie Tan, Hui Cheng, SongBai Cheng (Sun Yat-Sen University, China)
N13P168 Effect of flame-obstacle interaction on premixed hydrogen combustion in a confined chamber
Justina Jaseliūnaitė, Mantas Povilaitis (Lithuanian Energy Institute, Lithuania)
N13P205 The Study of Thermal Conductivity Degradation of Fuel Pellet in Loss Of Coolant Accident in WH Type NPP in KOREA
Lee Seung Chan (Korea Hydro Nuclear Power Co. (KHNP-CRI), South Korea)
Room 2
Computational Thermal-Hydraulics – I Sept. 6 (Tue.), 15:50 – 17:10, Room 2
Session Chair: Dr. Yue Jin (Massachusetts Institute of Technology, USA)
Session Co-Chair: Dr. Michał Spirzewski (National Centre For Nuclear Research, Poland)
N13P080 Application of Parallel Strategy in Thermal-Hydraulic System Program
Yingran Guo, Yanhua Yang (Shanghai Jiao Tong University, China)
N13P167 Development of turbulent hydrogen combustion CFD solver for OpenFOAM
Mantas Povilaitis, Justina Jaseliūnaitė, Andrius Ambrutis (Lithuanian Energy Institute, Lithuania)
N13P183 Uncertainty and Sensitivity Study of RANS Based CFD Modelling Approach for Flow in a Tightly Spaced Bare Rod Bundle
Tomasz Kwiatkowski, Michal Spirzewski (National Centre for Nuclear Research, Poland), Afaque Shams (King Fahd University of Petroleum & Minerals, Saudi Arabia)
N13P171 Development of a Sub-channel Analysis Code “MIDAC-T” based on Two-fluid Model and Fully Implicit Method for Three-dimensional Core Analysis in PWR Plants
Tadakatsu Yodo, Wataru Sakuma, Masaaki Katayama, Takayuki Suemura (Mitsubishi Heavy Industries, Ltd., Japan)
N13P151 Evaluation of the COBRA-TF Flow and Heat Transfer Models Based on the NRC/PSU RBHT Reflood Tests
Yue Jin (Massachusetts Institute of Technology, United States), Fan-Bill Cheung (Pennsylvania State University, United States)
Computational Thermal-Hydraulics – II Sept. 6 (Tue.), 17:25 – 18:45, Room 2
Session Chair: Prof. Youichi Utanohara (Komatsu University, Japan)
Session Co-Chair: Dr. Ayako Ono (Japan Atomic Energy Agency, Japan)
N13P048 Development of the simplified boiling model applied to the large-scale detailed simulation
Ayako Ono, Susumu Yamashita (Japan Atomic Energy Agency, Japan), Hiroto Sakashita (Hokkaido University, Japan), Takayuki Suzuki, Hiroyuki Yoshida (Japan Atomic Energy Agency, Japan)
N13P046 Development of Reactor Vessel Thermal-hydraulic Analysis Method in Natural Circulation Conditions with Coarse-mesh Subchannel CFD Model
Erina Hamase (Japan Atomic Energy Agency, Japan), Yasuhiro Yasuhiro, Yasutomo Imai (NDD Corporation, Japan), Norihiro Doda, Ayako Ono, Masaaki Tanaka (Japan Atomic Energy Agency, Japan)
N13P083 Analyses of Natural Convection Heat Transfer and the Resulting Thermal Stratification Inside Water-Filled Vessels Using the CFD-Code OpenFOAM
David Sonntag, Christoph Bratfisch, Marco K. Koch (Ruhr-Universität Bochum, Germany)
N13P032 Direct Numerical Simulation of Unitary to Low Pr Number Mixed Convection in Vertical Turbulent Channel: Analysis of Flow Transition
Cheng-kai Tai, Igor Bolotnov (North Carolina State University, United States)
N13P134 Numerical calculation of scalar transport process in complex flow field and comparison with experimental measurement
Tatsuya Tsuneyoshi (Nagoya University, Japan), Yoichi Utanohara, Koji Miyoshi (Institute of Nuclear Safety System Inc, Japan), Yoshiyuki Tsuji (Nagoya University, Japan)
Computational Thermal-Hydraulics – III Sept. 6 (Tue.), 19:00 – 20:20, Room 2
Session Chair: Dr. Omar S. Al-Yahia (Paul Scherrer Institut, Switzerland)
Session Co-Chair: Dr. Nhan Hien Hoang (Environment and Energy Technology, Inc., Korea)
N13P078 APR1400 Main Steam Line Break Accident Analysis using MARS-KS 3D Core Analysis Module
Nhan Hien Hoang, Y. S. Kim, J. Y. Lee, J. H. Kim, Y. K. Kwack, Suk Ku Sim (Environment and Energy Technology, Inc., South Korea)
N13P140 Modeling of Gaseous Contaminants and Particulate Matters Transport in a Ventilated Machine Workshop of Nuclear Power Plant
Chia-Kuan Chen (Institute of Nuclear Energy Research, Taiwan), Shao-Wen Chen (Institute of Nuclear Engineering and Science, Taiwan), Jhih Jhong Huang, Cheng-Fu Chen (Institute of Nuclear Energy Research, Taiwan)
N13P031 Parametric Study of Aerosol Deposition on Gas Bubble Surface Based on CFD Method
Zhongkai Mei, Xu Cheng (Karlsruhe Institute of Technology, Germany)
N13P113 Parametric Study on the Modeling of the Open Passive Containment Cooling System (CWC)
Omar Al-yahia, Ivor Clifford, Konstantin Nikitin, Hakim Ferroukhi (Paul Scherrer Institut, Switzerland)
Room 3
Experimental Thermal-Hydraulics – I Sept. 6 (Tue.), 15:50 – 17:10, Room 3
Session Chair: Prof. Huai-En Hsieh (Xiamen University, China)
Session Co-Chair: Dr. Jin-Der Lee (National Tsing Hua University, Taiwan)
N13P018 Experimental Investigation on the Heat Convection of Supercritical Carbon Dioxide Flowing Downward in a Uniformly Heated Tube
Yu Cheng Pan (Department of Engineering and System Science, National Tsing Hua University, Taiwan), Lei Wang (Jiangxi University of Science and Technology, China), Jin-Der Lee (Nuclear Science and Technology Development Center, National Tsing Hua University, Taiwan), Ben Ran Fu (Department of Mechanical Engineering, Ming Chi University of Technology, Taiwan), Chin Pan (Department of Mechanical Engineering, City University of Hong Kong, China)
N13P115 Study on heat transfer enhancement in pool with 28-100kHz ultrasonic oscillation at different heights
Po-Hung Hsu, Shao-Wen Chen, Yu-Ting Su, Yu-Sen Chen, Hsin-Ju Li, Han-Yao Chen, Shu-Yao Hwang, Jin-Der Lee (National Tsing Hua University, Taiwan), Jung-Hua Yang, Jong-Rong Wang (Nuclear and New Energy Education and Research Foundation, Taiwan)
N13P116 Effect of Vertical Vibration on the Void fraction and Velocity Field of Adiabatic Two-phase Flow in a Rectangular Tube
Han-Yao Chen, Shao-Wen Chen, Yung-Ming Hsu, Li-Tung Wu (National Tsing Hua University, Taiwan)
N13P067 The Study of Heat Transfer Enhancement by Al2O3 Nanofluids on a Downward Facing Heating Surface
Jia Gao, Huai-En Hsieh, Zhibo Zhang, Shiqi Wang (College of Energy, Xiamen University, China)
N13P063 The Study of Heat Transfer Enhancement by TiO2 Nanofluids Applications on a Downward Facing Surface
Zhibo Zhang, Huai-En Hsieh, Shiqi Wang, Jia Gao (College of Energy, Xiamen University, China)
Experimental Thermal-Hydraulics – II Sept. 6 (Tue.), 17:25 – 18:45, Room 3
Session Chair: Prof. Yuh-Ming Ferng (National Tsing Hua University, Taiwan)
Session Co-Chair: Prof. Ben-Ran Fu (National Yang Ming Chiao Tung University, Taiwan)
N13P052 Measurement of the natural convective heat transfer of a helical coil varying the pitch and the number of turn
Dong Ho Shin, Hyun Ha Ahn, Bum Jin Chung (Kyung Hee University, South Korea)
N13P050 Interaction between two heating spheres in a packed bed under natural convective heat transfer
Seong-il Baek, Bum-Jin Chung, Je-young Moon (Kyung Hee University, South Korea)
N13P057 Influence of bed height and sphere diameter on the natural convection heat transfer of packed beds
Hyunha Ahn, Jeyoung Moon, Jungwon Han, Bumjin Chung (Kyunghee University, South Korea)
N13P190 Measurement of velocity induced by steam condensation into a water pool by tracking the motion of bubbles
Yun Feng, Xicheng Wang, Dmitry Grishchenko, Pavel Kudinov (Royal Institute of Technology, Sweden)
Experimental Thermal-Hydraulics – III Sept. 6 (Tue.), 19:00 – 20:20, Room 3
Session Chair: Prof. Shao-Wen Chen (National Tsing Hua University, Taiwan)
Session Co-Chair: Dr. Yuanjie Li (City University of Hong Kong, China)
N13P144 Differentiations of Image Analysis on Bubble Characteristics during Subcooled Flow Boiling of Seawater Using Various Automatic Algorithms
Yuanjie Li, Xingchi Jiang, Gong Chen, SHAH Waqar Ali Shah, Yuan Gao, Chin Pan (City University Of Hong Kong, Hong Kong)
N13P198 Bubble Detections and Geometric Measurements Using Four Algorithms: Huang, Li, Otsu, and Yen
Yuanjie Li, Xingchi Jiang, Gong Chen, Syed Waqar Ali Shah, Yuan Gao, Chin Pan (City University Of Hong Kong, Hong Kong)
N13P108 Flow Regime Identification for Bubbly and Cap-bubbly Flow in a 3×3 Rod Bundle Using K-means and FCM Methods
Lung-Hung Huang, Pei-Syuan Ruan, Shao-Wen Chen, Yung-Ming Hsu, Jin-Der Lee (National Tsing Hua University, Taiwan), Jong-Rong Wang, Jung-Hua Yang (Nuclear and New Energy Education and Research Foundation, Taiwan), Han-Yao Chen, Hwang Shu Yao Yaog, Lee Shin Ju (National Tsing Hua University, Taiwan)
N13P147 Feasibility analysis for identifying the boundary between Slug and Churn flows by using Probability Density Function
Shu-Yao Hwang, Yon-Min Hsu, Shao-Wen Chen, Min-Song Lin, Bau-Shih Pei (National Tsing Hua University, Taiwan)
Room 4
Safety and Severe Accidents- I Sept. 6 (Tue.), 15:50 – 17:10, Room 4
Session Chair: Dr. Konstantin Nikitin (Paul Scherrer Institut, Switzerland)
Session Co-Chair: Dr. Xueyan Zhang (Huazhong University of Science and Technology, China)
N13P208 Recent Progress of International Standard Problem No.51 Open Phase
Xueyan Zhang, Shiqi Wang, Chengcheng Deng, Yixuan Zhang (Huazhong University of Science and Technology, China), Peng Zhang, Dandan He, Yuquan Li (State Power Investment Corporation Research Institute, China), Martina Adorni (Nuclear Energy Agency, Organisation for Economic Co-operation and Development, France), Jun Yang (Huazhong University of Science and Technology, China)
N13P084 Analyses of the combustible gas release into the containment during a SBO and a SBLOCA scenario in a generic PWR using the code package AC²
Miriam Sophie Mueer, Johannes Hoffrichter, Christoph Bratfisch, Marco K. Koch (Ruhr-Universität Bochum, Germany)
N13P124 Risk Assessment for Loss of Offside Power Scenarios Based on WOG2000 Model and Considering the Effectiveness of RCP Passive Shutdown Seal
Ching Han Chen (Institute of Nuclear Energy Research, Taiwan)
N13P156 CPR estimation by CTF subchannel code with machine learning support
Konstantin Nikitin (PSI, Switzerland), Benjamin Arnold (University of Basel, Switzerland), Ivor Clifford, Hakim Ferroukhi (PSI, Switzerland)
N13P035 Investigation of the Plant Characteristics and Management of Super-FR during BDBA-LOCA
Kota Sumida (Department of Applied Physics, School of Advanced Science and Engineering, Waseda University, Japan), Akifumi Yamaji (Cooperative Major in Nuclear Energy, Graduate School of Advanced Science and Engineering, Waseda University, Japan)
Safety and Severe Accidents- II Sept. 6 (Tue.), 17:25 – 18:45, Room 4
Session Chair: Prof. Guanghui Su (Xi’an Jiaotong University, China)
Session Co-Chair: Prof. Jinbiao Xiong (Shanghai Jiao Tong University, China)
N13P139 Simulation of a SBO Transient with Additional Failures using TRACE code
Jose Ordoñez Rodenas, Jose Felipe Villanueva López, Sofía Carlos Alberola, Sebastián Martorell Alsina (Departamento de Ingeniería Química y Nuclear, Grupo MEDASEGI, Universitat Politècnica de València, Spain), Isabel Martón Lluch, Ana Isabel Sánchez Galdón (Departamento de Estadística e Investigación Operativa Aplicadas y Calidad, Grupo MEDASEGI, Universitat Politècnica de València, Spain), Rafael Mendizabal Sanz, Javier Ramón Camarma (Consejo de Seguridad Nuclear (CSN), Spain)
N13P154 Estimation of the counter-current flow rate of gas flow through blowout panel with the tornado protection net in reactor building
Hiroshi Shirai, Daisuke Fujiwara (TEPCO Systems Corporation, Japan), Naohiro Hayashi, Kensuke Monma (Tokyo Electric Power Company Holdings, Inc., Japan), keizou Taura, Norihito Kobayashi (Electric Power Engineering Systems Co. Ltd., Japan), Hiroshi Takimoto (Central Research Institute of Electric Power Industry, Japan)
N13P060 Feasibility study of in-containment relief valve and pool scrubber in response to the steam generator tube rupture accident in OPR1000
Juhyeong Lee, Wonjun Choi (Hanyang University, South Korea), Byeonghee Lee, Kwang-Soon Ha (Korea atomic energy research institute, South Korea), Sung Joong Kim (Hanyang University, South Korea)
N13P034 Analysis of Thermal Conditions used for Equipment Environmental Qualification for Reactor Auxiliary Building of Kousheng BWR-6 Plant.
Li-Ying Huang (Institute of Nuclear Energy Research, Taiwan), Yng-Ruey Yuann (National Tsing Hua University, Taiwan), Yen-Shu Chen (Institute of Nuclear Energy Research, Taiwan)
Safety and Severe Accidents- III Sept. 6 (Tue.), 19:00 – 20:20, Room 4
Session Chair: Prof. Akifumi Yamaji (Waseda University, Japan)
Session Co-Chair: Prof. Xiaojing Liu (Shanghai Jiao Tong University, China)
N13P043 Characteristics of In-Vessel Hydrogen Generation during Severe Accident of Korean OPR1000 Plant
Byung Jo Kim, Su Min Kwak, Sun Hong Yoon (KEPCO Engineering and Construction Co., South Korea)
N13P039 Influence of the In-Vessel Debris Bed on the Heat Load to a Reactor Vessel under an IVR Condition
Joonsoo Park, Haekyun Park, Bumjin Chung (Kyung Hee University, South Korea)
N13P090 Study on the discharge behavior of the molten-core materials through the control rod guide tube: Investigations of the effect of an internal structure in the control rod guide tube on the discharge behavior
Shinya Kato, ken-ichi Matsuba, Kenji Kamiyama (Japan Atomic Energy Agency, Japan), Assan Akaev, Alexandr Vurim, Viktor Baklanov (National Nuclear Center of the Republic of Kazakhstan, Kazakhstan)
N13P097 Analysis on Cooling Behavior for Simulated Molten Core Material Impinging to a Horizontal Plate in a Sodium Pool
Hatsuki Matsushita, Takaaki Sakai, Ren Kobayashi (Tokai University, Japan), Shinya Kato, ken-ichi Matsuba, Kenji Kamiyama (Japan Atomic Energy Agency, Japan)
N13P047 Analysis of Molten Metal Flow and Freezing in a 3-D Pin Bundle Geometry by MPS Method
Haruki Takei, Takanari Fukuda (Cooperative Major in Nuclear Energy, Graduate School of Advanced Science and Engineering, Waseda University, Japan), Xin Li (Waseda Research Institute for Science and Engineering, Waseda University, Japan), Akifumi Yamaji (Cooperative Major in Nuclear Energy, Graduate School of Advanced Science and Engineering, Waseda University, Japan)

Sept. 7 (Wed)
Room 1
Keynote 1 Sept. 7 (Wed.), 13:00 – 13:30, Room 1
Session Chair: Prof. Shao-Wen Chen (National Tsing Hua University, Taiwan)
Critical heat flux enhancement with micro/nano coated surfaces
Prof. Jiyun Zhao (City University of Hong Kong, China)
Keynote 4 Sept. 7 (Wed.), 13:30 – 14:00, Room 1
Session Chair: Prof. Shao-Wen Chen (National Tsing Hua University, Taiwan)
Initiating event detection and identification in nuclear power plants with data-driven techniques
Prof. Shun-Chi Wu (National Tsing Hua University, Taiwan)
Special Session I – Decommission Sept. 7 (Wed.), 14:15 – 15:35, Room 1
Session Chair: Dr. Chun-Ping Huang (Institute of Nuclear Energy Research, Taiwan)
Session Co-Chair: Dr. Sue-Ray Lin (Institute of Nuclear Energy Research, Taiwan)
N13P100 Applying the Phenomena Identification and Ranking Table (PIRT) for Maintenance strategy of the Decommissioning Nuclear Power Plant during Transition Period
Sue-Ray Lin, Hsoung-Wei Chou (Institute of Nuclear Energy Research, Taiwan)
N13P038 Thermal Analysis of Recirculation Line Break Accident for a Decommissioning Mark III plant
Yen-Shu Chen, Ansheng Lin, Li-Ying Huang (Institute of Nuclear Energy Research, Taiwan)
N13P105 The Dismantling Experience of TRR Removable Upper Biological Shield
Peng-Yu Chen (Institute of Nuclear Energy Research (INER), Taiwan)
N13P093 Feedback on the Decommissioning Experience of Taiwan Research Reactor
Chun-Ping Huang, Lun-Hui Lee, Ching Wei Yang (Institute of Nuclear Energy Research, Taiwan)
Special Session II – Decommission Sept. 7 (Wed.), 15:50 – 17:10, Room 1
Session Chair: Prof. Naoko Watanabe (Hokkaido University, Japan)
Session Co-Chair: Dr. Chung-Hao Huang (Department of Electrical Engineering, Chung Yuan Christian University)
N13P029 Application of Surface Contamination Detection for Nuclear Facility Decommissioning Waste Measurement
Shih-Hsuan Lin, Ping-Ji Huang (Institute of Nuclear Energy Research, Taiwan)
N13P103 A Snake-type Robotic Arm Used for Cleaning up Radioactive Wastes
Tzu-Chin Kuo, Chung-Hao Huang, Yu-Hsiang Lin, Sheng-Chang Cheng (Institute of Nuclear Energy Research, Taiwan)
N13P218 Development of Remote Inspection System using Advanced Super Dragon Articulated Robot Arm for Decommissioning of the Fukushima Daiichi Nuclear Power Plant
Hideharu Takahashi, Gen Endo (Tokyo Institute of Technology, Japan), Ikuo Wakaida (Japan Atomic Energy Agency, Japan), Susumu Ozaki, Hiroshige Kikura (Tokyo Institute of Technology, Japan)
N13P104 Estimation of decommissioning piping waste based on 3D model
Hao-jun Gao, Hsin-Hsien Huang, Peng-Yu Chen (Institute of Nuclear Energy Research, Taiwan)
N13P188 Dependence of Neutron Activation on Elemental Composition of Biological Shield Wall Concrete for the Purpose of Decommissioning
Ryoma Nishiyama (Hokkaido University, Japan), K. Tanaka (The Institute of Applied Energy, Japan), N. Watanabe, T. Kozaki (Hokkaido University, Japan), S. Uematsu, S. Yanagihara (Fukui University, Japan)
Special Session III – Spent Fuel Management Sept. 7 (Wed.), 17:25 – 18:45, Room 1
Session Chair: Dr. Tadas Kaliatka (Lithuanian Energy Institute, Lithuania)
Session Co-Chair: Dr. Kuei-Jen Cheng (Institute of Nuclear Energy Research, Taiwan)
N13P044 A Novel Method of Inspecting the Surface Condition of a Loaded Transportable Canister During Its Storage Operation
Kuei-Jen Cheng, Hsiao-Ming Tung, Ying-Wei Lin, Cheng-Fu Chen, Chien-Chou Lee (Institute of Nuclear Energy Research, Taiwan)
N13P062 The Preliminary Application of Discrete Fracture Network Model using dfnWorks and PFLOTRAN on Spent Fuel Disposal
Shiang-Lin Hsu, Yu-Hsiang Shen, Hao-Ting Chang, Chieh-Chun Chang (Institute of Nuclear Energy Research, Taiwan)
N13P114 Amendment 8 of Certificate of Compliance No.1015 NAC-UMS Dry Storage System: High Burnup and Damaged BWR Fuel
Chih-Hao Chen (Institute of Nuclear Energy Research, Taiwan) (National Taiwan University, Taiwan), George Carver (NAC International Inc., USA), Ching-Wei Yang (Institute of Nuclear Energy Research, Taiwan), Chih-Hao Fan (National Taiwan University, Taiwan), May Su (Institute of Nuclear Energy Research, Taiwan)
N13P187 RBMK-1500 Spent Fuel Characterization using SCALE and TRANSURANUS codes
Andrius Slavickas, Andrius Tidikas, Tadas Kaliatka (Lithuanian Energy Institute, Lithuania)
Computational Thermal-Hydraulics – V Sept. 7 (Wed.), 19:00 – 20:20, Room 1
Session Chair: Prof. Wen-Yu Wang (National University of Tainan, Taiwan)
Session Co-Chair: Dr. Yung Shin Tseng (National Tsing Hua University, Taiwan)
N13P155 Chloride-Induced Stress Corrosion Cracking Crack Growth Rate of Stainless Steel Canister for Concrete Cask under Marine Condition
Wen-Yu Wang, Yung-Shin Tseng, Tsung-Kuang Yeh (National Tsing Hua University, Taiwan)
N13P023 Modelling Joule Heating Method for Supercritical Heat Transfer with PCHIP Heat Flux Profile
Kwun Ting Lau, Chung Ki Cheng, Shahid Ali Khan (City University Of Hong Kong, China), Chika Michael Eze (Hong Kong Quantum AI Lab, China), Jiyun Zhao (City University Of Hong Kong, China)
N13P182 Numerical Study on the Effect of an Upstream Flow Disturbance on the Butterfly Valve’s Dynamic Performance
Gong Hee Lee, June Ho Bae (Korea Institute of Nuclear Safety, South Korea)
N13P211 Numerical Investigation of Flow Instabilities in vertical boiling channels via Multidimensional CFD Approach under Ocean Conditions
Jianping Long (School of Energy and Power Engineering, Xi’an Jiaotong University, China), Bao-Wen Yang (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer, Delta Energy Innovation Technology, China), Bin Zhang (School of Energy and Power Engineering, Xi’an Jiaotong University, China), Sipeng Wang (College of Materials Science and Technology, Nanjing University of Aeronautics and Astronautics, China)
N13P011 Numerically Evaluate Hydrated Residual Water Drying Process for Dry Storage System under Low Thermal Load Situation
Wen Yu Wang (Department of Engineering and System Science; National Tsing Hua University, Taiwan), Yung Shin Tseng (Nuclear Science and Technology Development Center; National Tsing Hua University, Taiwan), Chin Hung Lin (Refrigeration, Air-Conditioning and Energy Engineering; National Chin-Yi University of Technology, Taiwan), Yun-Ming Ferng (Department of Engineering and System Science; National Tsing Hua University, Taiwan), Ming-Shian Wan (Fuel Cycle and Materials Administration; Atomic Energy Council, Taiwan)
N13P216 Benchmark of RANS Simulations against LES for Helium Flow in Mini-zigzag Channels
Chengqi Wang (Department of Nuclear Engineering and Radiological Sciences, University of Michigan, United States), Koroush Shirvan (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, United States), Xiaodong Sun (Department of Nuclear Engineering and Radiological Sciences, University of Michigan, United States)
Room 2
Keynote 2 Sept. 7 (Wed.), 13:00 – 13:30, Room 2
Session Chair: Prof. Chul-Hwa Song (Korea Atomic Energy Research Institute, Korea)
Session Co-Chair: Prof. Jun Sun (Tsinghua University, China)
R&D of the HTR-PM and construction of the demonstration power plant
Prof. Dong Yujie (Tsinghua University, China)
Keynote 5 Sept. 7 (Wed.), 13:30 – 14:00, Room 2
Session Chair: Prof. Chul-Hwa Song (Korea Atomic Energy Research Institute, Korea)
Session Co-Chair: Prof. Jun Sun (Tsinghua University, China)
Thermal-Hydraulic Effect Test Validation for Nuclear Safety against Design Extension Conditions by utilizing Passive Safety Systems
Dr. Kyoung-Ho Kang (Korea Atomic Energy Research Institute (KAERI), Korea)
Computational Thermal-Hydraulics – IV Sept. 7 (Wed.), 14:15 – 15:35, Room 2
Session Chair: Prof. Antonio Cammi (Politecnico di Milano, Italy)
Session Co-Chair: Dr. Markus Junk (GRS, Germany)
N13P129 Simulation of the UPTF tests 5a and 8a using ATHLET 3.3
Markus Junk, Norman Dünne, Andreas Wielenberg (Gesellschaft für Anlagen- und Reaktorsicherheit (GRS), Germany)
N13P132 Simulation and Uncertainty Analysis of the RBHT Blind Tests with ATHLET 3.3
Norman Dünne, Tomasz Skorek, Philipp Schöffel (Gesellschaft Für Anlagen- Und Reaktorsicherheit (GRS), Germany)
N13P202 Hybrid Data Assimilation Methods: Application to the DYNASTY Experimental Facility
Stefano Riva, Antonio Cammi, Carolina Introini, Stefano Lorenzi (Politecnico Di Milano, Italy)
N13P086 Multiscale CFD Simulations for a Single-Phase Flow Stability under Natural Circulation in the Framework of System Scaling Uncertainty Evaluation
Haifu Huang (French Alternative Energies and Atomic Energy Commission, DEN, DER, France) (Aix-Marseille University IUSTI, UMR 6595 CNRS, France), Jorge Perez, Nicolas Alpy (French Alternative Energies and Atomic Energy Commission, DEN, DER, France), Marc Medale (Aix-Marseille University IUSTI, UMR 6595 CNRS, France)
Fundamental Thermal-Hydraulics – IV Sept. 7 (Wed.), 15:50 – 17:10, Room 2
Session Chair: Prof. Kuang C. Lin (National Tsing Hua University, Taiwan)
Session Co-Chair: Prof. Antonio Cammi (Politecnico di Milano, Italy)
N13P056 ATHENA integral test facility: secondary system design and thermal-hydraulic assessment with RELAP5 code
Tommaso Del Moro (Sapienza University of Rome, Italy), Pierdomenico Lorusso (ENEA, Department for Fusion and Technology for Nuclear Safety and Security, Italy), Fabio Giannetti (Sapienza University of Rome, Italy), Mariano Tarantino (ENEA, Department for Fusion and Technology for Nuclear Safety and Security, Italy), Marco Caramelllo (Ansaldo Nucleare S.p.A., Italy), Damiano Vitale Di Maio (S.R.S. Servizi di Ricerche e Sviluppo S.r.l., Italy), Marin Constantin (RATEN ICN, Institute for Nuclear Research, Romania)
N13P165 Development of an Improved Model Incorporating Vertical Length Effect under Dropwise Condensation Heat Transfer
Taeseok Kim, Sung Joong Kim (Hanyang University, South Korea)
N13P203 Preliminary 1D Modelling of the Coupled DYNASTY-eDYNASTY Experimental Facility
Gabriele Benzoni, Carolina Introini, Stefano Lorenzi, Antonio Cammi (Politecnico Di Milano, Italy)
N13P041 Numerical Simulation of Condensation Heat Transfer from Mixture of Super-Heated Steam and Air in a Vertical Tube
Michio Murase, Yoichi Utanohara (Institute Of Nuclear Safety System, Inc., Japan)
N13P209 Effects of Numerical Geometry Features-wire rod contact and Working Fluids on Flow and Thermal Fields of Wire-Wrapped in a 7 Pin Bundles
Bin Han (School of Energy and Environment, Southeast University, China), Aiguo Liu, Bao-Wen Yang (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer, China), Xiaoliang Zhu, Shenghui Liu (School of Energy and Environment, Southeast University, China), Xinyi Miao (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer, China)
Experimental Thermal-Hydraulics – IV Sept. 7 (Wed.), 17:25 – 18:45, Room 2
Session Chair: Prof. Shengfei Wang (North China Electric Power University, China)
Session Co-Chair Dr. khalid Khasawneh (Pusan National University, Korea)
N13P135 Experimental Study on the Blockage Effect on Local Droplet Parameters in a Rod Bundle Geometry Under Annular-Mist Flow
Khalid Khasawneh, T.H. Kim, J.Y. Bak, J.J. Jeong, B.J. Yun (Pusan National University, South Korea)
N13P082 The role played by dissolved gases during the gravity-driven flashing of superheated water in a spent fuel pool under loss of cooling conditions
Jimmy Martin (Institut de Radioprotection et de Sûreté Nucléaire (IRSN) PSN-RES/SEMIA/LSMA, France) (Institute of Mechanics, Materials and Civil engineering (iMMC) Université catholique de Louvain (UCLouvain), Belgium), Pierre Ruyer (Institut de Radioprotection et de Sûreté Nucléaire (IRSN) PSN-RES/SEMIA/LSMA, France), Matthieu Duponcheel, Yann Bartosiewicz (Institute of Mechanics, Materials and Civil engineering (iMMC) Université catholique de Louvain (UCLouvain), Belgium)
N13P109 Research on the Influence of Non-condensable Gas on Temperature Field and Pressure Fluctuation in Small Suppression Pool
Yili Yang, Liangyou Zhao, Yanhao Li, Ruiyang Tu, Chuzhen Peng, Tian Wang, Shengfei Wang (North China Electric Power University, China)
N13P033 Vibration Measurement of a Quarter-scale Integrated Modular Reactor Internals by Simulated Flow Circulation within the Pressure Vessel
Kanghee Lee, Heungseok Kang, Taesoon Kwon, Kyeonghun Jeong (Korea Atomic Energy Research Institute, South Korea)
Plant Operation, Diagnostics, Monitoring and Maintenance Sept. 7 (Wed.), 19:00 – 20:20, Room 2
Session Chair: Prof. Shun-Chi Wu (National Tsing Hua University, Taiwan)
Session Co-Chair: Dr. Yu Min Chen (National Tsing Hua University, Taiwan)
N13P128 Development of the Nuclear Power Plant Diagnosis Technique based on Deep Learning with Infrared Camera embedded Drone
Ik Jae Jin, In Cheol Bang (Ulsan National Institute of Science and Technology, UNIST, South Korea)
N13P192 Human Error Probability Quantification of Operator Mitigation Actions in a Loss of Offsite Power Sequence
Min Chuan Hsieh, Yu Min Chen, Sheng Yang, Min Lee (Institute of Nuclear Engineering and Science, National Tsing Hua University, Taiwan)
N13P037 Verification of Stress Intensity factor evaluation for Reactor Pressure Vessel Nozzles of domestic Nuclear Power Plants
Chih-Hsuan Lee, Hsoung-Wei Chou (Institute of Nuclear Energy Research, Taiwan)
N13P125 The combined effect of plastic deformation and thermal aging on the stress corrosion cracking susceptibility of CF8A stainless steels in simulated BWR coolant environments
Tai-Cheng Chen (Institute of Nuclear Energy Research, Taiwan, R.O.C ; National Taiwan University, Taiwan, R.O.C.), Wen-Feng Lu, Jiunn-Yuan Huang (Institute of Nuclear Energy Research, Taiwan, R.O.C), Ren-Kae Shiue (National Taiwan University, Taiwan, R.O.C.), Leu-Wen Tsay (National Taiwan Ocean University, Taiwan, R.O.C.)
Room 3
Keynote 3 Sept. 7 (Wed.), 13:00 – 13:30, Room 1
Session Chair: Prof. Xu Cheng (Karlsruhe Institute of Technology, Germany)
Expansion of safety research scope at the Nuclear Safety Research Center of JAEA based on the lessons learned from the Fukushima Daiichi NPS accident
Dr. Masaki Amaya (Japan Atomic Energy Agency (JAEA), Japan)
Keynote 6 Sept. 7 (Wed.), 13:30 – 14:00, Room 3
Session Chair: Prof. Xu Cheng (Karlsruhe Institute of Technology, Germany)
Multiphase CFD for Nuclear Safety Research
Dr. Dirk Lucas (Helmholtz-Zentrum Dresden – Rossendorf (HZDR), Germany)
Thermal-Hydraulics and Safety of Advanced Reactors – I Sept. 7 (Wed.), 14:15 – 15:35, Room 3
Session Chair: Dr. Cheng Peng (Shanghai University of Electric Power, China)
Session Co-Chair: Dr. Hidemasa Yamano (Japan Atomic Energy Agency, Japan)
N13P020 Numerical investigation on thermal-hydraulic performance in lead-based reactor with non-uniform heat flux
Jiyun Zhao, Kejian Dong, Sihong He (City University Of Hong Kong, China)
N13P120 Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors
(1) Project Overview and Progress Until 2020
Hidemasa Yamano, Toshihide Takai, Yuki Emura (Japan Atomic Energy Agency, Japan), Hiroyuki Fukuyama, Hideo Higashi (Tohoku University, Japan), Tsuyoshi Nishi, Hiromichi Ohta (Ibaraki University, Japan), Koji Morita (Kyushu University, Japan), Kinya Nakamura (Central Research Institute of Electric Power Industry, Japan), Horofumi Fukai, Masahiro Furuya (Waseda University, Japan), Zhenhan Hong, Nejdet Erkan, Marco Pellegrini (The University of Tokyo, Japan)
N13P193 Simulation of MYRRHA ADS Core Thermal Hydraulic Model Using RELAP5-3D
Chien-hsiang Chen, Liang-Che Dai (Institute of Nuclear Energy Research, Taiwan)
N13P163 Analysis on applicability of NACOM code on sodium spray fire
Dalong Qiao, Youya Song, Cheng Peng (Shanghai University of Electric Power, China)
N13P094 Feasibility Study on the Alternative Passive Safety Systems Actuated by Decompression of the Helium Bubbling System for the Passive Molten Salt Fast Reactor
Jihun Lim, Taesuk Kim, Jae Hyung Park, Juhyeong Lee, Won Jun Choi (Department of nuclear engineering, Hanyang University, Republic of Korea), Yonghee Kim (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Republic of Korea), Sangtae Kim (Department of nuclear engineering, Hanyang University, Republic of Korea), Sung Joong Kim (Department of nuclear engineering, Hanyang University, Republic of Korea) (Institute of Nano Science & Technology, Hanyang University, Republic of Korea)
Thermal-Hydraulics and Safety of Advanced Reactors – II Sept. 7 (Wed.), 15:50 – 17:10, Room 3
Session Chair: Prof. Tetsuaki Takeda (University of Yamanashi, Japan)
Session Co-Chair: Prof. Jun Sun (Tsinghua University, China)
N13P026 Experimental Validation of a Hydraulic Model Predicting the Control Rod Drop Curve of the High Flux Reactor
Fulvio Bertocchi, Izak de Kock, Paul A. Breijder, Niels Bosker (Nuclear Research and Consultancy Group, The Netherlands)
N13P196 Analysis of Randomly Distributed TRISO-coated Particles on the Effective Thermal Conductivity of Fuel Pebble in HTGR
Yue Song, Z. Liu, J. Sun (Institute of Nuclear And New Energy Technology, China)
N13P175 Heat Transfer and Fluid Flow Characteristic of Flow Channel for Applications of VHTR
Kosuke Osakabe (Integrated Graduate School of Medicine, Engineering, and Agricultural Sciences, University of Yamanashi, Japan), Tetsuaki Takeda (Graduate School of Engineering, University of Yamanashi, Japan)
N13P176 Study on mixing phenomena of two-component gases with different densities
Sohma Yoshida, T. Takeda (University of Yamanashi, Japan)
Small Module Reactors and Micro Reactors – I Sept. 7 (Wed.), 17:25 – 18:45, Room 3
Session Chair: Prof. Tadashi Narabayashi (Tokyo Institute of Technology, Japan)
Session Co-Chair: Prof. Min Lee (National Tsing Hua University, Taiwan)
N13P127 Performance Evaluation of the RVACS by Simulating Experiments Combination of Two Similarity Laws
Min Ho Lee (Ulsan National Institute Of Science And Technology (unist), South Korea), Dong Wook Jerng (Chung Ang University, South Korea), In Cheol Bang (Ulsan National Institute Of Science And Technology (unist), South Korea)
N13P179 Analysis of Transient Characteristics and Design Improvement of the Passive Residual Heat Removal System of NHR-200-II
Yiwa Geng, Xiong-Bin Liu (Institute of Nuclear and New Energy Technology, Tsinghua University, Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, China)
N13P107 Numerical Investigation of Thermal Radiation Shielding Effects in Small Modular Reactor with Double-vessel Structure during Normal Operation Conditions
Geon Hyeong Lee, Taeseok Kim, Joongoo Jeon (Hanyang University, South Korea), Yonghee Kim (Korea Advanced Institute of Science and Technology, South Korea), Sung Joong Kim (Hanyang University, South Korea)
N13P133 Flow Blockage Analysis of the Fuel Assembly in a Conceptual Micro-marine Liquid Metal-cooled Fast Reactor
Joo Hyung Seo, J. Y. Kim, I. C. Bang (Ulsan Ulsan National Institute of Science and Technology, South Korea)
N13P169 New useful SMR for load follow with fluctuating renewable energy and enhance facilitates for stable grid control
Tadashi Narabayashi, Tran Vien, Hideharu Takahashi, Hiroshige Kikura (Tokyo Institute Of Technology, Japan)
Small Module Reactors and Micro Reactors – II Sept. 7 (Wed.), 19:00 – 20:20, Room 3
Session Chair: Prof. Xiang Wang (Harbin Engineering University, China)
Session Co-Chair: Prof. Chin Pan (City University of Hong Kong, China)
N13P160 District Heating Reactor LDR-50: Thermal-Hydraulic Analysis of Difficult Load Following Cases
Rebekka Komu, Seppo Hillberg, Tomi J. Lindroos, Jaakko Leppänen (VTT Technical Research Centre of Finland, Finland)
N13P045 Analysis of the Bending Effect of Heat Pipe for Nuclear Reactor Application
Ye Yeong Park, In Cheol Bang (Ulsan National Institute of Science and Technology, South Korea)
N13P136 Constructions of Experiments and Filing Facility of High Temperature Heat Pipe for Nuclear Applications as an Indefinite Cooling
DongHun Lee, In Cheol Bang (Ulsan National Institute of Science and Technology, South Korea)
N13P024 Physical Performance Study of Depletion Features for the Liquid-Fuel Heat-Pipe Reactor
Xuesong Bai, Xiang Wang (Harbin Engineering University, China)
N13P150 NuScale SMR 3-D Modelling and Applied Safety Analyses with the System Code ATHLET in the Framework of the EU H2020 McSAFER
Eduard Diaz-Pescador, Sören Kliem, Matthias Jobst (Helmholtz-Zentrum Dresden Rossendor (HZDR), Germany)
Room 4
Safety and Severe Accidents- IV Sept. 7 (Wed.), 14:15 – 15:35, Room 4
Session Chair: Prof. Huai-En Hsieh (Xiamen University, China)
Session Co-Chair: Prof. Min Lee (National Tsing Hua University, Taiwan)
N13P055 Three-Dimensional Analyses of the FARO L-26S Melt Spreading Experiment by MPS Method
Sara Honda, Takanari Fukuda (School of Advanced Science and Engineering, Waseda University, Japan), Guangtao Duan (The University of Tokyo, Japan), Akifumi Yamaji (School of Advanced Science and Engineering, Waseda University, Japan)
N13P214 CFD Simulation of Ablation Behaviour of Sacrificial Material in a Scaled down Ex-vessel Core Catcher Model
Samyak Munot, Arun Nayak (Homi Bhabha National Insitute, India) (Reactor Technology Division, Reactor Design and Development Group, Bhabha Atomic Research Centre, India)
N13P213 Numerical Simulation of Simulated Molten Corium Coolability in a Scaled down Ex vessel Core Catcher Model with Decay Heat
Samyak Munot, Arun Nayak (Homi Bhabha National Insitute, India) (Reactor Technology Division, Reactor Design and Development Group, Bhabha Atomic Research Centre, India)
N13P066 The Experiment of Critical Heat Flux Enhancement by Graphene Nanofluids Applications for External Reactor Vessel Cooling
Shiqi Wang, Huai-En Hsieh, Zhibo Zhang, Jia Gao (College of Energy, Xiamen University, China)
N13P087 Analysis of Venturi Scrubber Approaches regarding different Nozzle Geometries
Jonas Michael Rehrmann, Tobias Jankowski, Marco K. Koch (Ruhr Universität Bochum, Germany)
Safety and Severe Accidents- V Sept. 7 (Wed.), 15:50 – 17:10, Room 4
Session Chair: Dr. Sanjeev Gupta (Becker Technologies GmbH, Germany)
Session Co-Chair: Dr. Stephan Kelm (Forschungszentrum Juelich GmbH, Germany)
N13P081 Experimental Investigation on the Interaction Behavior of Nuclear Aerosols with Cable Fire Products
Yihui Wu (RWTH Aachen University, Germany), Michael Alexander Klauck (Forschungszentrum Jülich GmbH, Germany), Hans-Josef Allelein (RWTH Aachen University, Germany) (Forschungszentrum Jülich GmbH, Germany)
N13P191 Recent Progress and Perspective of Hydrogen Safety Research – Outcomes of Selected International Activities
Sanjeev Gupta (Becker Technologies Gmbh, Germany), Ahmed Bentaib (Institut de Radioprotection et de Sûreté Nucléaire, France), Haseeb ur Rehman, Tatjana Jevremovic (International Atomic Energy Agency, Austria)
N13P189 CFD simulation of thermal behavior in a Nordic BWR pressure suppression pool
Xicheng Wang, Dmitry Grishchenko, Pavel Kudinov (Royal Institute Of Technology, Sweden)
N13P158 Technical Scale CFD Analysis of the Pressurization and Transport Processes in the Battelle Model Containment during the ISP-37 VANAM M3 Test
Stephan Kelm (Forschungszentrum Juelich Gmbh, Germany), G. Vijaya Kumar (Forschungszentrum Juelich Gmbh, Germany) (Indian Institute of Technology Madras, India), Manohar Kampili,Xiongguo Liu (Forschungszentrum Juelich Gmbh, Germany), Ruijun Ji (Forschungszentrum Juelich Gmbh, Germany, Bundeswehr University Munich, Germany), Liam Cammiade (Forschungszentrum Juelich Gmbh, Germany, RWTH Aachen University, Germany), Allen George (Forschungszentrum Juelich Gmbh, Germany, Karlsruhe Institute of Technology, Germany), K. Arul Prakash (Indian Institute of Technology Madras, India), Hans-Josef Allelein (Forschungszentrum Juelich Gmbh, Germany)
Safety and Severe Accidents-VI Sept. 7 (Wed.), 17:25 – 18:45, Room 4
Session Chair: Prof. Hsingtzu Wu (Huazhong University of Science and Technology, China)
Session Co-Chair: Prof. Chih-Hung Lin (National Chin-Yi University of Technology, Taiwan)
N13P065 The Investigation of Boiling Heat Transfer Capabilities by different SiO2 nanofluids Mixing Conditions on a Downward-Facing Plane
Zhibo Zhang, Huai-En Hsieh, Shiqi Wang, Jia Gao (College of Energy, Xiamen University, China)
N13P040 Conceptual Design of Decay Heat Passive Cooling System for Spent Fuel Pool with Heat Pipes and Air Cooling Tower: Transient Calculation of Thermal Capacity during both Occasions of Normal and Accident Operation
Min Suk Lee, Wooseong Park, Yong Hoon Jeong (Korea Advanced Institute Of Science And Technology, South Korea)
N13P197 Two-dimensional Numerical Simulation of Rayleigh-Taylor Instabilities in Immiscible Fluids using the Phase-Field Model of TrioCFD Code
Mirantsoa Aimé Rasolofomanana (French Alternative Energies And Atomic Energy Commission, France) (Ecole Polytechnique, France), Romain Le Tellier (French Alternative Energies And Atomic Energy Commission, France), Hervé Henry (Ecole Polytechnique, France)
N13P159 Sensitivity Analysis of a Spiral-shaped Tube for Passive Residual Heat Removal Heat Exchanger
Hsingtzu Wu, Linfeng Yen (Huazhong University Of Science And Technology, China)
N13P200 Pilot Numerical Study of Proposed Modification of the Surface of the Containment Dome to Enhance Condensation
Hsingtzu Wu, Li Zhou, Dawei Wang (Huazhong University Of Science And Technology, China)
Safety and Severe Accidents- VII Sept. 7 (Wed.), 19:00 – 20:20, Room 4
Session Chair: Prof. Wei Wang (City University of Hong Kong, China)
Session Co-Chair: Dr. Thorsten Hollands (Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany)
N13P092 Development of a classification model to group source term category of accident sequences by using recurrent neural network
Chang Hyun Song, Wonjun Choi, Joon Young Bae, Sung Joong Kim (Hanyang University, South Korea)
N13P148 Validation of the Fission Product Transport Module in the Code System AC2 2021.
Livia Tiborcz, Sara Beck, Peter Pandazis, Thorsten Hollands (Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany)
N13P215 A method for inherently fault tolerant control of nuclear power plants using combined feedforward and feedback control
Muthuraj T, John Arul (Indira Gandhi Centre For Atomic Research, India)
N13P111 The Thermal Analysis of Pre-Defueled Operation for Decommissioning of a BWR/6 Reactor
Ben-Bo Xiao, Yu-Wen Wang (Institute of Nuclear Energy Research, Taiwan)

Sept. 8 (Thu)
Room 1
Special Session-Development and Prospect of Nuclear Backend Sept. 8 (Thu), 13:00 – 15:00, Room 1
Session Chair: Dr. Ching-Tsuen Huang (Atomic Energy Council (AEC), Taiwan) (Chung-Hwa Nuclear Society (CHNS), Taiwan)
Special Session-Development and Prospect of Nuclear Backend – I The Developments towards Final Disposal of Spent Nuclear Fuel and High Level Waste in Europe
Mr. Hans Forsstrom (SKB International) (Nuclear Fuel Cycle and Waste Technology, IAEA)
Special Session-Development and Prospect of Nuclear Backend – II Construction of Beishan Underground Research Laboratory for Geological Disposal of High Level Radioactive Waste in Chinese Mainland
Dr. Ju Wang (Beishan Underground Research Laboratory for HLW Disposal ; President, ISRM Commission on Radioactive Waste Disposal, Beijing Research Institute of Uranium Geology, China))
Special Session-Development and Prospect of Nuclear Backend – III Overview of Disposal in Boreholes
Mr. Rod Baltzer (Deep Isolation, United States)
Panel Discussion-SMR and Micro Reactors Sept. 8 (Thu), 15:20 – 17:20, Room 1
Host: Prof. Per Peterson (University of California, Berkeley, USA)
Co-Host: Prof. Yong Hoon Jeong (Korea Advanced Institute of Science and Technology (KAIST), Korea)
Panelists: Prof. Tadashi Narabayashi (Tokyo Institute of Technology, Japan)
Panelists: Prof. Xiang Wang (Harbin Engineering University, China)
Panelists: Prof. Yonghee Kim (Korea Advanced Institute of Science and Technology (KAIST), Korea)
Room 2
Fundamental Thermal-Hydraulics – V Sept. 8 (Thu), 13:00 – 15:00, Room 2
Session Co-Chair: Dr. Wen-Sheng Hsu (National Tsing Hua University, Taiwan)
Co-Chair: Prof. Sipeng Wang (Nanjing University of Aeronautics and Astronautics, China)
N13P217 Analysis of flow and heat transfer characteristics of annular fuel 2*2 bundle with spacer grid
Sipeng Wang (Nanjing University of Aeronautics and Astronautics, China) (Ministry of Industry, China), Qindong Zhang, Mingwei Li (Nanjing University of Aeronautics and Astronautics, China), Bao-Wen Yang (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer, China)
N13P130 Investigations of the Effect of Flow Oscillations and Flow Channel Orientation on the Occurrence of Boiling Crisis
Stelios Michaelides, Xu Cheng (Institute for Applied Thermofluidics (IATF), Karlsruhe Institute of Technology, Germany), Stephan Gabriel (Institute for Thermal Energy Technology and Safety (ITES), Karlsruhe Institute of Technology, Germany)
N13P199 Principle Component Analysis-based Feature Extraction for Identification of Two-phase Flow Pattern in Porous Media
Wenjie Wang, Liangxing Li, Xiangyu Li, Jiayuan Zhao, Haoxiang Zhao (State Key Laboratory of Multiphase Flow in Power Engineering, Xi’an Jiaotong University, China)
N13P054 Extension of a differential heat flux transport model to low Prandtl flows through Bayesian optimization and neural network regression
Matilde Fiore, Lilla Koloszar, Miguel Alfonso Mendez (Von Karman Institute For Fluid Dynamics, Belgium), Yann Bartosiewicz (Université catholique de Louvain, Belgium)