Conference Agenda

OECD/NEA Benchmark on Artificial Intelligence and Machine Learning for Critical Heat Flux Predictions – Summary of Phase 1 Results

Jean-Marie Le Corre¹, Gregory K. Delipei², Xu Wu², Xingang Zhao³, Oliver Buss⁴

1: Westinghouse Electric Sweden AB, Sweden; 2: North Carolina State University, United States of America; 3: University of Tennessee, United States of America; 4: Nuclear Energy Agency, France

AI-informed Parameter Selection for Critical Heat Flux Prediction Models: Revisiting the Role of Inlet Conditions

Evgeny Nikitin, Sören Kliem

Helmholtz-Zentrum Dresden-Rossendorf, Germany

Assessment of the State-of-the-Art AI Methods for Critical Heat Flux Prediction

Wen Zhou, Shuichiro Miwa, Hanyu Wang, Koji Okamoto

The University of Tokyo, Japan

Deep Learning for Critical Heat Flux Regression through an Increasing-complexity Approach

Gabriele Cassetta, Lucia Sargentini, Alberto Ghione, Guillaume Damblin

CEA, France

A Data-informed Continuous Machine Learning Approach for CHF Prediction

Meiqi Song^1,2, Fabian Wiltschko², Xiaojing Liu¹, Aurelian Florin Badea², Xu Cheng²

1: Shanghai Jiao Tong University (SJTU), China, People's Republic of; 2: Karlsruhe Institute of Technology (KIT),Germany

Use of PINNs to Improve CHF Model Behaviour

Yi Meng Chan

KTH, Sweden

Probabilistic/Interpretable Neural Network Frameworks for Flow Boiling CHF Prediction in Circular Tubes

Kyung Mo Kim¹, Juhyung Lee², Mooneon Lee², Hyuk Kwon², Han Seo²

1: Korea Institute of Energy Technology (KENTCH), Korea, Republic of; 2: Korea Atomic Energy Research Institute (KAERI), Korea, Republic of

Critical Heat Flux Prediction in Round Tubes Using AI/ML: A Comparison of XGBoost and MLP Models

Mooneon Lee¹, Juhyung Lee¹, Hyuk Kwon¹, Dae-Hyun Hwang¹, Kyung Mo Kim²

1: Korea Atomic Energy Research Institute, Korea, Republic of; 2: Korea Institute of Energy Technology, Korea, Republic of

Evaluating the Performance of Diffusion Models for Scientific Data Augmentation - a Case Study with Critical Heat Flux

Farah Raed Hussein Alsafadi, Xu Wu

North Carolina State University, United States of America

A Comparative Study of Large Language Model Agents for Data-Driven Critical Heat Flux Prediction

Yang Liu, Zaid Abulawi, Abhiram Garimidi, Lim Doyeong

Texas A&M University, United States of America

Aided Active Learning (AAL) for Enhanced Critical Heat Flux Prediction

Umme Mahbuba Nabila¹, Mohammed I. Radaideh¹, Logan Burnett¹, Linyu Lin², Majdi I. Radaideh¹

1: University of Michigan, United States of America; 2: Idaho National Laboratory, United States of America

Evaluation of the Machine Learning CHF Model Enhanced COBRA-TF Prediction Performance

Congshan Mao, Yue Jin

University of Missouri, United States of America

Prediction of Critical Heat Flux with Hybrid Machine Learning: Uncertainty Quantification and CTF Deployment

Aidan John Furlong¹, Xingang Zhao², Robert K. Salko³, Xu Wu¹

1: North Carolina State University, United States of America; 2: University of Tennessee, Knoxville, United States of America; 3: Oak Ridge National Laboratory, United States of America

A Data-Driven Approach to Critical Heat Flux: An ML-Based Method

Marcello Savini¹, Mattia Massone²

1: UNIBO/ENEA, Italy; 2: ENEA, Italy

Design and Development of AI-Driven Autonomous Control Testbed for Small-Scale Advanced Nuclear Reactors

Doyeong Lim, Zavier Ndum Ndum, Yassin Hassan, Yang Liu

Texas A&M University, United States of America

Integrated CFD Model for Entire eVinci™ Test Reactor Thermal System

Hong Xu, Yizhou Yan, Oriol Noguera Oliva, Liping Cao

Westinghouse, United States of America

Development and Evaluation of a Machine Learning-based Drift-flux Model in Molten Salt Bubbly Flow

Tristan Reynaldo Villarreal, Ethan Rozak, Cole Gentry, Benjamin Collins, Kevin Clarno

University of Texas at Austin, United States of America

Preliminary CFD Benchmarking of Machine Learning Algorithms for Korean Virtual Small Modular Reactor

Minseo Lee¹, Joongoo Jeon¹, Sangam Khanal¹, Shilaj Baral¹, Chaehyeon Song², Minseop Song², Sunwoong Yang³, Namwoo Kang^3,4, Heesun Choi⁵, Yonggyun Yu⁵

1: Jeonbuk National University, Korea, Republic of; 2: Hanyang University, Korea, Republic of; 3: Korea Advanced Institute of Science and Technology, Korea, Republic of; 4: Narnia Labs, Korea, Republic of; 5: Korea Atomic Energy Research Institute, Korea, Republic of

Generative AI-based Agentic Framework for the Formulation of Phenomena Identification and Ranking Table for Advanced Reactor Application

Paridhi Athe, Nam Dinh

North Carolina State University, United States of America

Application of Intelligent Design Technologies for Nuclear Reactor Thermal-Hydraulics

Qi Lu^1,2, Qingyu Huang^1,2, Baotong Li³, Jian Deng^1,2, Wei Zeng^1,2, Zhifang Qiu^1,2, Jia Liu^1,2, Wenbin Han^1,2

1: State Key Laboratory of Advanced Nuclear Energy Technology, China, People's Republic of; 2: Nuclear Power Institute of China, China, People's Republic of; 3: Key Laboratory of Education Ministry for Modern Design & Rotor-Bearing System, Xi’an Jiaotong University, China, People's Republic of

Multiphysics Coupling in Nuclear Reactors: A Physics-Informed Neural Network Framework

Hongtao Bi^1,2, Meiqi Song^1,2, Xiaojing Liu^1,2

1: Shanghai Digital Nuclear Reactor Technology Integration Innovation Center, China, People's Republic of; 2: Shanghai Jiao Tong University, China, People's Republic of

Efficient Reliability Assessment of EHRS in IRIS Reactor under LOCA using Physics-Informed Neural Networks (PINNs)

Xi Yuan, Lanxin Gong, Tianze Bai, Changhong Peng

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

Developing a Real-time Surrogate Model with POD-PINN approach for the Flow Field in the Main Coolant Pump of Lead-Cooled Fast Reactors

Yiwen Guo¹, Liangxing Li¹, Kailin Wang^1,2, Zutao Xiang¹, Jiabin Gui¹, Shang Shi¹, Zhenxin Lei¹, Xiangyang Xu¹, Xiaorong Jia¹

1: Xi’an Jiaotong University, China, People's Republic of; 2: Tokyo Institute of Technology, Japan

Sparsity-Promoting Regularization and Uncertainty Quantification for Heat Source Identification in Conjugate Heat Transfer System

Haeseong Kim¹, Sacit Cetiner^2,3, Matteo Bucci¹

1: Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, United States of America; 2: Idaho National Laboratory, United States of America; 3: INL/MIT Center for Reactor Instrumentation and Sensor Physics, MIT Nuclear Reactor Laboratory, United States of America

Toward Improved NekRS Case Setup Workflow with AI-powered Chatbot

Tri Nguyen¹, Luiz Aldeia Machado¹, Elia Merzari¹, Arsen Iskhakov²

1: Penn State University, United States of America; 2: Kansas State University, United States of America

High-fidelity Temperature Field Prediction for Upper Plenum and Hot Legs of PWR Using CFD and Non-intrusive Reduced-order Method

Yanjie Kang¹, Qingyu Huang², Yuan Zhou¹, Yuan Yuan¹

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

Acceleration of the Convergence of a Core Thermo-hydraulic Code Using Initialization from a Neural Network

Gauthier Lazare^1,2, Corentin Coudroy¹, Philippe Helluy², Erwan Le Coupanec¹, Qingqing Feng¹, Frank Hulsemann¹, Stéphane Pujet¹, Pauline Rotach¹

1: EDF, France; 2: IRMA, France

Model Calibration and Acceleration Techniques Based on Artificial Bee Colony Algorithm

Shubiao Dong, Xiaoyu Zhang, Qianping Zhang

China Nuclear Power Operation Technology Corporation, Ltd, China, People's Republic of

Thermal-Hydraulic Model Development for Semi-Circular Zigzag Channel PCHEs Based on Machine Learning

Shuai Che, Adam Burak, Xiaodong Sun

University of Michigan, United States of America

ANN-based Approach for Two-phase Model Development and Implementation in Thermal-hydraulic Codes

Van Thai Nguyen¹, Ngoc Dat Nguyen²

1: Hanoi University of Science and Technology, Vietnam; 2: Chungnam National University, Korea, Republic of

Thermal Stratification Prediction in Reactor System Based on CFD Simulations Accelerated by A Data-driven Coarse-grid Turbulence Model

Zijing Liu, Pengcheng Zhao, Yanan Zhao, Wei Deng, Tao Yu, Jinsen Xie

University of South China, China, People's Republic of

Flashing Induced Instabilities in a Forced Circulation Loop under Low Pressure and Low Power Conditions

Karim Mohammed Abdalwaged Yassin, Carlos Alberto Dorao, Maria Fernandino

Norwegian university of Science and Technology (NTNU), Norway

Theoretical Analysis of Two-Phase Flow Instability in Once-through Steam Generator Using Drift Flow Model

Yang Su, Xiaowei Li, Hongyi Fan, Xinxin Wu, Xiaowei Luo

Tsinghua University, China, People's Republic of

Theoretical Model of Water Jet Instability and Phase Change Steam Expansion during SGTR in Lead-cooled Fast Reactor

Ruiqi Bao, Li Liu, Hanyang Gu

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

The Study of Transient Heat Transfer Mechanisms and Two-Phase Flow during Post Flow Instability Dryout Accident

Yosef Aharon¹, Almog Chakmon^1,2, Gennady Ziskind²

1: NRCN, Israel; 2: Ben Gurion University, Israel

Defining Axial Void Fraction and Flashing Details from Pressure Profiles in Two-phase Critical Flow Discharges Made in CRAFTY Facility

Lauri Pyy, Giteshkumar Patel, Silja Oksanen, Juhani Hyvärinen

LUT University, Finland

A Study on the Phase State Measurement Method for Gas-liquid Two-phase Flow in a Tube during SCO₂ Loss-of-pressure Flash Vaporization

Junjie Yuan, Li Liu, Hanyang Gu

Shanghai Jiaotong University, China, People's Republic of

Experimental Validation of Identified Dimensionless Pitch Parameter of Additively Manufactured Helically Rifled Tubing for Molten Salt Heat Exchangers

Ryan Patrick McGuire, Lane Carasik, Andrew Hutsell, James Vulcanoff, Sierra Tutwiler

Virginia Commonwealth University, United States of America

Experiments on Thermal Stratification at Horizontally Oriented Pipeline-Elbows

Zhongkang Ma, Mi Zhou, Naiqiang Zhang

North China Electric Power University, China, People's Republic of

Flow Pattern Transition and Separation Performance of Swirl-Vane Separator in Small Modular Reactors

Luyun Mao, Nan Gui

Tsinghua University, China, People's Republic of

Comparison of MARS-KS and SPACE Code for Simulating a Helical Steam Generator Two-phase Instability

Junha Hwang, Seunghwan Oh, Jeong Ik Lee, Doh Hyeon Kim, Semin Joo, Taeyeon Min

Korea Advanced Institute of Science and Technology, Korea, Republic of

Experimental and Numerical Investigation on the Resistance Characteristics of the New Throttling Device for Steam Generators

Bo Wang^1,2, Yukang Liu¹, Yin Fang², Xianliang Lei², Yanfang Liu¹, Runze Liu², Xinyang Guo²

1: Dongfang Electric Co.Ltd., China, People's Republic of; 2: Xi’an Jiaotong University, China, People's Republic of

Study of Reactor Core Residual Heat Removal Schematic

Jiaming Zhao, Rui Zhang, Xiaoxia Chen, Nianzhe Zhang, Xiangyu Chi

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

Verification of the Reflectivity of the Boundary Surface Regarding the Development of Water Level Measurement Technology Using Ultrasound

Takahiro Ito¹, Kohei Kikuchi¹, Weichen Zhang¹, Hiroshige Kikura¹, Daisuke Sasa², Takeshi Suzuki²

1: Laboratory for Zero-Carbon Energy, Institute of Science Tokyo, Japan; 2: Tokyo Electric Power Company Holdings, Inc., Japan

Variational Bayesian Last Layer Augmented Recurrent Neural Networks for Transient Thermal Hydraulic Experiments

Logan Alexander Burnett¹, Umme Nabila¹, Izabela Gutowska², Majdi Radaideh¹

1: University of Michigan Ann Arbor, United States of America; 2: Oregon State University, United States of America

BF-GAN: Development of an AI-driven Bubbly Flow Image Generation Model Using Generative Adversarial Networks

Wen Zhou¹, Shuichiro Miwa¹, Yang Liu², Koji Okamoto¹

1: The University of Tokyo, Japan; 2: Virginia Tech, United States of America

Extracting Bubble Information in Nucleate Boiling Using a Deep Learning Approach

Ungjin Na¹, Bruno Pinheiro Serrao², Junyoung Seo³, Youngjoon Suh⁴, Hangjin Jo^1,3, Juliana Pacheco Duarte², Yoonjin Won⁴

1: Department of Mechanical Engineering, Pohang University of Science and Technology (POSTECH), Korea, Republic of; 2: University of Wisconsin-Madison, United States of America; 3: Division of Advanced Nuclear Engineering, Pohang University of Science and Technology (POSTECH), Korea, Republic of; 4: University of California, United States of America

A Holistic Segmentation of Boiling Heat Transfer Features Using U_NET based Convolutional Neural Network

Hyoung Suk Yu¹, Matthew Hughes³, Gustavo Matana Aguiar³, Guanyu Su*², Matteo Bucci³, Yong Hoon Jeong¹

1: Korea Advanced Institute of Science and Technology, Korea, Republic of; 2: University of California Berkeley, United State of America; 3: Massachusetts Institute of Technology, United State of America

A Novel Parametric Proper Orthogonal Decomposition Framework for Thermal-Hydraulic Simulations of Once-Through Steam Generators

Yifan Xu¹, Introini Carolina², Riva Stefano², Xiaobo Zeng¹, Minjun Peng¹, Chenyang Wang¹, Genglei Xia¹, Cammi Antonio^3,2

1: Harbin Engineering University, China, People's Republic of; 2: Politecnico di Milano, Italy; 3: Khalifa University, United Arab Emirates

Accelerating Microreactor Deployment with Hardware-in-the-Loop Augmented Digital Twin

Austin Michael Warren, Trevor Kent Howard

Oregon State University, United States of America

Transient Response of a Vertical Low-Temperature Heat Pipe

Ilyas Yilgor, Sungbeen Park, Shanbin Shi

Rensselaer Polytechnic Institute, United States of America

Design and Experimental Analysis of Intermediate Heat Exchanger for Heat Pipe Cooled Reactor Using Fiber Optic Sensor

Yongnam Lee¹, Suwon Lee¹, HangJin Jo^1,2

1: Division of Advanced Nuclear Engineering, Pohang University of Science and Technology, Korea, Republic of; 2: Department of Mechanical Engineering, Pohang University of Science and Technology, Korea, Republic of

Verification and Validation of 2-D Transient Heat Pipe Thermal Analysis Code with Melting/Solidification Model

Ye Sung Kim, Myung Jin Jeong, Hyoung Kyu Cho

Seoul National University, Korea, Republic of

Multi-physics Coupled Analysis of the Heat Pipe-cooled Reactor Based on OpenFOAM

Zeqin Zhang, Ruiyu Han, Chenglong Wang, Cheng Chen, Cheng Wang, Haocheng Zhao, Kailun Guo, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su

Department of Nuclear Science and Technology, State Key Laboratory of Multiphase Flow Engineering, Shaanxi Key Lab of Advanced Nuclear Energy and Technology

Development of a Machine Learning Model for Predicting the Long-term Coolability of Ex-vessel Debris Beds for Extension of Systemcode Modelling

Nicole Richter, Juliane Neuhaus, Marco K. Koch

Ruhr-Universität Bochum, Germany

Shallow Recurrent Decoders for State Estimation in Parametric Accidental Scenarios of Circulating Fuel Nuclear Reactors

Stefano Riva¹, Carolina Introini¹, J. Nathan Kutz², Antonio Cammi^1,3

1: Politecnico di Milano, Italy; 2: University of Washington, United States of America; 3: Khalifa University, United Arab Emirates

Development of an Auxiliary Surrogate Model for Refined Prediction of Severe Accident Progression: Oscillation Prediction Model

Taeyeon Min¹, Semin Joo¹, Seok Ho Song¹, Jeong Ik Lee¹, Mi Ro Seo²

1: KAIST, Korea, Republic of; 2: KHNP CRI, Korea, Republic of

Development of Surrogate Model for Reactor Cooling System based on ASTEC Simulations during the Early Phase of Station Blackout

Christophe D'Alessandro¹, Terttaliisa Lind¹, Seolsonghwa Song²

1: Paul Scherrer Institute, Switzerland; 2: Chung-Ang University, Korea, Republic of

Break Size Prediction Model for Small Modular Reactors Based on Explainable Artificial Intelligence and Hyperparameter Optimization

Dingyu Jiang, Hexin Wu, Zhenlan Wang, Junli Gou, Jianqiang Shan

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

Safety Evaluation of Multiple Steam Generator Tube Rupture Events with BEPU Analysis and Explainable AI

Tran Nguyen¹, Aya Diab²

1: Dalat Nuclear Research Institute, Dalat, Vietnam; 2: Ain Shams University, Cairo, Egypt

Enhanced Anomaly Detection in Liquid Sodium Cold Trap Operation with Synchronization of Time Series of Multi-Modal Sensors

Alexandra Gabrielle Akins^1,2, Xu Wu², Derek Kultgen¹, Alexander Heifetz¹

1: Argonne National Laboratory; 2: North Carolina State University

Sensor Data Prediction in the High Temperature Test Facility with Recurrent Neural Networks

Farhana Farha¹, Meredith Eaheart¹, Izabela Gutowska², Brendan Kochunas¹, Majdi Radaideh¹

1: University of Michigan, United States of America; 2: Oregon State University, United States of America

Verification and Validation of Shallow Recurrent Decoders for State Estimation in the DYNASTY Facility

Stefano Riva¹, Andrea Missaglia¹, Carolina Introini¹, J. Nathan Kutz², Antonio Cammi^1,3

1: Politecnico di Milano, Italy; 2: University of Washington, United States of America; 3: Khalifa University, United Arab Emirates

Toward Developing Machine-Learning-Aided Tools for the Thermomechanical Monitoring of Nuclear Reactor Components

Luiz Carlos Aldeia Machado¹, Victor Coppo Leite¹, Elia Merzari¹, Roberto Ponciroli², Lise Charlot³, Lander Ibarra², Arthur Motta¹

1: The Pennsilvanya State University, United States of America; 2: Argonne National Laboratory, United States of America; 3: Idaho National Laboratory, United States of America