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Proceedings Papers

Machine Learned Metamodeling of a Computationally Intensive Accident Simulation Code

Landon Conner, Clarence L. Worrell, James P. Spring, Jun Liao

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A035, August 4–6, 2021

Paper No: ICONE28-66619

DOI: https://doi.org/10.1115/ICONE28-66619

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Topics: Accidents, Machinery, Metamodeling, Simulation, Artificial neural networks, Machine learning, Manufacturing, Nuclear industry, Optimization, Safety

Proceedings Papers

Apros-Based Loviisa NPP Full Scope Training Simulator and Engineering Model

Arttu Meriläinen, Olli Viljakainen, Karri Honkoila, Ari Lahtela

Paper No: ICONE28-64294

DOI: https://doi.org/10.1115/ICONE28-64294

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Topics: Engineering models, Nuclear power stations, Accidents, Circuits, Accident management, Computer software, Containment, Design, Diesel generators, Electronic systems

Proceedings Papers

A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform

Biheng Xie, Chengzhi Ji, Xiaoyu Guo, Wenbin Han, Yisheng Hao, Junyi Chen, Shanfang Huang, Kan Wang, Hongbin Wei, Yanming Liang

Paper No: ICONE28-64532

DOI: https://doi.org/10.1115/ICONE28-64532

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Topics: Simulation, Teaching, Very high temperature reactors, Accidents, Nuclear engineering, Nuclear industry, Students, Boilers, Control systems, Design

Proceedings Papers

RELAP5 Code Analyses of PKL-4 Project Test on PWR Multiple Steam Generator Tube Rupture Accident With Recovery Actions

Masashi Sekine, Junichi Kaneko, Takeshi Takeda

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A009, August 4–6, 2021

Paper No: ICONE28-64117

DOI: https://doi.org/10.1115/ICONE28-64117

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Topics: Accidents, Boilers, Pressurized water reactors, Rupture, Damage, Cooling, Earthquakes, Emergency core cooling systems, Failure, Feedwater

Proceedings Papers

UHT Test Facility Updates and Oxidation Tests for Accident Tolerant Fuel Development

William A. Byers, Guoqiang Wang

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A042, August 4–6, 2021

Paper No: ICONE28-66592

DOI: https://doi.org/10.1115/ICONE28-66592

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Topics: Accidents, Fuels, High temperature, Oxidation, Test facilities, Zirconium alloys

Proceedings Papers

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Guoqiang Wang, William A. Byers, Zeses Karoutas

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A041, August 4–6, 2021

Paper No: ICONE28-66591

DOI: https://doi.org/10.1115/ICONE28-66591

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Topics: Accidents, Cladding systems (Building), Critical heat flux, Fuels, Chemistry, Pressurized water reactors, Coolants, Electrical resistivity, Film boiling, Heat flux

Proceedings Papers

Recent Activities and New Challenges for the EUR Organization

Vincent Sorel

Paper No: ICONE28-64617

DOI: https://doi.org/10.1115/ICONE28-64617

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Topics: Accidents, Design, Engineering standards, Fukushima nuclear disaster, Japan, 2011, Light water reactors, Nuclear power stations, Safety, Small modular reactors

Proceedings Papers

Experimental Study on Edge Blockage Accidents in a Narrow Rectangular Channel

Dongdong Yuan, Weian Du, Yuhao He, Jiahong Zhu, Yonghao Zhang, Chengwei Li, Sichao Tan, Dongyang Li

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A012, August 4–6, 2021

Paper No: ICONE28-64684

DOI: https://doi.org/10.1115/ICONE28-64684

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Topics: Accidents, Fuels, Manufacturing

Proceedings Papers

Aerosol Removal by a Heat Exchanger of Passive Containment Cooling System

Yangyang Liang, Junjing Lu, Tianqi Zhang, Xu Han, Yidan Yuan

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A011, August 4–6, 2021

Paper No: ICONE28-64252

DOI: https://doi.org/10.1115/ICONE28-64252

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Topics: Accidents, Aerosols, Containment, Cooling systems, Heat exchangers

Proceedings Papers

Applicability Assessment of Accident Analysis Codes and Determination of Testing Facility for Validation of the CAP1400

Xiaoyu Cai, Guobao Shi, Jinquan Yan, Pu Fan, Dongjian Zhao

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A040, August 4–6, 2021

Paper No: ICONE28-66257

DOI: https://doi.org/10.1115/ICONE28-66257

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Topics: Accidents, Design, Licensing, Safety, Test facilities

Proceedings Papers

Sensitivity Analysis of Power Related Parameters in a Reactivity-Initiated Accident of a Molten Salt Reactor

Chaoqun Wang, Qun Yang, Kai Wang, Xiaowei Jiao, Yanhua Wu, Zhaozhong He

Paper No: ICONE28-64430

DOI: https://doi.org/10.1115/ICONE28-64430

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Topics: Accidents, Molten salt reactors, Sensitivity analysis

Proceedings Papers

Preliminary Transient Analysis for LBE-Cooled Fast Reactor BLESS-D

Mian Xing, Linsen Li, Gang Zheng, Junlang Wen, Chunyuan Liu, Yeoh Eing Yee, Zhen Luo, Peidong Sun, Jinjun Feng

Paper No: ICONE28-63220

DOI: https://doi.org/10.1115/ICONE28-63220

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Topics: Fast neutron reactors, Safety, Transient analysis, Transients (Dynamics), Design, Reactor vessels, Accidents, Boilers, Conceptual design, Coolants

Proceedings Papers

Design Study of SMR Class Super FR Core for In-Vessel Retention

Ryotaro Sasaki, Akifumi Yamaji, Kyota Uchimura

Paper No: ICONE28-64162

DOI: https://doi.org/10.1115/ICONE28-64162

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Topics: Accidents, Design, Small modular reactors, Supercritical water reactors, Vessels, Water

Proceedings Papers

Experimental and Numerical Investigation on Debris Bed Quenching With Additional Injection of Non-Condensable Gas

Markus Petroff, Rudi Kulenovic, Jörg Starflinger

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A031, August 4–6, 2021

Paper No: ICONE28-65512

DOI: https://doi.org/10.1115/ICONE28-65512

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Topics: Quenching (Metalworking), Particulate matter, Accidents, Cavities, Computer simulation, Concretes, Databases, Flow (Dynamics), Gases, Light water reactors

Proceedings Papers

Steady-State Performance Analysis of a Dual-Cladding Design for Accident Tolerance Fuel

Qianliang Deng, Songyang Li, Dingqu Wang, Yueyuan Jiang, Zhihong Liu, Wei Xiong, Yalin Tian

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A004, August 4–6, 2021

Paper No: ICONE28-63101

DOI: https://doi.org/10.1115/ICONE28-63101

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Topics: Accidents, Cladding systems (Building), Design, Fuels, Steady state

Proceedings Papers

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

Fengyang Quan, Wei Li, Zikun Zhao, Xiao Zeng, Yong Guo, Yidan Yuan

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A024, August 4–6, 2021

Paper No: ICONE28-64739

DOI: https://doi.org/10.1115/ICONE28-64739

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Topics: Accidents, Cladding systems (Building), Coolants, Cooling, Dimensional analysis, Engineering prototypes, Failure, Floods, Fuels, Heat flux

Proceedings Papers

The Evaluation of Break Sizes of LOCA by the Temperature Difference at the Recirculation Inlets of BWR

Sheng-Dih Hwang

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A029, August 4–6, 2021

Paper No: ICONE28-65413

DOI: https://doi.org/10.1115/ICONE28-65413

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Topics: Boiling water reactors, Temperature, Accidents, Control rooms, Engineering simulation, Nuclear reactors, Probability, Simulation

Proceedings Papers

Analyses of Wet and Dry Cavity Strategies for BWR Severe Accident Management With MELCOR-2.2

Ayato Takashima, Akifumi Yamaji, Xin Li, Daisuke Fujiwara, Hiroshi Shirai, Takumi Noujuu

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A006, August 4–6, 2021

Paper No: ICONE28-63285

DOI: https://doi.org/10.1115/ICONE28-63285

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Topics: Accident management, Accidents, Boiling water reactors, Cavities

Proceedings Papers

Features of a BWR Neutron Absorber Melt Relocation in an Oxidative Environment During the CLADS-MADE-02 Test

Anton Pshenichnikov, Yuji Nagae, Masaki Kurata

Paper No: ICONE28-65129

DOI: https://doi.org/10.1115/ICONE28-65129

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Topics: Accidents, Blades, Boiling water reactors, Fukushima nuclear disaster, Japan, 2011, Neutrons

Proceedings Papers

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

Yubin Zhang

Paper No: ICONE28-64737

DOI: https://doi.org/10.1115/ICONE28-64737

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Topics: Numerical analysis, Reactor vessels, Thermal shock, Accidents, Computational fluid dynamics, Computer software, Coolants, Flow (Dynamics), Mechanical structures, Nozzles

2 3 4 5

NARROW

Machine Learned Metamodeling of a Computationally Intensive Accident Simulation Code

Apros-Based Loviisa NPP Full Scope Training Simulator and Engineering Model

A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform

RELAP5 Code Analyses of PKL-4 Project Test on PWR Multiple Steam Generator Tube Rupture Accident With Recovery Actions

UHT Test Facility Updates and Oxidation Tests for Accident Tolerant Fuel Development

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Recent Activities and New Challenges for the EUR Organization

Experimental Study on Edge Blockage Accidents in a Narrow Rectangular Channel

Aerosol Removal by a Heat Exchanger of Passive Containment Cooling System

Applicability Assessment of Accident Analysis Codes and Determination of Testing Facility for Validation of the CAP1400

Sensitivity Analysis of Power Related Parameters in a Reactivity-Initiated Accident of a Molten Salt Reactor

Preliminary Transient Analysis for LBE-Cooled Fast Reactor BLESS-D

Design Study of SMR Class Super FR Core for In-Vessel Retention

Experimental and Numerical Investigation on Debris Bed Quenching With Additional Injection of Non-Condensable Gas

Steady-State Performance Analysis of a Dual-Cladding Design for Accident Tolerance Fuel

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

The Evaluation of Break Sizes of LOCA by the Temperature Difference at the Recirculation Inlets of BWR

Analyses of Wet and Dry Cavity Strategies for BWR Severe Accident Management With MELCOR-2.2

Features of a BWR Neutron Absorber Melt Relocation in an Oxidative Environment During the CLADS-MADE-02 Test

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

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