Volumes | International Conference on Nuclear Engineering | American Society of Mechanical Engineers Digital Collection

Topics: Fuels , Manufacturing , Uncertainty , Uncertainty analysis , Fuel rods , Temperature , Coolants , Pressurized water reactors , Machining , Rods

A Study of Safety Importance Screening Criteria in the NPP Risk-Informed Safety Classification Process

Jinghua Zhou, Wei Deng, Chao Ma, Yiwen Guo

ICONE 2024; V010T12A002https://doi.org/10.1115/ICONE31-132467

Abstract

View Articletitled, A Study of Safety Importance Screening Criteria in the NPP Risk-Informed Safety Classification Process

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Topics: Nuclear power stations , Risk , Safety

Comparative Study of Deep Learning Models for Accidents Classification in NPP: Emphasizing Transparency and Performance

Merouane Najar, He Wang

ICONE 2024; V010T12A003https://doi.org/10.1115/ICONE31-133604

Abstract

View Articletitled, Comparative Study of Deep Learning Models for Accidents Classification in NPP: Emphasizing Transparency and Performance

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Topics: Accidents , Deep learning , Nuclear power stations , Safety , Transparency

A Text Intelligence-Based Approach for Automatic Generation of Fault Trees in Nuclear Power Plants

Xingyu Xiao, Songlin Liu, Zhiyong Zuo, Peng Chen, Ben Qi, Jingang Liang, Jiejuan Tong

ICONE 2024; V010T12A004https://doi.org/10.1115/ICONE31-134226

Abstract

View Articletitled, A Text Intelligence-Based Approach for Automatic Generation of Fault Trees in Nuclear Power Plants

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Topics: Fault tree analysis , Large language models , Nuclear power stations

The Development of the Fire PRA Model for Shimane Unit 2 Nuclear Power Plant

Kotaro Yoshizaki, Bumpei Fujioka, Daichi Shiota, Takahiro Usui, Hitoshi Nojima, Kenichi Kanda, Kazunobu Noriyasu

ICONE 2024; V010T12A005https://doi.org/10.1115/ICONE31-134339

Abstract

View Articletitled, The Development of the Fire PRA Model for Shimane Unit 2 Nuclear Power Plant

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Topics: Fire , Nuclear power stations , Probabilistic risk assessment

Enhancement of Shimane Unit 2 Internal Event At-Power PRA for Reflecting New Findings Including Current Plant States

Takahiro Usui, Hiroki Nakamura, Kenichi Ihara, Yuki Hirai, Hitoshi Nojima, Satoshi Yoneda, Kenichi Kanda, Kazunobu Noriyasu, Daichi Shiota, Naoki Hirokawa

ICONE 2024; V010T12A006https://doi.org/10.1115/ICONE31-134400

Abstract

View Articletitled, Enhancement of Shimane Unit 2 Internal Event At-Power PRA for Reflecting New Findings Including Current Plant States

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Topics: Accidents , Airbags , Boiling water reactors , Design , Electricity (Physics) , Engineering standards , Failure data , Fault tree analysis , Fukushima nuclear disaster, Japan, 2011 , Human reliability analysis

Analysis of Mobile Equipment Configuration for Severe Accidents in Nuclear Power Plants Based on Multi-Unit PSA

Dalin Liu, Jiangguo Wang, Zhen Yan, Shuting Wang, Ling Zhao

ICONE 2024; V010T12A007https://doi.org/10.1115/ICONE31-134510

Abstract

View Articletitled, Analysis of Mobile Equipment Configuration for Severe Accidents in Nuclear Power Plants Based on Multi-Unit PSA

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Topics: Accidents , Nuclear power stations

Typical Fault Diagnosis Model of Nuclear Power Plant Combined With Knowledge Driven and Data Driven

Xin Wang, Minjun Peng, Hang Wang, Zikang Li

ICONE 2024; V010T12A008https://doi.org/10.1115/ICONE31-134815

Abstract

View Articletitled, Typical Fault Diagnosis Model of Nuclear Power Plant Combined With Knowledge Driven and Data Driven

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Topics: Fault diagnosis , Nuclear power stations

Impact of Synoptic Weather Patterns Along the Pacific Coastline of Japan on Tornado Wind Hazard Curves

Kota Fujiwara, Daisuke Nohara, Yuzuru Eguchi, Yasuo Hattori, Hiromaru Hirakuchi

ICONE 2024; V010T12A009https://doi.org/10.1115/ICONE31-135030

Abstract

View Articletitled, Impact of Synoptic Weather Patterns Along the Pacific Coastline of Japan on Tornado Wind Hazard Curves

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Topics: Hazards , Pacific Ocean , Shorelines , Wind

Effect of Hydrogen Plant Structure on Hydrogen Diffusion

Zhang Shucheng, Xuefeng Lyu, Lin Wang, Xichen Li, Yu Yu, Houjian Zhao, Shengfei Wang, Zhangpeng Guo

ICONE 2024; V010T12A010https://doi.org/10.1115/ICONE31-135092

Abstract

View Articletitled, Effect of Hydrogen Plant Structure on Hydrogen Diffusion

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Topics: Combustion , Diffusion (Physics) , Explosions , Hydrogen , Hydrogen production , Leakage , Nuclear power , Risk

Typical Sequence Analysis of SLOCA Accidents in a Third Generation Nuclear Power Plant Based on RISMC Method

Churan Feng, Jingxiang Zhan, Lin Yan, Yiming Wang, Jinghua Zhou

ICONE 2024; V010T12A011https://doi.org/10.1115/ICONE31-135096

Abstract

View Articletitled, Typical Sequence Analysis of SLOCA Accidents in a Third Generation Nuclear Power Plant Based on RISMC Method

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Topics: Accidents , Nuclear power stations , Safety , Failure , Damage , Design , Feedwater , Probability , Risk , Uncertainty

Human Reliability Analysis for a Passive NPP and Application in Plant Operating Procedure Optimization

Yongping Qiu, Xiao Tan

ICONE 2024; V010T12A012https://doi.org/10.1115/ICONE31-135379

Abstract

View Articletitled, Human Reliability Analysis for a Passive NPP and Application in Plant Operating Procedure Optimization

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Topics: Errors , Human reliability analysis , Nuclear power stations , Optimization , Probability , Risk

Quantifying Software Safety in Nuclear Power Plants: A Framework for Requirements Phase Assessment

Boyuan Li, Duo Li, Jianghai Li, Chao Guo, Huasheng Xiong, Shuqiao Zhou, Xiaojin Huang

ICONE 2024; V010T12A013https://doi.org/10.1115/ICONE31-135382

Abstract

View Articletitled, Quantifying Software Safety in Nuclear Power Plants: A Framework for Requirements Phase Assessment

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Topics: Computer software , Gates (Closures) , Hazards , Nuclear power stations , Safety

The Mission Time Analysis in Level 2 Probabilistic Safety Assessment of the Third-Generation Nuclear Power Plant

Shujie Guo, Jing Liu, Yubao Zhong

ICONE 2024; V010T12A014https://doi.org/10.1115/ICONE31-135680

Abstract

View Articletitled, The Mission Time Analysis in Level 2 Probabilistic Safety Assessment of the Third-Generation Nuclear Power Plant

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Topics: Accidents , Nuclear power stations , Probabilistic safety assessment , Containment , Concretes , Damage , Delays , Failure analysis , Modeling

Effect of Different Temperature Probability Curve Fitting Methods on the System Reliability for PCCS in AP1000

Yu Yu, Guanyu Liu, Wanxin Feng, Houjian Zhao, Xuefeng Lyu

ICONE 2024; V010T12A015https://doi.org/10.1115/ICONE31-135769

Abstract

View Articletitled, Effect of Different Temperature Probability Curve Fitting Methods on the System Reliability for PCCS in AP1000

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Topics: Curve fitting , Failure , Probability , Reliability , Temperature

Risk-Informed Defense-in-Depth Strategy for Nuclear Power Plant

Qianwen Liu, Yuxiang Wu, Yuhan Wang

ICONE 2024; V010T12A016https://doi.org/10.1115/ICONE31-135793

Abstract

View Articletitled, Risk-Informed Defense-in-Depth Strategy for Nuclear Power Plant

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Topics: Defense industry , Nuclear power stations , Risk

Design Management Platform Maturity Research and Improvement Application

Haili Shi, Yuefei Hu, Wenzhao Zhao

ICONE 2024; V010T12A017https://doi.org/10.1115/ICONE31-135862

Abstract

View Articletitled, Design Management Platform Maturity Research and Improvement Application

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Topics: Design

Study on the PSA Application in Emergency Operating Procedure Development

Chao Ma, Churan Feng, Jinyan Du, Jian Yang

ICONE 2024; V010T12A018https://doi.org/10.1115/ICONE31-135954

Abstract

View Articletitled, Study on the PSA Application in Emergency Operating Procedure Development

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Topics: Design , Emergency operating procedures , Risk

Safety Evaluation and Optimization of Nuclear Power Plant Under Adaptive Sampling

Linfeng Li, Zhen Zhang, Anqi Xu, Ting Wen, Xiaomeng Dong, Ming Yang, Linxian Chen, Yong Liu

ICONE 2024; V010T12A019https://doi.org/10.1115/ICONE31-136531

Abstract

View Articletitled, Safety Evaluation and Optimization of Nuclear Power Plant Under Adaptive Sampling

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Topics: Nuclear power stations , Optimization , Probabilistic safety assessment , Risk , Safety , Support vector machines

Research on the Application of Risk-Managed Technical Specifications in Passive Nuclear Power Plants

Zhen Yan, Jiajian Wang, Gang Ma, Jianwen Sun, Zhenqi Wang, Dalin Liu, Shuting Wang, Sheng Zhu

ICONE 2024; V010T12A020https://doi.org/10.1115/ICONE31-136866

Abstract

View Articletitled, Research on the Application of Risk-Managed Technical Specifications in Passive Nuclear Power Plants

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Topics: Nuclear power stations , Risk

Computer Code Verification and Validation

Modeling and Analysis of VENUS-2 MOX Core Experiment Based on OpenMC Monte Carlo Code

Zelong Zhao

ICONE 2024; V010T13A001https://doi.org/10.1115/ICONE31-130363

Abstract

View Articletitled, Modeling and Analysis of VENUS-2 MOX Core Experiment Based on OpenMC Monte Carlo Code

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Topics: Cross section (Physics) , Dosimetry , Flux (Metallurgy) , Fuels , Modeling , Nuclear fission , Pins (Engineering) , Sensors

Research and Preliminary Verification of the Resonance Self-Shielding Calculation Method for the High-Fidelity Neutronics Code VITAS

Han Yin, Tengfei Zhang, Xiaojing Liu

ICONE 2024; V010T13A002https://doi.org/10.1115/ICONE31-133419

Abstract

View Articletitled, Research and Preliminary Verification of the Resonance Self-Shielding Calculation Method for the High-Fidelity Neutronics Code VITAS

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Topics: Computational methods , Resonance

The General Quadrant Meshing Approach for Constructive Solid Geometry Based Method of Characteristics

Jian Guo, Guifeng Zhu, Rui Yan, Yang Zou

ICONE 2024; V010T13A003https://doi.org/10.1115/ICONE31-134175

Abstract

View Articletitled, The General Quadrant Meshing Approach for Constructive Solid Geometry Based Method of Characteristics

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Topics: Geometry

Modeling Co-Current and Counter-Current Flow: A Performance Evaluation of the TRACE Condensation Model with Non-Condensable and Light Gases

Samah A. Albdour, Yacine Addad, Imran Afgan

ICONE 2024; V010T13A004https://doi.org/10.1115/ICONE31-134262

Abstract

View Articletitled, Modeling Co-Current and Counter-Current Flow: A Performance Evaluation of the TRACE Condensation Model with Non-Condensable and Light Gases

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Topics: Condensation , Containment , Cooling systems , Flow (Dynamics) , Gases , Heat transfer coefficients , Modeling , Performance evaluation

Validation and Verification of ASYST Code for Predicting Condensation Phenomena in Nuclear Reactor Safety Systems

Satya Prakash Saraswat, Mubashir Hassan, Sameer Mohammad Osman, Chris Allison, Yacine Addad

ICONE 2024; V010T13A005https://doi.org/10.1115/ICONE31-134294

Abstract

View Articletitled, Validation and Verification of ASYST Code for Predicting Condensation Phenomena in Nuclear Reactor Safety Systems

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Topics: Condensation , Nuclear reactor safety , Test facilities

Tube Plugging Induced Temperature Non-Uniformity in Once Through Steam Generator

Yunhao Luo, Xiaoyang Xie, Xiaowei Li, Xinxin Wu

ICONE 2024; V010T13A006https://doi.org/10.1115/ICONE31-134783

Abstract

View Articletitled, Tube Plugging Induced Temperature Non-Uniformity in Once Through Steam Generator

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Topics: Boilers , Porous materials , Temperature nonunifomity

Verification and Analysis of Thermal-Hydraulics System Program for a Power Plant Model

Lixin Du, Peng Zhou, Hao Zhang, Yanhua Yang

ICONE 2024; V010T13A007https://doi.org/10.1115/ICONE31-134794

Abstract

View Articletitled, Verification and Analysis of Thermal-Hydraulics System Program for a Power Plant Model

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Topics: Accidents , Circuits , Computer software , Design , Fluids , Heat transfer , Hydraulic drive systems , Nuclear power , Nuclear power stations , Power stations

Comparative Analysis of Loss of Coolant Accidents for GEN-III PWRs Based on ACME and ATLAS Facilities

Yuhang Huang, Xueyan Zhang, Jun Yang

ICONE 2024; V010T13A008https://doi.org/10.1115/ICONE31-134823

Abstract

View Articletitled, Comparative Analysis of Loss of Coolant Accidents for GEN-III PWRs Based on ACME and ATLAS Facilities

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Topics: Loss of coolant accidents , Pressurized water reactors , Safety , Accidents , Test facilities , Vessels , China , Cooling systems , Design , Failure

Reducing Variance in Nuclear Monte Carlo Simulations Through Deep Learning Post-Processing Techniques in the Gaming Domain

Haoxuan Guo, Wei Li, Yaodong Sang, Haizheng Chen, Qingmin Zhang

ICONE 2024; V010T13A009https://doi.org/10.1115/ICONE31-134868

Abstract

View Articletitled, Reducing Variance in Nuclear Monte Carlo Simulations Through Deep Learning Post-Processing Techniques in the Gaming Domain

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Topics: Deep learning , Simulation

Code-to-Code Verification of Thermal Hydraulic Subchannel Code LINDEN

Zixuan Wang, Yuanbing Zhu, Yan Wang

ICONE 2024; V010T13A010https://doi.org/10.1115/ICONE31-135128

Abstract

View Articletitled, Code-to-Code Verification of Thermal Hydraulic Subchannel Code LINDEN

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Topics: Circuits , Fuel rods , Pressurized water reactors , Simulation results , Steady state , Transients (Dynamics)

Multi-Physics Coupling Simulation of a Small Floating Lead-Cooled Fast Reactor Based on OpenMC and GeN-Foam

Haochen Huang, Fei Xie, Yu Liu, Daogang Lu

ICONE 2024; V010T13A011https://doi.org/10.1115/ICONE31-135154

Abstract

View Articletitled, Multi-Physics Coupling Simulation of a Small Floating Lead-Cooled Fast Reactor Based on OpenMC and GeN-Foam

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Topics: Fast neutron reactors , Physics , Simulation

TRIPOLI-4^® Monte Carlo Code Verification and Validation Using T4G Tool

Yi-Kang Lee, François-Xavier Hugot

ICONE 2024; V010T13A012https://doi.org/10.1115/ICONE31-135213

Abstract

View Articletitled, TRIPOLI-4<sup>®</sup> Monte Carlo Code Verification and Validation Using T4G Tool

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Topics: Collisions (Physics) , Electrons , Geometry , Instrumentation , Leakage , Neutrons , Nuclear engineering , Nuclear reactors , Particulate matter , Photons

Verification of the RMC-SaraGR Nuclear Design Code System Based on the HTTR Benchmark

Yuan Yuan, Guoming Liu, Peng Zhang

ICONE 2024; V010T13A013https://doi.org/10.1115/ICONE31-135368

Abstract

View Articletitled, Verification of the RMC-SaraGR Nuclear Design Code System Based on the HTTR Benchmark

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Topics: Neutrons , Nuclear design , Uncertainty , Very high temperature reactors , Cross section (Physics) , Fuels , Modeling , Rods

OECD-NEA Expert Group on Reactor Systems Multi-Physics: Development of Verification and Validation Guidelines for Multi-Physics Simulations

Timothy E. Valentine, Evgeny Ivanov, Kostadin Ivanov, Alessandro Petruzzi, Maria Avramova, Mathieu Hursin, Oliver Buss

ICONE 2024; V010T13A014https://doi.org/10.1115/ICONE31-136161

Abstract

View Articletitled, OECD-NEA Expert Group on Reactor Systems Multi-Physics: Development of Verification and Validation Guidelines for Multi-Physics Simulations

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Topics: Nuclear reactors , Physics , Simulation

SIMMER-III Code Simulation of High-Pressure Water-Lead Interaction in Westinghouse’s LEWIN Test Facility

Alessandro Bellomo, Mattia Massone, Simone Gianfelici, Fabio Martini, Sung Jin Lee, Mariano Tarantino, Francesco Galleni, Andrea Pucciarelli, Alessio Pesetti

ICONE 2024; V010T13A015https://doi.org/10.1115/ICONE31-136222

Abstract

View Articletitled, SIMMER-III Code Simulation of High-Pressure Water-Lead Interaction in Westinghouse’s LEWIN Test Facility

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Topics: Coolants , High pressure (Physics) , Simulation , Test facilities , Water

Pure Lead Thermodynamic Properties in SIMMER-III Code: A Comparative Review and New Evaluation Proposal

Alessandro Bellomo, Mattia Massone, Simone Gianfelici, Koji Morita, Mariano Tarantino, Alessio Pesetti, Vittorio Cossu, Andrei Rineiski

ICONE 2024; V010T13A016https://doi.org/10.1115/ICONE31-136243

Abstract

View Articletitled, Pure Lead Thermodynamic Properties in SIMMER-III Code: A Comparative Review and New Evaluation Proposal

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Topics: Equations of state , Fast neutron reactors , Thermodynamic properties , Heat capacity , Accidents , Design , Liquid metals , Pressure , Sodium fast reactors , Boilers