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2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference

August 4–5, 2020

Virtual, Online

Conference Sponsors:

ISBN:

978-0-7918-8377-8

In This Volume

Nuclear Policy (3)
Nuclear Safety, Security, and Cyber Security (61)
Operating Plant Experience (11)
Probabilistic Risk Assessments (15)
SMR and Advanced Reactors (16)

Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors

Nuclear Policy

Reforms and Innovations in a Nuclear Engineering Course: Nuclear Power Plant Systems and Equipment

Shanfang Huang, Jiageng Wang, Yisheng Hao, Guodong Liu, Minyun Liu, Yugao Ma

ICONE 2020; V002T07A001doi:https://doi.org/10.1115/ICONE2020-16033

Abstract

View Articletitled, Reforms and Innovations in a Nuclear Engineering Course: Nuclear Power Plant Systems and Equipment

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Topics: Innovation , Nuclear engineering , Nuclear power stations , Safety , Teaching

Analysis of Chinese People’s Perception of Radiation and Nuclear Power With Insights Into Behavioral Science

Hsingtzu Wu, Da-Wei Wang

ICONE 2020; V002T07A002doi:https://doi.org/10.1115/ICONE2020-16048

Abstract

View Articletitled, Analysis of Chinese People’s Perception of Radiation and Nuclear Power With Insights Into Behavioral Science

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Topics: Nuclear power , Radiation (Physics)

Public Engagement of Nuclear Energy in China: The Characteristics of Public Knowledge, Risk Perception, Trust Perception and Environmental Concern

Priscilla Obeng Oforiwaa, Zhang Chao, Liang Manchun, Su Guofeng, Wang Jiahao

ICONE 2020; V002T07A003doi:https://doi.org/10.1115/ICONE2020-16064

Abstract

View Articletitled, Public Engagement of Nuclear Energy in China: The Characteristics of Public Knowledge, Risk Perception, Trust Perception and Environmental Concern

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Topics: China , Nuclear power , Risk , Risk perception , Carbon , Climate change , Emissions

Nuclear Safety, Security, and Cyber Security

Seawater Desalination Using a High-Temperature Gas-Cooled Reactor (HTR): Overview of Regulatory and Safety Considerations

Mishari Al-Saud, Fang Chao

ICONE 2020; V002T08A001doi:https://doi.org/10.1115/ICONE2020-16023

Abstract

View Articletitled, Seawater Desalination Using a High-Temperature Gas-Cooled Reactor (HTR): Overview of Regulatory and Safety Considerations

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Topics: Safety , Very high temperature reactors , Water desalination

Emergency Action Level Study in Reprocessing Facility

Wang Renze, Zhang Jiangang, Yang Yapeng, Feng Zongyang, Jia Linsheng, Wang Ning, Liu Yining, Liang Boning

ICONE 2020; V002T08A002doi:https://doi.org/10.1115/ICONE2020-16052

Abstract

View Articletitled, Emergency Action Level Study in Reprocessing Facility

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Topics: Emergencies

Cyber Resilience Analysis of SCADA Systems in Nuclear Power Plants

Meghan Galiardi, Amanda Gonzales, Jamie Thorpe, Eric Vugrin, Raymond Fasano, Christopher Lamb

ICONE 2020; V002T08A003doi:https://doi.org/10.1115/ICONE2020-16071

Abstract

View Articletitled, Cyber Resilience Analysis of SCADA Systems in Nuclear Power Plants

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Topics: Nuclear power stations , Resilience , Supervisory Control and Data Acquisition systems , Control systems , Architecture , Design , Security , Computer security , Computer software , Hardware

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Kinetic Study of Boron Carbide-Stainless Steel Eutectic Melting by Differential Thermal Analysis

Shin Kikuchi, Hidemasa Yamano, Kinya Nakamura

ICONE 2020; V002T08A004doi:https://doi.org/10.1115/ICONE2020-16075

Abstract

View Articletitled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Kinetic Study of Boron Carbide-Stainless Steel Eutectic Melting by Differential Thermal Analysis

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Topics: Accidents , Boron , Melting , Sodium fast reactors , Steel , Thermal analysis

Identify the Broken Loop and Break Sizes of Recirculation Line LOCA for a BWR6/MarkIII Plant

Sheng-Dih Hwang, Te-Chuan Wang

ICONE 2020; V002T08A005doi:https://doi.org/10.1115/ICONE2020-16089

Abstract

View Articletitled, Identify the Broken Loop and Break Sizes of Recirculation Line LOCA for a BWR6/MarkIII Plant

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Topics: Boiling water reactors , Control rooms , Nuclear power stations , Probability , Steady state , Temperature

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Thermophysical Properties of Eutectic Mixture Containing of High Concentration Boron in a Solid State

Toshihide Takai, Tomohiro Furukawa, Hidemasa Yamano

ICONE 2020; V002T08A006doi:https://doi.org/10.1115/ICONE2020-16091

Abstract

View Articletitled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Thermophysical Properties of Eutectic Mixture Containing of High Concentration Boron in a Solid State

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Topics: Accidents , Boron , Melting , Sodium fast reactors , Stainless steel

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Project Overview and Progress Until 2018

Hidemasa Yamano, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama, Hiroyuki Fukuyama, Hideo Higashi, Tsuyoshi Nishi, Hiromichi Ohta, Xiaoxing Liu, Koji Morita, Kinya Nakamura

ICONE 2020; V002T08A007doi:https://doi.org/10.1115/ICONE2020-16102

Abstract

View Articletitled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Project Overview and Progress Until 2018

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Topics: Accidents , Melting , Sodium fast reactors , Stainless steel

Finite Element Method for Thermal Design of Radioactive Material Transport Packages

Dongyuan Meng, Shutang Sun, Hongchao Sun, Guoqiang Li

ICONE 2020; V002T08A008doi:https://doi.org/10.1115/ICONE2020-16115

Abstract

View Articletitled, Finite Element Method for Thermal Design of Radioactive Material Transport Packages

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Topics: Containers , Design , Finite element methods , Radioactive substances , Transport packages

A Fault Diagnosis Method Based on Signed Directed Graph and Correlation Analysis for Nuclear Power Plants

Chongchong Liu, Guohua Wu, Congsong Yang, Yunwen Li, Qian Wu

ICONE 2020; V002T08A009doi:https://doi.org/10.1115/ICONE2020-16120

Abstract

View Articletitled, A Fault Diagnosis Method Based on Signed Directed Graph and Correlation Analysis for Nuclear Power Plants

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Topics: Expert systems , Fault diagnosis , Nuclear power stations

Study on Measures During Loss of Normal Feedwater Accident for AP1000 NPP in Lower Power Operation

Baisong Ma, Zhengqiang Miao, Yaping Zhuang, Weili Hou

ICONE 2020; V002T08A010doi:https://doi.org/10.1115/ICONE2020-16122

Abstract

View Articletitled, Study on Measures During Loss of Normal Feedwater Accident for AP1000 NPP in Lower Power Operation

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Topics: Accidents , Feedwater , Nuclear power stations , Water

Method for Prognosis of LBLOCA Initiated Emergency Condition

Wang Ning, Wang Renze, Yang Yapeng, Feng Zongyang, Jia Linsheng, Liu Yining, Liang Boning

ICONE 2020; V002T08A011doi:https://doi.org/10.1115/ICONE2020-16130

Abstract

View Articletitled, Method for Prognosis of LBLOCA Initiated Emergency Condition

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Topics: Emergencies

Protection of Nuclear Power Plants Against Severe Winds: Impact of the Local Building Configuration on the Wind Speed to Consider

Arièle Défossez, Eric Dupont, Laurence Grammosenis, Hervé Cordier, Tiphaine Le Morvan

ICONE 2020; V002T08A012doi:https://doi.org/10.1115/ICONE2020-16136

Abstract

View Articletitled, Protection of Nuclear Power Plants Against Severe Winds: Impact of the Local Building Configuration on the Wind Speed to Consider

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Topics: Computational fluid dynamics , Flow (Dynamics) , Nuclear power stations , Pressurized water reactors , Safety , Wind velocity , Structures , Wind , Power stations , Storms

Uranium Radioactivity Measurement for Low-Level Wastewater Based on Ultra-Low Level Liquid Scintillation Analyzer

Jinxu Lv, Ning Lv, Huiping Guo, Zeting Hu, Geng Song, Yinying Cai, Heling Zhang, Daji Li

ICONE 2020; V002T08A013doi:https://doi.org/10.1115/ICONE2020-16143

Abstract

View Articletitled, Uranium Radioactivity Measurement for Low-Level Wastewater Based on Ultra-Low Level Liquid Scintillation Analyzer

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Topics: Radiation measurement , Radioactivity , Sewage , Uranium

Study on On-Site Calibration Method of Stationary Neutron Dosimeter

Jinxu Lv, Ning Lv, Huiping Guo, Mingyan Sun, Kuo Zhao, Wenhui Lv, Zhihao Wei, Qizhan Xiao, Daji Li, Yang Liu

ICONE 2020; V002T08A014doi:https://doi.org/10.1115/ICONE2020-16144

Abstract

View Articletitled, Study on On-Site Calibration Method of Stationary Neutron Dosimeter

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Topics: Calibration , Dosimeters , Neutrons

Research on Operating Strategy of Total Loss of Essential Service Water System With RHR Not Connected in PWR Unit

Shengtao Zhang, Ke Yi

ICONE 2020; V002T08A015doi:https://doi.org/10.1115/ICONE2020-16145

Abstract

View Articletitled, Research on Operating Strategy of Total Loss of Essential Service Water System With RHR Not Connected in PWR Unit

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Topics: Pressurized water reactors , Water

Nuclear Material Measurement Based on Fast Neutron Multiplicity Counter

Xianghua Su, Quanhu Zhang, Suxia Hou, Sufen Li, Jianqing Yang, Linjun Hou, Qifan Chen, Zhichun Xu

ICONE 2020; V002T08A016doi:https://doi.org/10.1115/ICONE2020-16151

Abstract

View Articletitled, Nuclear Material Measurement Based on Fast Neutron Multiplicity Counter

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Topics: Neutrons

Simulation and Construction of Fast Neutron Multi-Counter Based on Liquid Flash

Qifan Chen, Quanhu Zhang, Suxia Hou, Sufen Li, Jianqing Yang, Xianghua Su, Linjun Hou, Zhichun Xu

ICONE 2020; V002T08A017doi:https://doi.org/10.1115/ICONE2020-16152

Abstract

View Articletitled, Simulation and Construction of Fast Neutron Multi-Counter Based on Liquid Flash

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Topics: Construction , Neutrons , Simulation

Nuclear Facility Safety at the United States Department of Energy

Patrick Frias, José R. O. Muñoz, Louis Restrepo, James L. Tingey, David L. Y. Louie

ICONE 2020; V002T08A018doi:https://doi.org/10.1115/ICONE2020-16167

Abstract

View Articletitled, Nuclear Facility Safety at the United States Department of Energy

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Topics: Safety

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide

Xiaoxing Liu, Koji Morita, Hidemasa Yamano

ICONE 2020; V002T08A019doi:https://doi.org/10.1115/ICONE2020-16175

Abstract

View Articletitled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide

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Topics: Accidents , Boron , Melting , Sodium fast reactors , Stainless steel , Equilibrium (Physics) , Fast neutron reactors , Heat , Mass transfer , Safety

Preliminary Investigation on Improvement of FP Management During BWR Severe Accident With MELCOR-2.2

Kento Matsubara, Akifumi Yamaji, Xin Li, Daisuke Fujiwara, Hiroshi Shirai, Takumi Noujuu

ICONE 2020; V002T08A020doi:https://doi.org/10.1115/ICONE2020-16182

Abstract

View Articletitled, Preliminary Investigation on Improvement of FP Management During BWR Severe Accident With MELCOR-2.2

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Topics: Accident management , Accidents , Boiling water reactors

Impact of Climate Change on EDF’s Nuclear Facilities: Climate Watch Approach

L. Guinard, S. Parey, H. Cordier, L. Grammosenis

ICONE 2020; V002T08A021doi:https://doi.org/10.1115/ICONE2020-16186

Abstract

View Articletitled, Impact of Climate Change on EDF’s Nuclear Facilities: Climate Watch Approach

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Topics: Climate , Climate change , Hazards , Nuclear power stations , Safety

Protection of Nuclear Power Plants Against Natural Hazards: Consideration for EDF’s Nuclear Facilities of Decamillennial Events (WENRA RL T4.2)

L. Guinard, S. Parey, L. Grammosenis, H. Cordier

ICONE 2020; V002T08A022doi:https://doi.org/10.1115/ICONE2020-16187

Abstract

View Articletitled, Protection of Nuclear Power Plants Against Natural Hazards: Consideration for EDF’s Nuclear Facilities of Decamillennial Events (WENRA RL T4.2)

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Topics: Hazards , Nuclear power stations , Safety

Review of Application on Dynamic Fault Tree Method in Nuclear Power Plants

Wu Guohua, Yuan Diping, Xiao Yiqing, Wang Jiaxin

ICONE 2020; V002T08A023doi:https://doi.org/10.1115/ICONE2020-16191

Abstract

View Articletitled, Review of Application on Dynamic Fault Tree Method in Nuclear Power Plants

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Topics: Nuclear power stations , Chain , Explosions , Computer software , Failure , Probabilistic risk assessment

Research on Fault Diagnosis Based on Hierarchical Signed Directed Graph for Nuclear Power Plants

Wu Guohua, Wang Jiaxin, Yuan Diping, Xiao Yiqing

ICONE 2020; V002T08A024doi:https://doi.org/10.1115/ICONE2020-16192

Abstract

View Articletitled, Research on Fault Diagnosis Based on Hierarchical Signed Directed Graph for Nuclear Power Plants

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Topics: Fault diagnosis , Flaw detection , Nuclear power stations

Analytical Study on Removal Mechanisms of Cesium Aerosol From a Noble Gas Bubble Rising Through Liquid Sodium Pool

Shinya Miyahara, Munemichi Kawaguchi, Hiroshi Seino

ICONE 2020; V002T08A025doi:https://doi.org/10.1115/ICONE2020-16208

Abstract

View Articletitled, Analytical Study on Removal Mechanisms of Cesium Aerosol From a Noble Gas Bubble Rising Through Liquid Sodium Pool

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Topics: Aerosols , Bubbles , Decontamination , Sodium

The Choice of MOSFET Manufacturing Technique Used in Emergency Response Robot

Liu Yining, Wang Renze, Yang Yapeng, Zhang Jiangang, Wang Ning, Feng Zongyang, Jia Linsheng, Liang Boning

ICONE 2020; V002T08A026doi:https://doi.org/10.1115/ICONE2020-16222

Abstract

View Articletitled, The Choice of MOSFET Manufacturing Technique Used in Emergency Response Robot

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Topics: Emergency response , Manufacturing , MOSFET transistors , Robots

Selection and Validation of Fast and Synchronous Interface to the Controller of a Space Nuclear Reactor Power System

Andrew Hahn, Timothy Schriener, Mohamed S. El-Genk

ICONE 2020; V002T08A027doi:https://doi.org/10.1115/ICONE2020-16237

Abstract

View Articletitled, Selection and Validation of Fast and Synchronous Interface to the Controller of a Space Nuclear Reactor Power System

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Topics: Control equipment , Nuclear reactors , Power systems (Machinery)

Emulation Methodology of Programmable Logic Controllers for Cybersecurity Applications

Raymond Fasano, Christopher Lamb, Mohamed El Genk, Timothy Schriener, Andrew Hahn

ICONE 2020; V002T08A028doi:https://doi.org/10.1115/ICONE2020-16245

Abstract

View Articletitled, Emulation Methodology of Programmable Logic Controllers for Cybersecurity Applications

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Topics: Computer security , Instrumentation , Programmable controllers

Discussion of Water Quality Factors Affecting ¹³⁷C_s Adsorption and the Relationship Between ¹³⁷C_s-K_d and Flow Rate in Freshwater

Jiaxin Wang, Liuguo Zhang, Jingyuan Qu, Guohua Wu

ICONE 2020; V002T08A029doi:https://doi.org/10.1115/ICONE2020-16248

Abstract

View Articletitled, Discussion of Water Quality Factors Affecting 137Cs Adsorption and the Relationship Between 137Cs-Kd and Flow Rate in Freshwater

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Topics: Flow (Dynamics) , Nuclear power stations , Particulate matter , Water pollution

Research on the Simulation of Radiographic Imaging Based on Cosmic-Ray Muon Scattering and the Optimization of PoCA

Lin-jun Hou, Quan-hu Zhang, Yong-gang Huo, Wen-ming Zuo, Qi-fan Chen, Xiang-hua Su, Zhi-chun Xu

ICONE 2020; V002T08A030doi:https://doi.org/10.1115/ICONE2020-16268

Abstract

View Articletitled, Research on the Simulation of Radiographic Imaging Based on Cosmic-Ray Muon Scattering and the Optimization of PoCA

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Topics: Algorithms , Cosmic rays , Electromagnetic scattering , Imaging , Muons , Optimization , Radiation scattering , Scattering (Physics) , Simulation

Development of Approaches to Simulate Fuel Rod Destruction With Different Fuel Type

Eduard Usov, Nikolay Pribaturin, Vladimir Chukhno, Ilya Klimonov, Anton Butov, Ivan Kudashov, Albert Gafiyatullin, Pavel Lobanov

ICONE 2020; V002T08A031doi:https://doi.org/10.1115/ICONE2020-16326

Abstract

View Articletitled, Development of Approaches to Simulate Fuel Rod Destruction With Different Fuel Type

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Topics: Fuel rods , Fuels

Artificial Neural Networks in Condition Monitoring and Fault Diagnosis of Nuclear Power Plants: A Concise Review

B. T. Jiang, J. Zhou, X. B. Huang

ICONE 2020; V002T08A032doi:https://doi.org/10.1115/ICONE2020-16334

Abstract

View Articletitled, Artificial Neural Networks in Condition Monitoring and Fault Diagnosis of Nuclear Power Plants: A Concise Review

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Topics: Artificial neural networks , Condition monitoring , Fault diagnosis , Nuclear power stations , Artificial intelligence

An Image Quality Improvement Method Based on Neural Network for Digital Radiography Security Inspection System

Zhiying Leng, Zhentao Wang

ICONE 2020; V002T08A033doi:https://doi.org/10.1115/ICONE2020-16344

Abstract

View Articletitled, An Image Quality Improvement Method Based on Neural Network for Digital Radiography Security Inspection System

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Topics: Artificial neural networks , Inspection , Security , Noise (Sound) , Vehicles , Algorithms , Nuclear power stations , Sensors , Vibration

New Control System of VR-1 Training Reactor

Martin Kropík, Jan Rataj, Ladislav Reisner, Jiri Matousek

ICONE 2020; V002T08A034doi:https://doi.org/10.1115/ICONE2020-16373

Abstract

View Articletitled, New Control System of VR-1 Training Reactor

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Topics: Control systems , Safety

Weakly Supervised Deep Neural Network for Bearing Fault Diagnosis

Daisuke Miki, Kazuyuki Demachi

ICONE 2020; V002T08A035doi:https://doi.org/10.1115/ICONE2020-16380

Abstract

View Articletitled, Weakly Supervised Deep Neural Network for Bearing Fault Diagnosis

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Topics: Artificial neural networks , Bearings , Fault diagnosis , Signals , Time series , Vibration , Failure , Flaw detection , Artificial intelligence , Feature extraction

Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software

Changbing Tang, Yongjun Jiao, Yuanming Li, Yi Zhou, Kun Zhang

ICONE 2020; V002T08A036doi:https://doi.org/10.1115/ICONE2020-16387

Abstract

View Articletitled, Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software

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Topics: Cladding systems (Building) , Computer simulation , Computer software , Fuel rods , Fuels , Stress , Failure , Pressure , Simulation , Transients (Dynamics)

Benchmarking an AI-Guided Reasoning-Based Operator Support System on the Three Mile Island Accident Scenario

Botros N. Hanna, Tran C. Son, Nam T. Dinh

ICONE 2020; V002T08A037doi:https://doi.org/10.1115/ICONE2020-16400

Abstract

View Articletitled, Benchmarking an AI-Guided Reasoning-Based Operator Support System on the Three Mile Island Accident Scenario

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Topics: Accidents , Computer programming

MELCOR Modeling of Combined Accident Tolerant Fuel and Reactor Core Isolation Cooling System Operation

Chris Faucett, Bradley Beeny, Karen Vierow Kirkland

ICONE 2020; V002T08A038doi:https://doi.org/10.1115/ICONE2020-16409

Abstract

View Articletitled, MELCOR Modeling of Combined Accident Tolerant Fuel and Reactor Core Isolation Cooling System Operation

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Topics: Accidents , Cooling systems , Fuels , Modeling

Development of New Organic Iodine Filter for FCVS

Kazuo Tominaga, Sohei Fukui, Motoi Tanaka, Tomoharu Hashimoto, Ryuichi Tayama

ICONE 2020; V002T08A039doi:https://doi.org/10.1115/ICONE2020-16416

Abstract

View Articletitled, Development of New Organic Iodine Filter for FCVS

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Topics: Filters , Silver , Water , Aerosols , Accidents , Aerosol containers , Boiling water reactors , Bonding , Containment , Electromagnetic scattering

Localization of Radiation Sources Using Randomly Distributed Detectors

Ke Li, Manchun Liang, Jie Yang, Dandan Yang, Hongmin Shen, Shuijun He, Fang Liu

ICONE 2020; V002T08A040doi:https://doi.org/10.1115/ICONE2020-16439

Abstract

View Articletitled, Localization of Radiation Sources Using Randomly Distributed Detectors

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Topics: Radiation sources , Sensors

Analysis of Transient Corium Pool Structure in the Lower Plenum of Reactor Vessel

Liang Chen, Hua Pang, Ximing Xie, Lei Zhong, Rong Cai

ICONE 2020; V002T08A041doi:https://doi.org/10.1115/ICONE2020-16470

Abstract

View Articletitled, Analysis of Transient Corium Pool Structure in the Lower Plenum of Reactor Vessel

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Topics: Accidents , Reactor vessels , Transients (Dynamics) , Vessels , Density , Heat flux , Heavy metals , China , Coolants , Critical heat flux

Reliability Assessment of NPP System for Risk Management Based on an Information Reasoning Methodology

Guixia Zhu, Tianmi Zhou, Yugang Qian, Chongchong Liu, Hongxing Lu

ICONE 2020; V002T08A042doi:https://doi.org/10.1115/ICONE2020-16482

Abstract

View Articletitled, Reliability Assessment of NPP System for Risk Management Based on an Information Reasoning Methodology

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Topics: Nuclear power stations , Reliability , Risk management , Fault diagnosis , Failure mechanisms , Modeling , Probability , Risk , Safety , System failures

Image Calibration Based on Dynamic No-Load Data for the ⁶⁰Co Gantry-Movable Dual-Projection Radiography Inspection System

Li Guangchao, Cong Peng, Guo Xiaojing, Chen Liu, Ni Minzi, Sun Yuewen, Zhao Zhongwei

ICONE 2020; V002T08A043doi:https://doi.org/10.1115/ICONE2020-16511

Abstract

View Articletitled, Image Calibration Based on Dynamic No-Load Data for the 60Co Gantry-Movable Dual-Projection Radiography Inspection System

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Topics: Calibration , Inspection , Stress

MELCOR Validation Study on Multi-Room Fire

David L. Y. Louie, Samir El-Darazi, Lyndsey M. Fyffe, James L. Clark

ICONE 2020; V002T08A044doi:https://doi.org/10.1115/ICONE2020-16562

Abstract

View Articletitled, MELCOR Validation Study on Multi-Room Fire

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Topics: Aerosols , Fire

MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant

Kenneth C. Wagner, David L. Y. Louie

ICONE 2020; V002T08A045doi:https://doi.org/10.1115/ICONE2020-16584

Abstract

View Articletitled, MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant

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Topics: Accidents , Fire , Explosions , Radioisotopes , Aerosols , Model development , Nuclear power stations , Probabilistic risk assessment , Safety , Spent nuclear fuels

Study on Preparation Process and Properties of High Hydrogen Content Concrete for Neutron Shielding

Li Yuanyuan, Pan Xiaoqiang, Huang Xiulin, Wu Ying, Yang Jing

ICONE 2020; V002T08A046doi:https://doi.org/10.1115/ICONE2020-16631

Abstract

View Articletitled, Study on Preparation Process and Properties of High Hydrogen Content Concrete for Neutron Shielding

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Topics: Boron , Cements (Adhesives) , Concretes , Hydrogen , Neutrons

Research on Cooling Water Source Safety Measures in Water Intake Engineering of Coastal NPP

Tang Ben-jing, Hou Shu-qiang, Wang Yan-long, Li Jing

ICONE 2020; V002T08A047doi:https://doi.org/10.1115/ICONE2020-16654

Abstract

View Articletitled, Research on Cooling Water Source Safety Measures in Water Intake Engineering of Coastal NPP

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Topics: Cooling , Nuclear power stations , Safety , Sewage , Shorelines , Water

A Novel System for Automated Proper Use Identification of Personal Protective Equipment in Decommissioning Site of Fukushima Daiichi Nuclear Power Station

Shi Chen, Kazuyuki Demachi

ICONE 2020; V002T08A048doi:https://doi.org/10.1115/ICONE2020-16707

Abstract

View Articletitled, A Novel System for Automated Proper Use Identification of Personal Protective Equipment in Decommissioning Site of Fukushima Daiichi Nuclear Power Station

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Topics: Fukushima nuclear disaster, Japan, 2011 , Nuclear decommissioning , Nuclear power stations

Development and Application of Dose Assessment Methodology During IS-LOCA in BWR Plant

Hironobu Iwanami, Tomoharu Hashimoto, Motoi Tanaka, Ryuichi Tayama, Satoshi Mizuno, Takashi Uemura

ICONE 2020; V002T08A049doi:https://doi.org/10.1115/ICONE2020-16721

Abstract

View Articletitled, Development and Application of Dose Assessment Methodology During IS-LOCA in BWR Plant

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Topics: Boiling water reactors , Accidents , Evaluation methods , Pipes , Nuclear fission , Water , Coolants , Design , Evacuations , Pressure

Development of Three-Dimensional Distribution Visualization Technology for Boron Using Energy Resolved Neutron-Imaging System (RADEN)

Yuta Abe, Yusuke Tsuchikawa, Tetsuya Kai, Yoshihiro Matsumoto, Joseph D. Parker, Takenao Shinohara, Yuji Ohishi, Takashi Kamiyama, Yuji Nagae, Ikken Sato

ICONE 2020; V002T08A050doi:https://doi.org/10.1115/ICONE2020-16723

Abstract

View Articletitled, Development of Three-Dimensional Distribution Visualization Technology for Boron Using Energy Resolved Neutron-Imaging System (RADEN)

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Topics: Boron , Fukushima nuclear disaster, Japan, 2011 , Imaging , Melting , Neutrons , Nuclear decommissioning , Nuclear power stations , Visualization

Development of a Water Injection System Fusible Plug for Severe Accidents at Nuclear Power Plants

Sei Hirano, Daisuke Hirasawa, Yoshihisa Kiyotoki, Keisuke Sakemura, Keiji Sasaki, Yuta Fukuda

ICONE 2020; V002T08A051doi:https://doi.org/10.1115/ICONE2020-16737

Abstract

View Articletitled, Development of a Water Injection System Fusible Plug for Severe Accidents at Nuclear Power Plants

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Topics: Accidents , Alloys , Fusibles (Textiles) , Nuclear power stations , Underground injection , Vessels

Effects of Pre-Crack Depth and Hydrogen Absorption on the Failure Strain of Zircaloy-4 Cladding Tubes Under Biaxial Strain Conditions

Feng Li, Takeshi Mihara, Yutaka Udagawa, Masaki Amaya

ICONE 2020; V002T08A052doi:https://doi.org/10.1115/ICONE2020-16738

Abstract

View Articletitled, Effects of Pre-Crack Depth and Hydrogen Absorption on the Failure Strain of Zircaloy-4 Cladding Tubes Under Biaxial Strain Conditions

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Topics: Absorption , Cladding systems (Building) , Failure , Fracture (Materials) , Hydrogen , Heat treating (Metalworking) , Accidents , Fuels , Manufacturing , Metals

Stratification and Heat Transfer of Molten Corium Pool for In-Vessel Retention

Qingan Xiang, Jian Deng, Dahuan Zhu, Xiaoli Wu, Jinsheng Bi, Baowen Chen, Rong Cai, Libo Qian, Yugao Ma

ICONE 2020; V002T08A053doi:https://doi.org/10.1115/ICONE2020-16742

Abstract

View Articletitled, Stratification and Heat Transfer of Molten Corium Pool for In-Vessel Retention

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Topics: Heat transfer , Heavy metals , Vessels

Determining Airborne Release Fraction From DOT 7A Drums Exposed to a Thermal Insult

Hector Mendoza, Victor G. Figueroa, Walter Gill, Scott Sanborn

ICONE 2020; V002T08A054doi:https://doi.org/10.1115/ICONE2020-16755

Abstract

View Articletitled, Determining Airborne Release Fraction From DOT 7A Drums Exposed to a Thermal Insult

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Topics: Accidents , Filters , Fire , Liquid pool fires , Radiant heat , Radioactive substances , Safety , Stress , Testing , Thermogravimetry

NICSim: Nuclear Instrumentation and Control Simulation for Evaluating Response to Cyber-Attacks

Mohamed S. El Genk, Timothy Schriener, Ragai Altamimi, Andrew Hahn, Christopher Lamb, Raymond Fasano

ICONE 2020; V002T08A055doi:https://doi.org/10.1115/ICONE2020-16756

Abstract

View Articletitled, NICSim: Nuclear Instrumentation and Control Simulation for Evaluating Response to Cyber-Attacks

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Topics: Computer security , Cyber-attacks , Instrumentation , Modeling , Nuclear power stations , Pressurized water reactors , Programmable controllers , Simulation

Heating Impact on Corrosion Mechanism of Carbon Steel Surrounded by Bentonite

Masao Uyama, Hiroyuki Saito, Tomoya Iioka

ICONE 2020; V002T08A056doi:https://doi.org/10.1115/ICONE2020-16765

Abstract

View Articletitled, Heating Impact on Corrosion Mechanism of Carbon Steel Surrounded by Bentonite

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Topics: Carbon steel , Corrosion , Electrochemical impedance spectroscopy , Heating , Radioactive wastes , Steel

Research on Nuclear Safety Video Display Unit Technology Based on Digital Twin

Yanqun Wu, Yang Zhao, Mingxing Liu, Wei Jiang, Qi Chen, Shun Wang, Hao Yan

ICONE 2020; V002T08A057doi:https://doi.org/10.1115/ICONE2020-16792

Abstract

View Articletitled, Research on Nuclear Safety Video Display Unit Technology Based on Digital Twin

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Topics: Safety

Use of Micro-Gravity Sensors for External Fluid Level Monitoring in Waste and Nuclear Related Applications

Jeff Ridgway, Bryant Slater

ICONE 2020; V002T08A058doi:https://doi.org/10.1115/ICONE2020-16810

Abstract

View Articletitled, Use of Micro-Gravity Sensors for External Fluid Level Monitoring in Waste and Nuclear Related Applications

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Topics: Fluids , Gravity (Force) , Sensors , Vessels , Leakage , Nuclear power , Sensor placement , Simulation , Accuracy and precision , Algorithms

Transient Analysis of Dedicated Pressure Relief Valve Under High-Pressure Condition in Severe Accident for Tianwan 56 Nuclear Power Plant

Youyou Xu, Jian Deng, Xiaoji Wang, Lingjun Wu, Ming Zhang, Libo Qian, Rong Cai, Lei Zhong, Zhengyu Du

ICONE 2020; V002T08A059doi:https://doi.org/10.1115/ICONE2020-16847

Abstract

View Articletitled, Transient Analysis of Dedicated Pressure Relief Valve Under High-Pressure Condition in Severe Accident for Tianwan 56 Nuclear Power Plant

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Topics: Accidents , Feedwater , High pressure (Physics) , Nuclear power stations , Relief valves , Transient analysis

Development of an Efficient Tool for Evaluating Dose at Through-Holes

Tatsuya Watanabe, Hironobu Iwanami, Tomoharu Hashimoto, Ryuichi Tayama

ICONE 2020; V002T08A060doi:https://doi.org/10.1115/ICONE2020-16931

Abstract

View Articletitled, Development of an Efficient Tool for Evaluating Dose at Through-Holes

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Topics: Cables , Computation , Computational methods , Design , Ducts , Electromagnetic scattering , Gamma rays , Nuclear power stations , Particulate matter , Radiation scattering

Numerical Analysis of Nuclear Facility Reinforced Concrete Wall and Roof Slab Behavior Under Close-in Explosions

Li Rongpeng, Li Yumin, Sui Chunguang, Jiang Di

ICONE 2020; V002T08A061doi:https://doi.org/10.1115/ICONE2020-16957

Abstract

View Articletitled, Numerical Analysis of Nuclear Facility Reinforced Concrete Wall and Roof Slab Behavior Under Close-in Explosions

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Topics: Computer simulation , Damage , Explosions , Numerical analysis , Reinforced concrete , Roofs , Slabs

Operating Plant Experience

Periodic Tests Improvement of Emergency Diesel Generator Units in Nuclear Power Plant

Liu Fei

ICONE 2020; V002T09A001doi:https://doi.org/10.1115/ICONE2020-16105

Abstract

View Articletitled, Periodic Tests Improvement of Emergency Diesel Generator Units in Nuclear Power Plant

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Topics: Diesel generators , Emergencies , Nuclear power stations

A New Data Driven Method for Monitoring a Large Number of Process Values and Detecting Anomaly Signs With a Two-Stage Model Composed of a Time Window Autoencoder and a Deviation Autoencoder

Susumu Naito, Yasunori Taguchi, Yuichi Kato, Kouta Nakata, Ryota Miyake, Isaku Nagura, Shinya Tominaga, Toshio Aoki

ICONE 2020; V002T09A002doi:https://doi.org/10.1115/ICONE2020-16150

Abstract

View Articletitled, A New Data Driven Method for Monitoring a Large Number of Process Values and Detecting Anomaly Signs With a Two-Stage Model Composed of a Time Window Autoencoder and a Deviation Autoencoder

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Topics: Boiling water reactors , Machine learning , Noise (Sound) , Nuclear power stations , Temperature , Time series , Transients (Dynamics)

Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV

Yupeng Cao, Yinbiao He, Yifeng Huang, Binxi Wang, Yan Yu, Hui Li, Hu Hui

ICONE 2020; V002T09A003doi:https://doi.org/10.1115/ICONE2020-16261

Abstract

View Articletitled, Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV

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Topics: Embrittlement , Irradiation (Radiation exposure) , Metals , Forging , Mechanical properties , China , Damage , Design , Fluence (Radiation measurement) , Fracture toughness

Technology of Phased Array Ultrasonic Testing on Jet Pump Beam Installed in Reactor Pressure Vessel

Shunsuke Sasaki, Setsu Yamamoto, Toshiaki Takada, Keiji Matsunaga, Kohei Uraguchi, Ikuko Kameyama

ICONE 2020; V002T09A004doi:https://doi.org/10.1115/ICONE2020-16386

Abstract

View Articletitled, Technology of Phased Array Ultrasonic Testing on Jet Pump Beam Installed in Reactor Pressure Vessel

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Topics: Inspection , Jet pumps , Reactor vessels , Ultrasonic testing

Guided Waves in Pitch-Catch Configuration: A Theoretical Framework to Steer Toward Experimental Tests

Francesco Cordella, Mauro Cappelli, Francesco Bertoncini

ICONE 2020; V002T09A005doi:https://doi.org/10.1115/ICONE2020-16436

Abstract

View Articletitled, Guided Waves in Pitch-Catch Configuration: A Theoretical Framework to Steer Toward Experimental Tests

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Topics: Waves

Nuclear Regulatory Acceptance of Certified Process Data Reconciliation (CPDR)

Andy Jansky, Magnus Langenstein

ICONE 2020; V002T09A006doi:https://doi.org/10.1115/ICONE2020-16525

Abstract

View Articletitled, Nuclear Regulatory Acceptance of Certified Process Data Reconciliation (CPDR)

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Topics: Maintenance , Measurement uncertainty , Municipal solid wastes , Nuclear power stations , Optimization , Power uprate , Public utilities , Risk , Safety , Solid wastes

Improvement of the Evaluation Accuracy for the Diameter Prediction of the CANDU Pressure Tubes

Jong Yeob Jung

ICONE 2020; V002T09A007doi:https://doi.org/10.1115/ICONE2020-16590

Abstract

View Articletitled, Improvement of the Evaluation Accuracy for the Diameter Prediction of the CANDU Pressure Tubes

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Topics: Pressure , Creep , Fuels , Irradiation (Radiation exposure) , Modeling , Cooling , Deformation , Flow (Dynamics) , Heat , Heat transfer

Artificial Neural Network Model for Diagnosing the Performance and the Conditions of Air-Operated Valves

Taeyun Kim, Jangbom Chai, Chanwoo Lim, Ilyoung Han

ICONE 2020; V002T09A008doi:https://doi.org/10.1115/ICONE2020-16636

Abstract

View Articletitled, Artificial Neural Network Model for Diagnosing the Performance and the Conditions of Air-Operated Valves

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Topics: Artificial neural networks , Valves

Simulation for Predicting Condition of Plant Equipment

Shoichi Kashiwase, Kenji Osaki, Makoto Hatakeyama, Tomokazu Kaneko

ICONE 2020; V002T09A009doi:https://doi.org/10.1115/ICONE2020-16840

Abstract

View Articletitled, Simulation for Predicting Condition of Plant Equipment

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Topics: Engines , Motors , Pumps , Simulation , Valves

Convolutional Neural Network Considering the Effects of Noise for Bearing Fault Diagnosis

Ilyoung Han, Jangbom Chai, Chanwoo Lim, Taeyun Kim

ICONE 2020; V002T09A010doi:https://doi.org/10.1115/ICONE2020-16861

Abstract

View Articletitled, Convolutional Neural Network Considering the Effects of Noise for Bearing Fault Diagnosis

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Topics: Artificial neural networks , Bearings , Fault diagnosis , Noise (Sound) , Signals

Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Line Down Horizontal Elbow

Yue Zou, Brian Derreberry

ICONE 2020; V002T09A011doi:https://doi.org/10.1115/ICONE2020-16948

Abstract

View Articletitled, Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Line Down Horizontal Elbow

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Topics: Coolants , Fatigue , Pressurized water reactors

Probabilistic Risk Assessments

Study on Methodology and Application of Seismic-Induced Flood Level 2 PSA for PWR in China

Liu Yu, Li Wenjing, Yu Yun

ICONE 2020; V002T10A001doi:https://doi.org/10.1115/ICONE2020-16076

Abstract

View Articletitled, Study on Methodology and Application of Seismic-Induced Flood Level 2 PSA for PWR in China

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Topics: China , Floods , Pressurized water reactors

Multi-Group Staggered Tests for Highly Redundant Systems

Shota Soga

ICONE 2020; V002T10A002doi:https://doi.org/10.1115/ICONE2020-16172

Abstract

View Articletitled, Multi-Group Staggered Tests for Highly Redundant Systems

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Topics: Boiling water reactors , Failure , Notch testing , Reactor protection systems , Redundancy (Engineering) , Reliability , Risk , Rods , Safety

Development of Advanced Fire Zone Model Applicable to Fire PRA for Nuclear Power Plant

Junghoon Ji, Koji Shirai, Koji Tasaka, Toshiko Udagawa

ICONE 2020; V002T10A003doi:https://doi.org/10.1115/ICONE2020-16201

Abstract

View Articletitled, Development of Advanced Fire Zone Model Applicable to Fire PRA for Nuclear Power Plant

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Topics: Feedback , Fire , Heat , Nuclear power stations , Simulation , Thermal radiation

The Fire Event Analysis for Fire Frequency Estimation on Japanese Nuclear Power Plant

Yasunori Nagata, Tsuyoshi Uchida, Koji Shirai

ICONE 2020; V002T10A004doi:https://doi.org/10.1115/ICONE2020-16209

Abstract

View Articletitled, The Fire Event Analysis for Fire Frequency Estimation on Japanese Nuclear Power Plant

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Topics: Event history analysis , Fire , Ignition , Nuclear power stations

Single Point Vulnerabilities Management Strategy of Qinshan Nuclear Power Plant

Wang Hanlin

ICONE 2020; V002T10A005doi:https://doi.org/10.1115/ICONE2020-16491

Abstract

View Articletitled, Single Point Vulnerabilities Management Strategy of Qinshan Nuclear Power Plant

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Topics: Maintenance , Nuclear power stations , Reliability , Risk management , Stress , Trains

Hazard Analysis of Digital Engineered Safety Features Actuation System in Advanced Nuclear Power Plants Using a Redundancy-Guided Approach

Han Bao, Tate Shorthill, Hongbin Zhang

ICONE 2020; V002T10A006doi:https://doi.org/10.1115/ICONE2020-16573

Abstract

View Articletitled, Hazard Analysis of Digital Engineered Safety Features Actuation System in Advanced Nuclear Power Plants Using a Redundancy-Guided Approach

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Topics: Failure , Hazard analysis , Nuclear power stations , Redundancy (Engineering) , Safety

Level 2 PSA Overview of HPR1000 Nuclear Power Plant

Wang Ziguan, Lu Fang, Yang Benlin, Chen Shi, Hu Lingsheng

ICONE 2020; V002T10A007doi:https://doi.org/10.1115/ICONE2020-16623

Abstract

View Articletitled, Level 2 PSA Overview of HPR1000 Nuclear Power Plant

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Topics: Accidents , Nuclear power stations

Technical Maturity Assessment of Risk-Informed Safety Analysis Tools

Yong-Joon Choi

ICONE 2020; V002T10A008doi:https://doi.org/10.1115/ICONE2020-16700

Abstract

View Articletitled, Technical Maturity Assessment of Risk-Informed Safety Analysis Tools

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Topics: Light water reactors , Risk , Safety

Risk-Informed Analysis for Accident Tolerant Fuel in Pressurized Water Reactors

Zhegang Ma, Carlo Parisi, Cliff Davis, Sai Zhang, Hongbin Zhang

ICONE 2020; V002T10A009doi:https://doi.org/10.1115/ICONE2020-16761

Abstract

View Articletitled, Risk-Informed Analysis for Accident Tolerant Fuel in Pressurized Water Reactors

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Topics: Accidents , Fuels , Light water reactors , Pressurized water reactors , Risk

Inter-Unit Common Cause Failure Analysis Based on Data From Intra-Unit Cases

Eishiro Higo, Shota Soga, Hiromichi Miura

ICONE 2020; V002T10A010doi:https://doi.org/10.1115/ICONE2020-16819

Abstract

View Articletitled, Inter-Unit Common Cause Failure Analysis Based on Data From Intra-Unit Cases

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Topics: Failure , Failure analysis , Databases , Probability , Nuclear power stations , Performance , Probabilistic risk assessment

Research on Probabilistic Safety Assessment (PSA) Method of Safety Class Distributed Control System (DCS) in Nuclear Power Plant Based on Fuzzy Markov Process

Tian Xufeng, Yan Hao

ICONE 2020; V002T10A011doi:https://doi.org/10.1115/ICONE2020-16835

Abstract

View Articletitled, Research on Probabilistic Safety Assessment (PSA) Method of Safety Class Distributed Control System (DCS) in Nuclear Power Plant Based on Fuzzy Markov Process

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Topics: Control systems , Markov processes , Nuclear power stations , Probabilistic safety assessment , Safety

Applicability of FLASH-CAT Model to Cable Tray Fire Modeling in Zone Model BRI2002

Koji Shirai, Koji Tasaka, Toshiko Udagawa

ICONE 2020; V002T10A012doi:https://doi.org/10.1115/ICONE2020-16874

Abstract

View Articletitled, Applicability of FLASH-CAT Model to Cable Tray Fire Modeling in Zone Model BRI2002

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Topics: Cables , Fire , Heat , Modeling

Incorporating FLEX Strategies in Multi-Unit Probabilistic Risk Assessment

Sai Zhang, Zhegang Ma

ICONE 2020; V002T10A013doi:https://doi.org/10.1115/ICONE2020-16889

Abstract

View Articletitled, Incorporating FLEX Strategies in Multi-Unit Probabilistic Risk Assessment

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Topics: Probabilistic risk assessment , Reliability

Probability of Rupture for WWER-1000 Main Piping

Yaroslav Dubyk, Maksym Zarazovskii, Sergii Ageiev, Vladislav Filonov

ICONE 2020; V002T10A014doi:https://doi.org/10.1115/ICONE2020-16897

Abstract

View Articletitled, Probability of Rupture for WWER-1000 Main Piping

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Topics: Leakage , Pipes , Probability , Rupture , Stress , Fracture (Materials) , Accounting , Flow (Dynamics) , Fracture toughness , Nuclear power stations

Considerations for Development of Probabilistic Assessments for Nuclear Systems and Components

Mahesh Pandey, Bogdan Wasiluk

ICONE 2020; V002T10A015doi:https://doi.org/10.1115/ICONE2020-16935

Abstract

View Articletitled, Considerations for Development of Probabilistic Assessments for Nuclear Systems and Components

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Topics: Defense industry , Failure , Nuclear industry , Probability , Reliability , Risk , Safety , Transparency

SMR and Advanced Reactors

Guidance for Developing Fuel Design Limit of High Temperature Gas-Cooled Reactor

Hiroyuki Sato, Takeshi Aoki, Hirofumi Ohashi

ICONE 2020; V002T11A001doi:https://doi.org/10.1115/ICONE2020-16050

Abstract

View Articletitled, Guidance for Developing Fuel Design Limit of High Temperature Gas-Cooled Reactor

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Topics: Design , Fuels , Safety , Very high temperature reactors

Modeling the Molten Salt Reactor Experiment With the GOTHIC Code

Rodney Harvill, Jeff Lane, John Link, Anita Gates, Tom Kindred

ICONE 2020; V002T11A002doi:https://doi.org/10.1115/ICONE2020-16058

Abstract

View Articletitled, Modeling the Molten Salt Reactor Experiment With the GOTHIC Code

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Topics: Design , Modeling , Molten salt reactors , Heat , Fuels , Neutrons , Transients (Dynamics) , Flow (Dynamics) , Fluids , Nuclear fission

Development of a Flow Network Calculation Code (FNCC) for High Temperature Gas-Cooled Reactors (HTGRs)

Takeshi Aoki, Kazuyoshi Isaka, Hiroyuki Sato, Hirofumi Ohashi

ICONE 2020; V002T11A003doi:https://doi.org/10.1115/ICONE2020-16196

Abstract

View Articletitled, Development of a Flow Network Calculation Code (FNCC) for High Temperature Gas-Cooled Reactors (HTGRs)

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Topics: Flow (Dynamics) , Very high temperature reactors

Methodology Development for Transient Flow Distribution Analysis in High Temperature Gas-Cooled Reactor

Takeshi Aoki, Hiroyuki Sato, Hirofumi Ohashi

ICONE 2020; V002T11A004doi:https://doi.org/10.1115/ICONE2020-16199

Abstract

View Articletitled, Methodology Development for Transient Flow Distribution Analysis in High Temperature Gas-Cooled Reactor

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Topics: Unsteady flow , Very high temperature reactors

HTGR Power-Level Control Only by Regulating Helium Flowrate

Zhe Dong

ICONE 2020; V002T11A005doi:https://doi.org/10.1115/ICONE2020-16218

Abstract

View Articletitled, HTGR Power-Level Control Only by Regulating Helium Flowrate

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Topics: Helium , Stability , Very high temperature reactors

Walk-Away Safe Modular Small and Micro Reactors for Electricity Generation and Process Heat

Mohamed S. El-Genk, Timothy Schriener

ICONE 2020; V002T11A006doi:https://doi.org/10.1115/ICONE2020-16238

Abstract

View Articletitled, Walk-Away Safe Modular Small and Micro Reactors for Electricity Generation and Process Heat

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Topics: Electric power generation , Heat , Safety

Simulation Analysis on the Pressurizer Degassing Sub-System of Module Small Reactor (ACP100)

Cai Zhiyun, Ren Yun, Lai Jianyong, Zhang Yulong, Liu Hang, Liu Xianghong, Liu Minghao, Ye Zhu

ICONE 2020; V002T11A007doi:https://doi.org/10.1115/ICONE2020-16341

Abstract

View Articletitled, Simulation Analysis on the Pressurizer Degassing Sub-System of Module Small Reactor (ACP100)

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Topics: Equilibrium (Physics) , Simulation analysis , Transients (Dynamics) , Flow (Dynamics) , Nuclear reactor coolants , Pressure , Safety , Valves , Water , Boundary-value problems

Optimal Design for Helium Cooled Solid Breeder Blanket of CFETR

Jose A. Nogueron, Zhang Baorui, Zhou Zhiwei

ICONE 2020; V002T11A008doi:https://doi.org/10.1115/ICONE2020-16345

Abstract

View Articletitled, Optimal Design for Helium Cooled Solid Breeder Blanket of CFETR

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Topics: Cooling , Design , Helium , Tokamaks , Computational fluid dynamics , Bridges (Structures) , China , Combustion , Computer software , Cycles

Analysis of Gas Entrainment Phenomenon From Free Liquid Surface for a Sodium-Cooled Fast Reactor Design: Validation of Velocity Profile and Strouhal Number in a Flow Field

Mao Uchida, Moe Hirakawa, Aaru Sano, Keisuke Inoue, Takaaki Sakai, Toshiki Ezure, Masaaki Tanaka

ICONE 2020; V002T11A009doi:https://doi.org/10.1115/ICONE2020-16418

Abstract

View Articletitled, Analysis of Gas Entrainment Phenomenon From Free Liquid Surface for a Sodium-Cooled Fast Reactor Design: Validation of Velocity Profile and Strouhal Number in a Flow Field

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Topics: Design , Flow (Dynamics) , Sodium fast reactors , Vortices , Computational fluid dynamics , Reactor vessels , Water , Coolants , Evaluation methods , Particulate matter