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Proceedings Papers

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

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

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A042, August 4–5, 2020

Paper No: ICONE2020-16482

DOI: https://doi.org/10.1115/ICONE2020-16482

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

Proceedings Papers

Evaluation of Core Damage Frequency of High Flux Engineering Test Reactor From Internal Events

Jinlin Liu, Wanhong Wang, Changhong Peng, Yun Guo

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A006, July 22–26, 2018

Paper No: ICONE26-81176

DOI: https://doi.org/10.1115/ICONE26-81176

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Topics: Damage, Construction, Design, Safety, Computer software, Coolants, Modeling, Nuclear reactors, Reliability, System failures

Proceedings Papers

Uncertainty Analysis of Scaling Calculations From LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization Applying to a Four-Loop PWR

Ikuo Kinoshita

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A012, July 22–26, 2018

Paper No: ICONE26-81920

DOI: https://doi.org/10.1115/ICONE26-81920

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Topics: Boilers, Pressurized water reactors, Uncertainty analysis, Uncertainty, Accidents, Accident management, Coolants, High pressure (Physics), Reliability, System failures

Proceedings Papers

Verification of FPGA Based NPP I&C Systems Considering Multiple Faults: Technique and Automation Tool

Alexander Yasko, Eugene Babeshko, Vyacheslav Kharchenko

Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A033, July 2–6, 2017

Paper No: ICONE25-67065

DOI: https://doi.org/10.1115/ICONE25-67065

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Topics: Nuclear power stations, Safety, Failure mechanisms, Reliability, Engineering standards, Failure, Failure mode and effects analysis, Gates (Closures), Instrumentation, Integrated circuits

Proceedings Papers

Cyber Security Assessment of Component Off-the-Shelf Based NPP I&C System Using IMECA Technique

Ilona Zelinko, Vyacheslav Kharchenko, Konstantin Leontiev

Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A034, July 2–6, 2017

Paper No: ICONE25-67120

DOI: https://doi.org/10.1115/ICONE25-67120

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Topics: Computer security, Nuclear power stations, Safety, Computer software, Countermeasures, Databases, Failure, Joining, Security, Decision making

Proceedings Papers

RELAP5 Code Uncertainty Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure

Ikuo Kinoshita, Toshihide Torige

Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A035, June 26–30, 2016

Paper No: ICONE24-60525

DOI: https://doi.org/10.1115/ICONE24-60525

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Topics: Accident management, Boilers, Uncertainty analysis, Uncertainty, Accidents, Cladding systems (Building), Coolants, Experimental analysis, High pressure (Physics), Reliability

Proceedings Papers

Reliability of PCCS in AP1000 Based on Accident Development

Yu Yu, Shengfei Wang, Fenglei Niu

Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T14A007, June 26–30, 2016

Paper No: ICONE24-60155

DOI: https://doi.org/10.1115/ICONE24-60155

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Topics: Accidents, Reliability, Containment, Heat, Pressure, Failure, Nuclear power stations, Steam, System failures, Temperature

Proceedings Papers

RELAP5 Code Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure: Investigation on Base Case Result Appropriate for the Best Estimate Plus Uncertainty (BEPU) Application

Ikuo Kinoshita, Toshihide Torige, Michio Murase, Yoshitaka Yoshida, Takeshi Takeda, Akira Satou, Hideo Nakamura

Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A022, July 7–11, 2014

Paper No: ICONE22-30559

DOI: https://doi.org/10.1115/ICONE22-30559

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Topics: Accident management, Boilers, Uncertainty, Accidents, Condensation, Coolants, Flow (Dynamics), High pressure (Physics), Pressure, Simulation analysis

Proceedings Papers

Modified Layer of Protection Analysis for Nuclear Safety Assessment

Seyed Mohsen Gheyasi, Mohammad Pourgol-Mohammad

Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A034, July 7–11, 2014

Paper No: ICONE22-30828

DOI: https://doi.org/10.1115/ICONE22-30828

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Topics: Safety, Chemical processes, Failure, Probability, Fire, Probabilistic risk assessment, Risk, System failures

Proceedings Papers

Study of Decay Heat Removal Approach for Advanced Passive PWR During Station Blackout

Jie Zou, Lili Tong, Xuewu Cao

Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A047, July 7–11, 2014

Paper No: ICONE22-30698

DOI: https://doi.org/10.1115/ICONE22-30698

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Topics: Heat, Pressurized water reactors, Containment, Failure, Safety, Accidents, Reactor vessels, System failures, Cooling systems, Design

Proceedings Papers

Development of Steam Generator Model Using RELAP5 to Simulate Two-Phase Natural Circulation for Pressurized Water Reactor

Shinya Miyata, Satoru Kamohara, Wataru Sakuma, Hiroaki Nishi

Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A024, July 7–11, 2014

Paper No: ICONE22-30703

DOI: https://doi.org/10.1115/ICONE22-30703

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Topics: Boilers, Pressurized water reactors, Pressure, Coolants, Cooling, Accidents, Condensation, Design, Safety, Secondary cells

Proceedings Papers

Sensitivity Analyses of a Simulation Model for Estimating Fiber-Induced Sump Screen and Core Failure Rates

David Morton, Bruce Letellier, Jeremy Tejada, David Johnson, Zahra Mohaghegh, Ernie Kee, Vera Moiseytseva, Seyed Reihani, Alexander Zolan

Paper No: ICONE22-30917

DOI: https://doi.org/10.1115/ICONE22-30917

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Topics: Failure, Fibers, Sensitivity analysis, Simulation models, Computer simulation, Probability, Uncertainty, Errors, Physics, Power stations

Proceedings Papers

Reliability Research of Power-Supply System in Nuclear Power Plant Based on Markov Theory and Bayes Network

Li Zhen, Xinli Sun, Jian Ding, Xia Zhang, Xinghui Cai

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 375-380, May 17–21, 2010

Paper No: ICONE18-29165

DOI: https://doi.org/10.1115/ICONE18-29165

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Topics: Nuclear power stations, Reliability, Probability, Fault diagnosis, System failures

Proceedings Papers

Experimental and Computational Studies of LNPP-2 Passive System for Severe Accident Management

Valery G. Sidorov, Vladimir Bezlepkin, Sergej Alekseev, Sergey Semashko, Igor Ivkov, Vladimir Kukhtevich

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 589-596, May 17–21, 2010

Paper No: ICONE18-29857

DOI: https://doi.org/10.1115/ICONE18-29857

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Topics: Accident management, Accidents, Boilers, Circuits, Containment, Cooling, Design, Electricity (Physics), Emissions, Experimental analysis

Proceedings Papers

Quantification of Fault Tree Models for Initiating Events

Donald J. Wakefield, Steven A. Epstein

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 543-547, May 17–21, 2010

Paper No: ICONE18-29753

DOI: https://doi.org/10.1115/ICONE18-29753

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Topics: Computation, Cooling, Damage, Nuclear power stations, System failures, Trains, Water

Proceedings Papers

Creation of Automatic System for Monitoring, Forecasting and Control of Condition of Lead-Bismuth (Lead) Coolant and Surfaces of Circuits of Nuclear Power Plants

P. N. Martynov, R. Sh. Askhadullin, A. A. Simakov, A. Yu. Chaban’, M. E. Chernov, V. S. Lanskikh, A. Yu. Legkikh

Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 549-554, July 12–16, 2009

Paper No: ICONE17-75504

DOI: https://doi.org/10.1115/ICONE17-75504

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Topics: Circuits, Coolants, Nuclear power stations, Safety, Accidents, Design, Fast neutron reactors, Fuels, Heat, Pumps

Proceedings Papers

Digital I&C Operating Experience in the US

Bruce Geddes, Ray Torok

Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 1009-1018, May 11–15, 2008

Paper No: ICONE16-48862

DOI: https://doi.org/10.1115/ICONE16-48862

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Topics: Computer software, Corrective actions, Databases, Defense industry, Electricity (Physics), Failure, Failure mechanisms, Fault tolerance, Hardware, Instrumentation

Proceedings Papers

Development of Reliability Function and Failure Rate Considering Information of Censored Data

Kwang-Won Ahn, Yoonik Kim, Chang-Hyun Chung, Kil-Yoo Kim

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 753-758, April 14–18, 2002

Paper No: ICONE10-22248

DOI: https://doi.org/10.1115/ICONE10-22248

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Topics: Failure, Reliability, Accidents, Biomedicine, Engines, Motors, Nuclear power stations, Simulation, System failures, Valves

Proceedings Papers

The Probability and Management of Human Error

Romney D. Duffey, John W. Saull

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 133-137, April 25–29, 2004

Paper No: ICONE12-49287

DOI: https://doi.org/10.1115/ICONE12-49287

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Topics: Errors, Probability, Failure, Accidents, Nuclear power, Risk, Safety, System failures

NARROW

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

Evaluation of Core Damage Frequency of High Flux Engineering Test Reactor From Internal Events

Uncertainty Analysis of Scaling Calculations From LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization Applying to a Four-Loop PWR

Verification of FPGA Based NPP I&C Systems Considering Multiple Faults: Technique and Automation Tool

Cyber Security Assessment of Component Off-the-Shelf Based NPP I&C System Using IMECA Technique

RELAP5 Code Uncertainty Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure

Reliability of PCCS in AP1000 Based on Accident Development

RELAP5 Code Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure: Investigation on Base Case Result Appropriate for the Best Estimate Plus Uncertainty (BEPU) Application

Modified Layer of Protection Analysis for Nuclear Safety Assessment

Study of Decay Heat Removal Approach for Advanced Passive PWR During Station Blackout

Development of Steam Generator Model Using RELAP5 to Simulate Two-Phase Natural Circulation for Pressurized Water Reactor

Sensitivity Analyses of a Simulation Model for Estimating Fiber-Induced Sump Screen and Core Failure Rates

Reliability Research of Power-Supply System in Nuclear Power Plant Based on Markov Theory and Bayes Network

Experimental and Computational Studies of LNPP-2 Passive System for Severe Accident Management

Quantification of Fault Tree Models for Initiating Events

Creation of Automatic System for Monitoring, Forecasting and Control of Condition of Lead-Bismuth (Lead) Coolant and Surfaces of Circuits of Nuclear Power Plants

Digital I&C Operating Experience in the US

Development of Reliability Function and Failure Rate Considering Information of Censored Data

The Probability and Management of Human Error

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