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Proceedings Papers

The Development and Application of Real-Time Risk Monitor System Based on Level 2 PSA for NPP

Wenjing Li, Yu Liu, Wei Wei, Xinli Yu
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A022, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91785
https://doi.org/10.1115/ICONE29-91785
View Paper titled, The Development and Application of Real-Time Risk Monitor System Based on Level 2 PSA for NPP
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Topics: Nuclear power stations, Risk monitoring, Risk, Risk management, Safety, Economics , Optimization, China, Damage, Failure
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16482
https://doi.org/10.1115/ICONE2020-16482
View Paper titled, 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
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81920
https://doi.org/10.1115/ICONE26-81920
View Paper titled, Uncertainty Analysis of Scaling Calculations From LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization Applying to a Four-Loop PWR
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Topics: Boilers, Pressurized water reactors, Uncertainty analysis, Uncertainty, Accidents, Accident management, Coolants, High pressure (Physics), Reliability, 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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81176
https://doi.org/10.1115/ICONE26-81176
View Paper titled, Evaluation of Core Damage Frequency of High Flux Engineering Test Reactor From Internal Events
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Topics: Damage, Construction, Design, Safety, Computer software, Coolants, Modeling, Nuclear reactors, 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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67065
https://doi.org/10.1115/ICONE25-67065
View Paper titled, Verification of FPGA Based NPP I&C Systems Considering Multiple Faults: Technique and Automation Tool
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67120
https://doi.org/10.1115/ICONE25-67120
View Paper titled, Cyber Security Assessment of Component Off-the-Shelf Based NPP I&C System Using IMECA Technique
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Topics: Computer security, Nuclear power stations, Safety, Computer software, Countermeasures, Databases, Failure, Joining, Security, Decision making
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60155
https://doi.org/10.1115/ICONE24-60155
View Paper titled, Reliability of PCCS in AP1000 Based on Accident Development
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Topics: Accidents, Reliability, Containment, Heat, Pressure, Failure, Nuclear power stations, Steam, System failures, Temperature
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60525
https://doi.org/10.1115/ICONE24-60525
View Paper titled, RELAP5 Code Uncertainty Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure
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Topics: Accident management, Boilers, Uncertainty analysis, Uncertainty, Accidents, Cladding systems (Building), Coolants, Experimental analysis, High pressure (Physics), Reliability
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30828
https://doi.org/10.1115/ICONE22-30828
View Paper titled, Modified Layer of Protection Analysis for Nuclear Safety Assessment
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Topics: Safety, Chemical processes, Failure, Probability, Fire, Probabilistic risk assessment, Risk, System failures
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30703
https://doi.org/10.1115/ICONE22-30703
View Paper titled, Development of Steam Generator Model Using RELAP5 to Simulate Two-Phase Natural Circulation for Pressurized Water Reactor
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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
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A026, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30917
https://doi.org/10.1115/ICONE22-30917
View Paper titled, Sensitivity Analyses of a Simulation Model for Estimating Fiber-Induced Sump Screen and Core Failure Rates
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Topics: Failure, Fibers, Sensitivity analysis, Simulation models, Computer simulation, Probability, Uncertainty, Errors, Physics, Power stations
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30698
https://doi.org/10.1115/ICONE22-30698
View Paper titled, Study of Decay Heat Removal Approach for Advanced Passive PWR During Station Blackout
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Topics: Heat, Pressurized water reactors, Containment, Failure, Safety, Accidents, Reactor vessels, System failures, Cooling systems, Design
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30559
https://doi.org/10.1115/ICONE22-30559
View Paper titled, 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
Open the PDF for 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 in another window
Topics: Accident management, Boilers, Uncertainty, Accidents, Condensation, Coolants, Flow (Dynamics), High pressure (Physics), Pressure, Simulation analysis
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29165
https://doi.org/10.1115/ICONE18-29165
View Paper titled, Reliability Research of Power-Supply System in Nuclear Power Plant Based on Markov Theory and Bayes Network
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29857
https://doi.org/10.1115/ICONE18-29857
View Paper titled, Experimental and Computational Studies of LNPP-2 Passive System for Severe Accident Management
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29753
https://doi.org/10.1115/ICONE18-29753
View Paper titled, Quantification of Fault Tree Models for Initiating Events
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75504
https://doi.org/10.1115/ICONE17-75504
View Paper titled, Creation of Automatic System for Monitoring, Forecasting and Control of Condition of Lead-Bismuth (Lead) Coolant and Surfaces of Circuits of Nuclear Power Plants
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48862
https://doi.org/10.1115/ICONE16-48862
View Paper titled, Digital I&C Operating Experience in the US
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22248
https://doi.org/10.1115/ICONE10-22248
View Paper titled, Development of Reliability Function and Failure Rate Considering Information of Censored Data
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49287
https://doi.org/10.1115/ICONE12-49287
View Paper titled, The Probability and Management of Human Error
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Topics: Errors, Probability, Failure, Accidents, Nuclear power, Risk, Safety, System failures