1-20 of 23
System failures
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

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

Available to Purchase

Churan Feng, Jingxiang Zhan, Lin Yan, Yiming Wang, Jinghua Zhou
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135096
https://doi.org/10.1115/ICONE31-135096
View Paper titled, Typical Sequence Analysis of SLOCA Accidents in a Third Generation Nuclear Power Plant Based on RISMC Method
Open the PDF for Typical Sequence Analysis of SLOCA Accidents in a Third Generation Nuclear Power Plant Based on RISMC Method in another window
Topics: Accidents, Nuclear power stations, Safety, Failure, Damage, Design, Feedwater, Probability, Risk, Uncertainty
Proceedings Papers

Methodology for Acquiring Reliability Data in Novel Nuclear Energy Systems Using a Non-Homogeneous Poisson Process

Available to Purchase

Zefeng Li, Pu Chen, Tao Liu
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A046, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134981
https://doi.org/10.1115/ICONE31-134981
View Paper titled, Methodology for Acquiring Reliability Data in Novel Nuclear Energy Systems Using a Non-Homogeneous Poisson Process
Open the PDF for Methodology for Acquiring Reliability Data in Novel Nuclear Energy Systems Using a Non-Homogeneous Poisson Process in another window
Topics: Nuclear power, Reliability, Maintenance, Failure, Modeling, Bayesian network, Chain, Nuclear power plant maintenance, Nuclear power stations, Safety
Proceedings Papers

Research Methods and Protective Measures for Internal Flooding Analysis of Nuclear Islands

Available to Purchase

Guang Du, Danfeng Zhao, Daping Lin, Xiaoxia Chen
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135047
https://doi.org/10.1115/ICONE31-135047
View Paper titled, Research Methods and Protective Measures for Internal Flooding Analysis of Nuclear Islands
Open the PDF for Research Methods and Protective Measures for Internal Flooding Analysis of Nuclear Islands in another window
Topics: Floods, Nuclear power stations, Design, Hazards, Safety, Water, Computational methods, Engineering design, Evaluation methods, Nuclear power
Proceedings Papers

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

Available to Purchase

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
Open the PDF for The Development and Application of Real-Time Risk Monitor System Based on Level 2 PSA for NPP in another window
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

Available to Purchase

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
Open the PDF for Reliability Assessment of NPP System for Risk Management Based on an Information Reasoning Methodology in another window
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

Available to Purchase

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
Open the PDF for Uncertainty Analysis of Scaling Calculations From LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization Applying to a Four-Loop PWR in another window
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

Available to Purchase

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
Open the PDF for Evaluation of Core Damage Frequency of High Flux Engineering Test Reactor From Internal Events in another window
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

Available to Purchase

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
Open the PDF for Verification of FPGA Based NPP I&C Systems Considering Multiple Faults: Technique and Automation Tool in another window
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

Available to Purchase

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
Open the PDF for Cyber Security Assessment of Component Off-the-Shelf Based NPP I&C System Using IMECA Technique in another window
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

Available to Purchase

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
Open the PDF for RELAP5 Code Uncertainty Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure in another window
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

Available to Purchase

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
Open the PDF for Reliability of PCCS in AP1000 Based on Accident Development in another window
Topics: Accidents, Reliability, Containment, Heat, Pressure, Failure, Nuclear power stations, Steam, System failures, Temperature
Proceedings Papers

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

Available to Purchase

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
Open the PDF for Development of Steam Generator Model Using RELAP5 to Simulate Two-Phase Natural Circulation for Pressurized Water Reactor in another window
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

Available to Purchase

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
Open the PDF for Sensitivity Analyses of a Simulation Model for Estimating Fiber-Induced Sump Screen and Core Failure Rates in another window
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

Available to Purchase

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
Open the PDF for Study of Decay Heat Removal Approach for Advanced Passive PWR During Station Blackout in another window
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

Available to Purchase

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

Modified Layer of Protection Analysis for Nuclear Safety Assessment

Available to Purchase

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
Open the PDF for Modified Layer of Protection Analysis for Nuclear Safety Assessment in another window
Topics: Safety, Chemical processes, Failure, Probability, Fire, Probabilistic risk assessment, Risk, System failures
Proceedings Papers

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

Available to Purchase

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
Open the PDF for Reliability Research of Power-Supply System in Nuclear Power Plant Based on Markov Theory and Bayes Network in another window
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

Available to Purchase

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
Open the PDF for Experimental and Computational Studies of LNPP-2 Passive System for Severe Accident Management in another window
Topics: Accident management, Accidents, Boilers, Circuits, Containment, Cooling, Design, Electricity (Physics), Emissions, Experimental analysis
Proceedings Papers

Quantification of Fault Tree Models for Initiating Events

Available to Purchase

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
Open the PDF for Quantification of Fault Tree Models for Initiating Events in another window
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

Available to Purchase

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
Open the PDF for Creation of Automatic System for Monitoring, Forecasting and Control of Condition of Lead-Bismuth (Lead) Coolant and Surfaces of Circuits of Nuclear Power Plants in another window
Topics: Circuits, Coolants, Nuclear power stations, Safety, Accidents, Design, Fast neutron reactors, Fuels, Heat, Pumps