1-8 of 8
Reliability
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
Journal Articles

An estimation method for bias error of measurements by utilizing process data, an incidence matrix and a reference instrument for data validation and reconciliation: Part 2 Extension to the energy balance relation

Accepted Manuscript
Akinori Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1037
https://doi.org/10.1115/1.4066344
Published Online: August 26, 2024
View Article titled, An estimation method for bias error of measurements by utilizing process data, an incidence matrix and a reference instrument for data validation and reconciliation: Part 2 Extension to the energy balance relation
Open the PDF for An estimation method for bias error of measurements by utilizing process data, an incidence matrix and a reference instrument for data validation and reconciliation: Part 2 Extension to the energy balance relation in another window
Topics: Energy budget (Physics), Errors, Instrumentation, Measurement uncertainty, Flow (Dynamics), Reliability, Digital twin, Energy conservation, Feedwater, Internet of things
Journal Articles

High Reliability Microgrid for a Nuclear Facility Emergency Power Supply

Gerard R. Lekhema, Willem A. Cronje, Ian Korir
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031802.
Paper No: NERS-19-1062
https://doi.org/10.1115/1.4046353
Published Online: May 27, 2022
View Article titled, High Reliability Microgrid for a Nuclear Facility Emergency Power Supply
Open the PDF for High Reliability Microgrid for a Nuclear Facility Emergency Power Supply in another window
Topics: Microgrids, Reliability, Batteries, Diesel generators, Failure, Risk-based design, Emergency power, Probability, Nuclear power stations
Journal Articles

Dr. Romney B. Duffey on His 80th Birthday

Igor Pioro, Richard R. Schultz, Dr. Hideki Kamide, Dr. Sama Bilbao y Leon, Dr. Nils Diaz, Alexander V. Bychkov, Dr. Leon Cizelj, Francesco D'Auria, Dr. Yanping Huang, Dr. Yasuo Koizumi, Tomio Okawa, Dr. Robert Walker, Dr. Robert Youngblood, Enrico Zio
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Editorial
ASME J of Nuclear Rad Sci. July 2022, 8(3): 030201.
Paper No: NERS-22-1030
https://doi.org/10.1115/1.4054329
Published Online: May 3, 2022
View Article titled, Dr. Romney B. Duffey on His 80th Birthday
Open the PDF for Dr. Romney B. Duffey on His 80th Birthday in another window
Topics: Accidents, Design, Electricity (Physics), Governments, Innovation, Japan Society of Mechanical Engineers, Nuclear engineering, Nuclear power, Risk, Safety
Journal Articles

Utilization of Nuklearna Elektrarna Krško Full Scope Simulator for Plant Operation Optimization, Nuclear Education and Engineering in 20 Years

Matjaž Žvar, Tomaž Žagar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041701.
Paper No: NERS-21-1022
https://doi.org/10.1115/1.4052013
Published Online: March 16, 2022
View Article titled, Utilization of Nuklearna Elektrarna Krško Full Scope Simulator for Plant Operation Optimization, Nuclear Education and Engineering in 20 Years
Open the PDF for Utilization of Nuklearna Elektrarna Krško Full Scope Simulator for Plant Operation Optimization, Nuclear Education and Engineering in 20 Years in another window
Topics: Accidents, Design, Drills (Tools), Education, Emergency preparedness, Nuclear power stations, Safety, Optimization, Computers, Spent nuclear fuels
Journal Articles

ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors

Robert B. Keating, Suzanne P. McKillop, Todd Allen, Mark Anderson
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041106.
Paper No: NERS-19-1161
https://doi.org/10.1115/1.4047113
Published Online: September 4, 2020
View Article titled, ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors
Open the PDF for ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors in another window
Topics: Design, Diffusion (Physics), Heat exchangers, High temperature, Reliability, Testing, Construction, ASME Standards, ASME Boiler and Pressure Vessel Code, Stress
Journal Articles

Markov/CCMT Dynamic Reliability Analysis of the Main and Startup Feedwater Control System in Nuclear Power Plant

Wentao Li, Danying Gu, Henan Zhang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041011.
Paper No: NERS-17-1290
https://doi.org/10.1115/1.4040888
Published Online: September 10, 2018
View Article titled, Markov/CCMT Dynamic Reliability Analysis of the Main and Startup Feedwater Control System in Nuclear Power Plant
Open the PDF for Markov/CCMT Dynamic Reliability Analysis of the Main and Startup Feedwater Control System in Nuclear Power Plant in another window
Topics: Control systems, Event history analysis, Failure, Failure mechanisms, Feedwater, Nuclear power stations, Probability, Reliability
Journal Articles

Dynamic Flowgraph Methodology Assessment of an FPGA-Based Postaccident Monitoring System for Westinghouse AP1000 Nuclear Power Plants

Phillip McNelles, Lixuan Lu, Marc-James Abi-Jaoude
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2015, 1(3): 034501.
Paper No: NERS-14-1035
https://doi.org/10.1115/1.4029591
Published Online: May 20, 2015
View Article titled, Dynamic Flowgraph Methodology Assessment of an FPGA-Based Postaccident Monitoring System for Westinghouse AP1000 Nuclear Power Plants
Open the PDF for Dynamic Flowgraph Methodology Assessment of an FPGA-Based Postaccident Monitoring System for Westinghouse AP1000 Nuclear Power Plants in another window
Topics: Design, Design for Manufacturing, Instrumentation, Monitoring systems, Nuclear power stations, Reliability, Calibration, Probability, Sensors
Journal Articles

Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements

Shigeru Takaya, Tai Asayama, Yoshio Kamishima, Hideo Machida, Daigo Watanabe, Satoru Nakai, Masaki Morishita
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011004.
Paper No: NERS-14-1020
https://doi.org/10.1115/1.4026392
Published Online: February 9, 2015
View Article titled, Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements
Open the PDF for Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements in another window
Topics: Creep, Design, Failure, Fatigue, Fracture (Materials), In-service inspection, Probability, Reliability, Safety, Stress