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Journal Articles

High-Performance Manufacturing of Canned Main Coolant Pump — Part II: Reliability Evaluation

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Accepted Manuscript
M.K. Lei, H.L. Che, Yupeng Li, Bao Zhu, X.P. Zhu, L. Lin, X.P. Lv, M.Q. Li, G.Y. Ma, D.M. Guo
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1098
https://doi.org/10.1115/1.4068596
Published Online: May 3, 2025
View Articletitled, High-Performance Manufacturing of Canned Main Coolant Pump — Part II: Reliability Evaluation
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Topics: Coolants, Manufacturing, Pumps, Reliability, Failure, Density, Engineering prototypes, Cycles, Damage, Design
Journal Articles

High Reliability Microgrid for a Nuclear Facility Emergency Power Supply

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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 Articletitled, High Reliability Microgrid for a Nuclear Facility Emergency Power Supply
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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

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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 Articletitled, Dr. Romney B. Duffey on His 80th Birthday
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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

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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 Articletitled, 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

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

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

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

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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 Articletitled, Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements
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Topics: Creep, Design, Failure, Fatigue, Fracture (Materials), In-service inspection, Probability, Reliability, Safety, Stress