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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

Development of an Artificial Intelligence-Based Predictive Anomaly Detection System to Nuclear Power Plant

Ryota Miyake, Shinya Tominaga, Yusuke Terakado, Naoyuki Takado, Toshio Aoki, Chikashi Miyamoto, Susumu Naito, Yasunori Taguchi, Yuichi Kato, Kota Nakata
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2025, 11(1): 011701.
Paper No: NERS-23-1062
https://doi.org/10.1115/1.4064123
Published Online: May 10, 2024
View Article titled, Development of an Artificial Intelligence-Based Predictive Anomaly Detection System to Nuclear Power Plant
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Topics: Artificial intelligence, Nuclear power stations, Power stations, Pumps, Fluctuations (Physics), Signals, Feedwater, Linkages, Time series, Transients (Dynamics)
Journal Articles

Total Loss of Feedwater Analysis of Pressurized Water Reactor Using RELAP5

Andrej Prošek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011401.
Paper No: NERS-23-1032
https://doi.org/10.1115/1.4063009
Published Online: October 20, 2023
View Article titled, Total Loss of Feedwater Analysis of Pressurized Water Reactor Using RELAP5
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Topics: Design, Feedwater, Pressurized water reactors, Pumps, Safety, Accidents, Nuclear reactor coolants
Journal Articles

Nuclear Regulatory Acceptance of Certified Process Data Reconciliation

Andy Jansky, Magnus Langenstein
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 022101.
Paper No: NERS-20-1199
https://doi.org/10.1115/1.4051619
Published Online: October 19, 2021
View Article titled, Nuclear Regulatory Acceptance of Certified Process Data Reconciliation
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Topics: Measurement uncertainty, Nuclear power stations, Uncertainty, Safety, Feedwater, Flow (Dynamics)
Journal Articles

Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code

M. Ruscak, G. Mazzini, A. Dambrosio, A. Musa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021402.
Paper No: NERS-20-1208
https://doi.org/10.1115/1.4049854
Published Online: February 26, 2021
View Article titled, Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code
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Topics: Accidents, Coolants, Flow (Dynamics), Pressure, Safety, Simulation, Water, Nuclear power stations, Feedwater, Design
Journal Articles

Investigating the Effect of Prior Distributions on Posterior Estimates of Common Cause Failure Parameters Using Bayesian Method

Edward Shitsi, Emmanuel K. Boafo, Felix Ameyaw, H. C. Odoi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031801.
Paper No: NERS-19-1117
https://doi.org/10.1115/1.4045803
Published Online: March 9, 2020
View Article titled, Investigating the Effect of Prior Distributions on Posterior Estimates of Common Cause Failure Parameters Using Bayesian Method
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Topics: Failure, Feedwater, High pressure (Physics), Pumps, Safety, Valves, Nuclear power stations
Journal Articles

Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant

Jun Wang, Mckinleigh Mccabe, Troy Christopher Haskin, Yingwei Wu, Guanghui Su, Michael L. Corradini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041002.
Paper No: NERS-17-1163
https://doi.org/10.1115/1.4040887
Published Online: September 10, 2018
View Article titled, Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant
Open the PDF for Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant in another window
Topics: Cladding systems (Building), Oxidation, Sensitivity analysis, Boilers, Simulation, Feedwater, Water, Temperature, Underground injection, Nuclear power stations
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
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Topics: Control systems, Event history analysis, Failure, Failure mechanisms, Feedwater, Nuclear power stations, Probability, Reliability
Journal Articles

Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor

Guido Mazzini, Miloš Kynčl, Marek Ruščák
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2016, 2(4): 044505.
Paper No: NERS-15-1221
https://doi.org/10.1115/1.4034144
Published Online: October 12, 2016
View Article titled, Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
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Topics: Accidents, Design, Feedwater, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Hydrogen production, Leakage, Nuclear engineering, Nuclear power stations, Pressure