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Journal Articles

Heat Flux Correlations for Condensation from Steam and Air Mixtures on Vertical Flat Plates

Accepted Manuscript
Michio Murase, Toshiya Takaki
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1021
https://doi.org/10.1115/1.4066343
Published Online: August 26, 2024
View Article titled, Heat Flux Correlations for Condensation from Steam and Air Mixtures on Vertical Flat Plates
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Topics: Condensation, Flat plates, Heat flux, Steam, Computational fluid dynamics, Flow (Dynamics), Natural convection, Accidents, Boundary-value problems, Containment vessels
Journal Articles

Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy

Accepted Manuscript
Valerie Nwadeyi, Adam Judy, Tad Whiteside
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1015
https://doi.org/10.1115/1.4066342
Published Online: August 26, 2024
View Article titled, Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy
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Topics: Contamination, Gamma rays, Imaging, Radiation measurement, Spectroscopy, Filters, Filtration, Nondestructive evaluation, Nuclear power stations, Pressure
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

Development of Risk Informed Aging Management Program in Decommissioning

Masao Uesaka, Kenta Murakami
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2025, 11(1): 014501.
Paper No: NERS-23-1063
https://doi.org/10.1115/1.4065139
Published Online: May 10, 2024
View Article titled, Development of Risk Informed Aging Management Program in Decommissioning
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Topics: Maintenance, Nuclear decommissioning, Nuclear power stations, Safety, Fire, Risk
Journal Articles

NED Chair's Message

Asif Arastu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. January 2024, 10(1): 010301.
Paper No: NERS-23-1108
https://doi.org/10.1115/1.4063844
Published Online: December 8, 2023
View Article titled, NED Chair's Message
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Topics: Nuclear engineering, Radiation (Physics), Safety, Radioactive wastes, Environmental remediation, Nuclear decommissioning, Carbon neutrality, Computer security, Decontamination, Education
Journal Articles

Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko

Davor Grgic, Paulina Duckic, Vesna Bencik, Sinisa Sadek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011701.
Paper No: NERS-23-1019
https://doi.org/10.1115/1.4062797
Published Online: October 20, 2023
View Article titled, Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko
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Topics: Accidents, Containment, Ducts, Nuclear power stations, Fluids
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

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. October 2023, 9(4): 041802.
Paper No: NERS-23-1050
https://doi.org/10.1115/1.4062865
Published Online: September 15, 2023
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
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 in another window
Topics: Errors, Flow (Dynamics), Instrumentation, Measurement uncertainty, Uncertainty, Nuclear power stations, Sensors, Pipes
Journal Articles

Study on Performance of New Flexible Shielding Materials and First Demonstration Application in Chinese Pressurized Water Reactor Nuclear Power Plant

Li Yulong, Liu Feng, Liu Xiajie, Li Li, Kang Zheng, He Ye
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041105.
Paper No: NERS-22-1153
https://doi.org/10.1115/1.4062796
Published Online: July 17, 2023
View Article titled, Study on Performance of New Flexible Shielding Materials and First Demonstration Application in Chinese Pressurized Water Reactor Nuclear Power Plant
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Topics: Composite materials, Gamma rays, Mechanical properties, Nuclear power stations, Pressurized water reactors, Radiation (Physics), Silicone rubber, Particle size
Journal Articles

Technical Evaluation Method of Mechanical Equipment Item Substitution in the Procurement and Construction Process of Nuclear Power Plant

Jindong Zhang, Chongzhi Wu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011801.
Paper No: NERS-22-1014
https://doi.org/10.1115/1.4054878
Published Online: July 19, 2022
View Article titled, Technical Evaluation Method of Mechanical Equipment Item Substitution in the Procurement and Construction Process of Nuclear Power Plant
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Topics: Construction, Design, Evaluation methods, Nuclear power stations, Failure mechanisms, Nuclear power
Journal Articles

Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool

Antonio Guglielmelli, Stefano Ederli, Fulvio Mascari, Federico Rocchi, Pietro Maccari
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041602.
Paper No: NERS-21-1018
https://doi.org/10.1115/1.4054514
Published Online: June 24, 2022
View Article titled, Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool
Open the PDF for Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool in another window
Topics: Accidents, Cooling, Emissions, Fukushima nuclear disaster, Japan, 2011, Meteorology, Nuclear power stations, Simulation, Spent nuclear fuels, Wind, Wind velocity
Journal Articles

Necessity of Coordinating Nondestructive Examination Requirement for Nuclear Power Plant

Chongzhi Wu, Haoming Sun, Zhenguo Peng, Benzheng Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Expert View
ASME J of Nuclear Rad Sci. January 2023, 9(1): 014701.
Paper No: NERS-21-1177
https://doi.org/10.1115/1.4054169
Published Online: June 7, 2022
View Article titled, Necessity of Coordinating Nondestructive Examination Requirement for Nuclear Power Plant
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Topics: Design, Nondestructive evaluation, Nuclear power stations, Safety
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
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Topics: Microgrids, Reliability, Batteries, Diesel generators, Failure, Risk-based design, Emergency power, Probability, Nuclear power stations
Journal Articles

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

S. A. Cancemi, R. Lo Frano
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 034501.
Paper No: NERS-20-1206
https://doi.org/10.1115/1.4053689
Published Online: May 26, 2022
View Article titled, Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance
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Topics: Filters, Pipes, Signals, Stress, Temperature, Monitoring systems, Nuclear power stations
Journal Articles

Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste

Glenn Harvel
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031302.
Paper No: NERS-21-1100
https://doi.org/10.1115/1.4052808
Published Online: May 26, 2022
View Article titled, Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste
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Topics: Fuels, Heat, Nuclear power stations, Plastics, Pyrolysis, Small modular reactors, Heating, Syngas, Temperature, Biochar
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
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Topics: Accidents, Design, Electricity (Physics), Governments, Innovation, Japan Society of Mechanical Engineers, Nuclear engineering, Nuclear power, Risk, Safety
Journal Articles

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

A. M. Baisov, A. N. Churkin, V. I. Deev, V. S. Kharitonov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031101.
Paper No: NERS-21-1101
https://doi.org/10.1115/1.4053049
Published Online: March 22, 2022
View Article titled, Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes
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Topics: Coolants, Fluids, Fuel rods, Heat transfer, Momentum, Temperature, Water, Wall temperature, Flow (Dynamics), Testing
Journal Articles

Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One

Davor Grgić, Mario Matijević, Paulina Dučkić, Radomir Ječmenica
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041902.
Paper No: NERS-21-1029
https://doi.org/10.1115/1.4051447
Published Online: March 16, 2022
View Article titled, Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One
Open the PDF for Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One in another window
Topics: Accidents, Fuels, Hardware, Neutrons, Nuclear power stations, Particulate matter, Spent nuclear fuels, Storage, Uncertainty, Manufacturing
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
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Topics: Accidents, Design, Drills (Tools), Education, Emergency preparedness, Nuclear power stations, Safety, Optimization, Computers, Spent nuclear fuels
Journal Articles

Comparison of the ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 Libraries for the Nuclear Design Calculations of the Nuclear Power Plant Krško With the CORD-2 System

Marjan Kromar, Bojan Kurinčič
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041501.
Paper No: NERS-21-1014
https://doi.org/10.1115/1.4050991
Published Online: March 15, 2022
View Article titled, Comparison of the ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 Libraries for the Nuclear Design Calculations of the Nuclear Power Plant Krško With the CORD-2 System
Open the PDF for Comparison of the ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 Libraries for the Nuclear Design Calculations of the Nuclear Power Plant Krško With the CORD-2 System in another window
Topics: Boron, Cycles, Fuels, Manufacturing, Neutrons, Nuclear design, Nuclear power stations, Nuclear fission, Cross section (Physics), Rods