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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

Akinori Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
Publisher: ASME
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
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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
Article Type: Research-Article
Publisher: ASME
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

Interactions Between Molten Sodium and Standard Pipe Insulation

Accepted Manuscript
Daniel LaBrier, Jordan Harley, Morgan Robbins
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1191
https://doi.org/10.1115/1.4062798
Published Online: June 20, 2023
View Article titled, Interactions Between Molten Sodium and Standard Pipe Insulation
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Topics: Pipe insulation, Sodium, Insulation, Leakage, Pipes, Heat, Binders (Materials), Design, Fire, Glass fiber insulation
Journal Articles

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

Accepted Manuscript
Davor Grgic, Paulina Duckic, Vesna Bencik, Sinisa Sadek
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1019
https://doi.org/10.1115/1.4062797
Published Online: June 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, Nuclear power stations, Containment, Ducts, Design, Exhaust systems, Failure, Fluids, Radiation measuring instruments, Radiation sources
Journal Articles

Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code

Accepted Manuscript
Sinisa Sadek, Renato Pavlinac, Karlo Ivanjko, Davor Grgic
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1016
https://doi.org/10.1115/1.4062799
Published Online: June 20, 2023
View Article titled, Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code
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Topics: Simulation, Uncertainty, Cladding systems (Building), Electricity (Physics), Flow (Dynamics), Fuel rods, Safety, Steam, Acceptance criteria, Boundary-value problems
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
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

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

Accepted Manuscript
Javier Ortiz-Villafuerte, Heriberto Sanchez-Mora, Cesar Queral, Melisa Reyes-Fuentes, Edmundo del-Valle-Gallegos
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1021
https://doi.org/10.1115/1.4055011
Published Online: July 15, 2022
View Article titled, Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA
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Topics: Boiling water reactors, Hydrogen, Uncertainty analysis, Accidents, Simulation, Explosions, Cladding systems (Building), Failure, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations
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
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
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
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

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

Glenn Harvel
Journal: Journal of Nuclear Engineering and Radiation Science
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

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
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

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
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
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

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
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

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
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
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Topics: Accidents, Fuels, Hardware, Neutrons, Nuclear power stations, Particulate matter, Spent nuclear fuels, Storage, Uncertainty, Manufacturing
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
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
Journal Articles

Nuclear Regulatory Acceptance of Certified Process Data Reconciliation

Andy Jansky, Magnus Langenstein
Journal: Journal of Nuclear Engineering and Radiation Science
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

Systematic Approach to Transboundary Radioactivity Monitoring for Accidents in External Nuclear Power Plants

Kampanart Silva, Piyawan Krisanangkura, Krirerk Phungsara, Chatchai Chaiyasaen, Suchin Udomsomporn
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041701.
Paper No: NERS-20-1099
https://doi.org/10.1115/1.4049279
Published Online: April 16, 2021
View Article titled, Systematic Approach to Transboundary Radioactivity Monitoring for Accidents in External Nuclear Power Plants
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Topics: Accidents, Meteorology, Nuclear power stations, Plumes (Fluid dynamics), Radiation measurement, Wind, Feedback
Journal Articles

Developing and Implementing Artificial Intelligence-Based Classifier for Requirements Engineering

Santeri Myllynen, Ilpo Suominen, Tapani Raunio, Rasmus Karell, Jussi Lahtinen
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041201.
Paper No: NERS-20-1102
https://doi.org/10.1115/1.4049722
Published Online: April 16, 2021
View Article titled, Developing and Implementing Artificial Intelligence-Based Classifier for Requirements Engineering
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Topics: Algorithms, Design, Engineering disciplines, Natural language processing, Safety, Nuclear power stations, Decision making, Nuclear power, Workflow, Artificial intelligence