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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

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

Javier Ortiz-Villafuerte, Heriberto Sánchez-Mora, César Queral, Melisa Reyes-Fuentes, Edmundo del- Valle-Gallegos
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031701.
Paper No: NERS-22-1021
https://doi.org/10.1115/1.4055011
Published Online: April 22, 2024
View Article titled, Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a Boiling Water Reactor STSBO Using MAAP5 and AZTUSIA
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Topics: Boiling water reactors, Hydrogen, Oxidation, Simulation, Uncertainty analysis, Zirconium, Accidents, Sensitivity analysis, Temperature, Uncertainty
Journal Articles

Application of Level 3 Probabilistic Safety Analysis in UK HPR1000

Jinkai Wang, Qi Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021702.
Paper No: NERS-22-1112
https://doi.org/10.1115/1.4063874
Published Online: January 29, 2024
View Article titled, Application of Level 3 Probabilistic Safety Analysis in UK HPR1000
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Topics: Accidents, Radiation (Physics), Risk, Probabilistic safety assessment, Design
Journal Articles

Cold Crucible Facility for Severe Accident Research at Canadian Nuclear Laboratories

R. David, B. Mitchell, J. H. Spencer, N. Lair, S. M. Petoukhov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2024, 10(2): 024501.
Paper No: NERS-23-1049
https://doi.org/10.1115/1.4063673
Published Online: November 1, 2023
View Article titled, Cold Crucible Facility for Severe Accident Research at Canadian Nuclear Laboratories
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Topics: Accidents, Zirconium, Electromagnetic induction
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

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

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041102.
Paper No: NERS-22-1136
https://doi.org/10.1115/1.4056854
Published Online: March 14, 2023
View Article titled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
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Topics: Coolants, Flow (Dynamics), Fuels, Sodium, Temperature, Accidents, Transients (Dynamics), Pins (Engineering)
Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021301.
Paper No: NERS-21-1161
https://doi.org/10.1115/1.4056834
Published Online: March 2, 2023
View Article titled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study
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Topics: Accidents, Coolants, Fuels, Temperature, Fast neutron reactors, Flow (Dynamics), Pins (Engineering), Transients (Dynamics)
Journal Articles

Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU

M. D. Shah, A. C. Morreale, L. S. Lebel
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011701.
Paper No: NERS-22-1025
https://doi.org/10.1115/1.4055258
Published Online: September 2, 2022
View Article titled, Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU
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Topics: Accidents, Containment, Failure, Pressure, Water
Journal Articles

Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating

Rofida Hamad Khlifa, Nicolay N. Nikitenkov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 012003.
Paper No: NERS-22-1044
https://doi.org/10.1115/1.4055012
Published Online: September 1, 2022
View Article titled, Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating
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Topics: Boron, Coatings, Fuels, Temperature, Cladding systems (Building), Neutrons, Accidents
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
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Topics: Accidents, Cooling, Emissions, Fukushima nuclear disaster, Japan, 2011, Meteorology, Nuclear power stations, Simulation, Spent nuclear fuels, Wind, Wind velocity
Journal Articles

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

S. P. Saraswat, D. Ray, G. Mishra, D. Yadav, V. S. Bhadouria, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.
Paper No: NERS-21-1073
https://doi.org/10.1115/1.4052014
Published Online: May 26, 2022
View Article titled, Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design
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Topics: Accidents, Boiling water reactors, Containment, Design, Pressure, Safety, Steam, Water, Heat, Economics
Journal Articles

Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA

Emmanuel K. Boafo, Emmanuel Numapau Gyamfi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031703.
Paper No: NERS-21-1094
https://doi.org/10.1115/1.4053050
Published Online: May 26, 2022
View Article titled, Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA
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Topics: Accidents, Hydrogen, Sensitivity analysis, Uncertainty, Uncertainty quantification, Uncertainty analysis, Design, Optimization
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

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
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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

Experimental Investigation on the Retention of Soluble Particles by Pool Scrubbing

R. Vennemann, M. Klauck, H.-J. Allelein
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2022, 8(4): 044502.
Paper No: NERS-20-1212
https://doi.org/10.1115/1.4051250
Published Online: March 15, 2022
View Article titled, Experimental Investigation on the Retention of Soluble Particles by Pool Scrubbing
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Topics: Aerosols, Particulate matter, Water, Accidents, Bubbles
Journal Articles

ESFR-SMART Core Safety Measures and Their Preliminary Assessment

Andrei Rineiski, Clément Mériot, Marco Marchetti, Jiri Krepel, Christine Coquelet-Pascal, Haileyesus Tsige-Tamirat, Francisco Álvarez-Velarde, Enrico Girardi, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011322.
Paper No: NERS-20-1130
https://doi.org/10.1115/1.4052588
Published Online: October 29, 2021
View Article titled, ESFR-SMART Core Safety Measures and Their Preliminary Assessment
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Topics: Fuels, Safety, Sodium, Sodium fast reactors, Design, Accidents
Journal Articles

Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Hong Xu, Aurelian Florin Badea, Xu Cheng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021404.
Paper No: NERS-21-1036
https://doi.org/10.1115/1.4050770
Published Online: October 19, 2021
View Article titled, Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark
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Topics: Accidents, Coolants, Steady state, Transients (Dynamics), Errors, Flow (Dynamics), Thermal hydraulics, Leakage, Simulation
Journal Articles

Post-Test Analyses of the CMMR-4 Test

Takuya Yamashita, Hiroshi Madokoro, Ikken Sato
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021701.
Paper No: NERS-21-1055
https://doi.org/10.1115/1.4051443
Published Online: October 19, 2021
View Article titled, Post-Test Analyses of the CMMR-4 Test
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Topics: Blades, Boiling water reactors, Cutting, Fuels, Heating, Melting, Water, Temperature, Accidents, Permeability