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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

Public–Private Partnering in Nuclear Reactor Development—Historical Review and Implications for Today

Steven Krahn, Andrew Sowder
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Review Articles
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030904.
Paper No: NERS-23-1042
https://doi.org/10.1115/1.4064233
Published Online: March 8, 2024
View Article titled, Public–Private Partnering in Nuclear Reactor Development—Historical Review and Implications for Today
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Topics: Construction, Governments, Nuclear power, Nuclear reactors, Technology development, Boiling water reactors, Pressurized water reactors, Design
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

The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term

Riku Tuominen, Ville Valtavirta
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2022, 8(4): 044503.
Paper No: NERS-21-1019
https://doi.org/10.1115/1.4051445
Published Online: March 15, 2022
View Article titled, The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term
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Topics: Boiling water reactors, Emissions, Heat, Manufacturing, Nuclear fission, Photons, Probability, Resonance, Spent nuclear fuels, Nuclides
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
Journal Articles

Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)

S. P. Saraswat, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011402.
Paper No: NERS-19-1022
https://doi.org/10.1115/1.4047161
Published Online: October 2, 2020
View Article titled, Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)
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Topics: Accidents, Boiling water reactors, Eigenvalues, Fluids, Porosity, Pressure, Pressurized water reactors, Light water reactors, Water, Stability
Journal Articles

Radionuclide Composition of Airborne Discharges of European NPPS With WWER, Pressurized Water Reactor, and Boiling Water Reactor Facilities

Angelina-Nataliya V. Vukolova, Andrei A. Rusinkevich
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 012001.
Paper No: NERS-20-1008
https://doi.org/10.1115/1.4047044
Published Online: October 1, 2020
View Article titled, Radionuclide Composition of Airborne Discharges of European NPPS With WWER, Pressurized Water Reactor, and Boiling Water Reactor Facilities
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Topics: Nuclear power stations, Radioisotopes, Boiling water reactors, Pressurized water reactors
Journal Articles

Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework

Sergey Galushin, Dmitry Grishchenko, Pavel Kudinov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041113.
Paper No: NERS-19-1170
https://doi.org/10.1115/1.4047552
Published Online: September 4, 2020
View Article titled, Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework
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Topics: Boiling water reactors, Containment, Explosions, Failure, Steam, Vessels, Risk, Accidents, Uncertainty
Journal Articles

Current Status of Reactors Deployment and Small Modular Reactors Development in the World

I. Pioro, R. B. Duffey, P. L. Kirillov, N. Dort-Goltz
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technology Review
ASME J of Nuclear Rad Sci. October 2020, 6(4): 044001.
Paper No: NERS-20-1112
https://doi.org/10.1115/1.4047927
Published Online: September 3, 2020
View Article titled, Current Status of Reactors Deployment and Small Modular Reactors Development in the World
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Topics: Boiling water reactors, China, Construction, Design, Fuels, Licensing, Nuclear power, Nuclear power stations, Nuclear reactors, Pressurized water reactors
Journal Articles

Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor

A. K. Nayak, Mukesh Kumar, Sumit V. Prasad, V. Jain, D. K. Chandraker
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041203.
Paper No: NERS-18-1079
https://doi.org/10.1115/1.4042852
Published Online: July 19, 2019
View Article titled, Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor
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Topics: Heat, Test facilities, Water, Cavities, Earthquakes, Heat sinks, Boiling water reactors, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Fracture (Materials)
Journal Articles

Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor

A. K. Nayak, Mukesh Kumar, A. K. Vishnoi, Vikas Jain, D. K. Chandraker
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041205.
Paper No: NERS-18-1093
https://doi.org/10.1115/1.4043198
Published Online: July 19, 2019
View Article titled, Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor
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Topics: Boiling water reactors, Condensers (steam plant), Coolants, Design, Flow (Dynamics), Heat, Pressure, Safety, Temperature, Test facilities
Journal Articles

Numerical Investigations of the Effect of Radial Power Distribution and Inlet Orifice on the Stability Behavior of Parallel Multichannel Type Natural Circulation Boiling Water Reactor

Sapna Singh, Garima Singal, A. K. Nayak, Umasankari Kannan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031002.
Paper No: NERS-17-1075
https://doi.org/10.1115/1.4039594
Published Online: May 16, 2018
View Article titled, Numerical Investigations of the Effect of Radial Power Distribution and Inlet Orifice on the Stability Behavior of Parallel Multichannel Type Natural Circulation Boiling Water Reactor
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Topics: Flow (Dynamics), Oscillations, Stability, Boiling water reactors
Journal Articles

Severe Accident Context Quantification for Long-Term Station Blackout in Boiling Water Reactor Nuclear Power Plants

Gueorgui I. Petkov, Monica Vela-Garcia
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020913.
Paper No: NERS-16-1134
https://doi.org/10.1115/1.4038928
Published Online: March 5, 2018
View Article titled, Severe Accident Context Quantification for Long-Term Station Blackout in Boiling Water Reactor Nuclear Power Plants
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Topics: Accidents, Boiling water reactors, Nuclear power stations, Safety
Journal Articles

Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions

Yuta Abe, Ikken Sato, Toshio Nakagiri, Akihiro Ishimi, Yuji Nagae
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020901.
Paper No: NERS-16-1117
https://doi.org/10.1115/1.4038911
Published Online: March 5, 2018
View Article titled, Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions
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Topics: Heating, Plasmas (Ionized gases), Boiling water reactors, Accidents
Journal Articles

Overview of Boiling Water Reactor Steam Dryer Alternating Stress Assessment Procedures

Stephen A. Hambric, Samir Ziada, Richard J. Morante
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021002.
Paper No: NERS-17-1059
https://doi.org/10.1115/1.4037898
Published Online: March 5, 2018
View Article titled, Overview of Boiling Water Reactor Steam Dryer Alternating Stress Assessment Procedures
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Topics: Steam, Stress, Boiling water reactors, Dryers
Journal Articles

Intelligent Identification of Boiling Water Reactor State Utilizing Relevance Vector Regression Models

Miltiadis Alamaniotis, Mauro Cappelli
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020904.
Paper No: NERS-16-1137
https://doi.org/10.1115/1.4037203
Published Online: March 5, 2018
View Article titled, Intelligent Identification of Boiling Water Reactor State Utilizing Relevance Vector Regression Models
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Topics: Boiling water reactors, Signals
Journal Articles

In Memoriam: Jan Kysela

Martin Ruscak, Thomas Schulenberg, Igor Pioro, Michal Kostal
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: In Memoriam
ASME J of Nuclear Rad Sci. April 2016, 2(2): 020101.
Paper No: NERS-16-1004
https://doi.org/10.1115/1.4032548
Published Online: April 4, 2016
View Article titled, In Memoriam: Jan Kysela
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Topics: Water, Water chemistry, Chemistry, Corrosion, Energy generation, Nuclear research, Pressurized water reactors, Supercritical water reactors, Biomedicine, Boiling water reactors
Journal Articles

Irradiation Capabilities at the Halden Reactor and Testing Possibilities Under Supercritical Water Conditions

Rudi Van Nieuwenhove
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021013.
Paper No: NERS-15-1033
https://doi.org/10.1115/1.4030798
Published Online: February 29, 2016
View Article titled, Irradiation Capabilities at the Halden Reactor and Testing Possibilities Under Supercritical Water Conditions
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Topics: Fuels, Instrumentation, Irradiation (Radiation exposure), Pressurized water reactors, Temperature, Testing, Water, Corrosion, Boiling water reactors, Heating