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Journal Articles

Monitoring for Actinide Neutron Emissions From Spent Nuclear Fuel Under Extreme Gamma Fields Using Centrifugally Tensioned Metastable Fluid Detector Sensor Technology

C. Harabagiu, R. P. Taleyarkhan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041601.
Paper No: NERS-23-1119
https://doi.org/10.1115/1.4065280
Published Online: May 10, 2024
View Article titled, Monitoring for Actinide Neutron Emissions From Spent Nuclear Fuel Under Extreme Gamma Fields Using Centrifugally Tensioned Metastable Fluid Detector Sensor Technology
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Topics: Fluids, Neutrons, Sensors, Emissions, Photons, Spent nuclear fuels
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

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

Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2

Silja Häkkinen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041901.
Paper No: NERS-21-1015
https://doi.org/10.1115/1.4051444
Published Online: March 15, 2022
View Article titled, Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2
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Topics: Approximation, Coolants, Cycles, Irradiation (Radiation exposure), Manufacturing, Nuclides, Spent nuclear fuels, Heat, Boron, Photons
Journal Articles

The Environmental, Economic, and Social Performance of Nuclear Technology in Australia

Troy Malatesta
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041202.
Paper No: NERS-20-1089
https://doi.org/10.1115/1.4049758
Published Online: April 22, 2021
View Article titled, The Environmental, Economic, and Social Performance of Nuclear Technology in Australia
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Topics: Emissions, Fossil fuels, Nuclear power, Climate change, Construction, Cycles, Carbon, Energy generation
Journal Articles

Methodology of 63 Cu(n,2n) 62 Cu Reaction Rate Measurement

Martin Schulc, Michal Košťál, Jan Šimon, Evžen Novák
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2021, 7(2): 024503.
Paper No: NERS-20-1039
https://doi.org/10.1115/1.4048236
Published Online: November 16, 2020
View Article titled, Methodology of 63 Cu(n,2n) 62 Cu Reaction Rate Measurement
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Topics: Half-life, Irradiation (Radiation exposure), Isotopes, Neutrons, Nuclear fission, Uncertainty, Gamma ray spectrometry, Emissions
Journal Articles

Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor

Luis M. Palomino, Mohamed S. El-Genk, Timothy M. Schriener
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031302.
Paper No: NERS-19-1045
https://doi.org/10.1115/1.4045297
Published Online: March 9, 2020
View Article titled, Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor
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Topics: Cladding systems (Building), Emissions, Fuels, Neutrons, Photons, Steel, Vessels, Storage, Radioactivity, Isotopes
Journal Articles

Radiographic Nondestructive Testing Simulations Using gate Software Toolkit

Eslam Taha, M. S. Mohammed, Essam Banoqitah
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011901.
Paper No: NERS-18-1127
https://doi.org/10.1115/1.4044909
Published Online: November 29, 2019
View Article titled, Radiographic Nondestructive Testing Simulations Using gate Software Toolkit
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Topics: Computer software, Gates (Closures), Nondestructive evaluation, Radiation (Physics), Simulation, Testing, Wedges, X-rays, Gamma rays, Emissions
Journal Articles

Investigation of 127 I(n,2n) 126 I and 23 Na(n,2n) 22 Na Reactions Using 252 Cf Neutron Source

Martin Schulc, Michal Košťál, Evžen Novák, Jan Šimon, Nicola Burianová
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030918.
Paper No: NERS-18-1012
https://doi.org/10.1115/1.4039774
Published Online: April 16, 2019
View Article titled, Investigation of 127 I(n,2n) 126 I and 23 Na(n,2n) 22 Na Reactions Using 252 Cf Neutron Source
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Topics: Chemical kinetics, Cross section (Physics), Emissions, Irradiation (Radiation exposure), Neutron sources, Neutrons, Uncertainty, Nuclear fission, Sodium, Germanium
Journal Articles

Measurement of Selected Differential Cross Sections in 235 U Spectrum

Nicola Burianová, Michal Košt´ál, Martin Schulc, Jan Šimon, Martin Mareček, Jan Uhlíř
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030906.
Paper No: NERS-18-1051
https://doi.org/10.1115/1.4042850
Published Online: April 16, 2019
View Article titled, Measurement of Selected Differential Cross Sections in 235 U Spectrum
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Topics: Chemical kinetics, Computational methods, Cross section (Physics), Gamma ray spectrometry, Manganese dioxide, Neutrons, Nuclear fission, Sensors, Uncertainty, Irradiation (Radiation exposure)
Journal Articles

A Study on Hydrogen Emission of Zirconium Hydride

Fu Xiaogang, Qin Bo, Ma Haoran, Zhang Jinquan, Long Bin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2019, 5(1): 014501.
Paper No: NERS-17-1245
https://doi.org/10.1115/1.4041274
Published Online: January 24, 2019
View Article titled, A Study on Hydrogen Emission of Zirconium Hydride
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Topics: Emissions, Hydrogen, Zirconium, Cladding systems (Building)