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Journal Articles

Performance of NB-CTMFD Detector Versus Ludlum 42-49B, and Fuji NSN3 Detectors for Hard (Am-Be) and Soft (Cf-252 Fission) Energy Spectra Neutron Sources Within Lead/Concrete Shielded Configurations

Yusuke Ota, Stepan Ozerov, Rusi 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): 042001.
Paper No: NERS-24-1035
https://doi.org/10.1115/1.4065852
Published Online: July 16, 2024
View Article titled, Performance of NB-CTMFD Detector Versus Ludlum 42-49B, and Fuji NSN3 Detectors for Hard (Am-Be) and Soft (Cf-252 Fission) Energy Spectra Neutron Sources Within Lead/Concrete Shielded Configurations
Open the PDF for Performance of NB-CTMFD Detector Versus Ludlum 42-49B, and Fuji NSN3 Detectors for Hard (Am-Be) and Soft (Cf-252 Fission) Energy Spectra Neutron Sources Within Lead/Concrete Shielded Configurations in another window
Topics: Concretes, Fluids, Neutrons, Sensors, Particulate matter, Neutron sources, Nuclear fission, Spectra (Spectroscopy), Simulation
Journal Articles

Development and Calibration of an Indigenous Spectroscopic System for Radiation Portal Monitor Application

Akanchha Fnu, Vikesh Singh Bhadouria, Arun Kumar Pandey, Pankaj Wahi, Niraj Sinha, Prabhat Munshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 032003.
Paper No: NERS-22-1091
https://doi.org/10.1115/1.4056464
Published Online: February 8, 2023
View Article titled, Development and Calibration of an Indigenous Spectroscopic System for Radiation Portal Monitor Application
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Topics: Calibration, Gamma rays, Gates (Closures), Radiation (Physics), Sensors, Spectra (Spectroscopy), Radioisotopes, Resolution (Optics)
Journal Articles

Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252 Cf Source in Center

Tomáš Czakoj, Michal Košťál, Martin Schulc, Vojtěch Rypar, Evžen Novák, Evžen Losa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 032001.
Paper No: NERS-22-1038
https://doi.org/10.1115/1.4056508
Published Online: February 8, 2023
View Article titled, Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252 Cf Source in Center
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Topics: Copper, Leakage, Neutrons, Uncertainty, Spectra (Spectroscopy), Neutron sources
Journal Articles

Applicability of the Dose Spiking Electron Paramagnetic Resonance Method for the Quantitative Measurements of Low Doses in Alanine Dosimetry

Lekhnath Ghimire, Edward Waller
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 012004.
Paper No: NERS-22-1016
https://doi.org/10.1115/1.4055010
Published Online: September 2, 2022
View Article titled, Applicability of the Dose Spiking Electron Paramagnetic Resonance Method for the Quantitative Measurements of Low Doses in Alanine Dosimetry
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Topics: Accuracy and precision, Anisotropy, Dosimetry, Electron paramagnetic resonance, Electrons, Errors, Microwaves, Signals, Cavities, Spectra (Spectroscopy)
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

On the Self-Shielding in the Unresolved Resonance Range

Daniel Lopez Aldama, Andrej Trkov, Dermott E. Cullen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041503.
Paper No: NERS-21-1026
https://doi.org/10.1115/1.4052377
Published Online: March 16, 2022
View Article titled, On the Self-Shielding in the Unresolved Resonance Range
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Topics: Cross section (Physics), Resonance, Spectra (Spectroscopy), Probability, Leakage
Journal Articles

serpent 2 Validation for Radiation Shielding Applications

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): 042001.
Paper No: NERS-21-1009
https://doi.org/10.1115/1.4051614
Published Online: March 15, 2022
View Article titled, serpent 2 Validation for Radiation Shielding Applications
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Topics: Iron, Neutrons, Photons, Spectra (Spectroscopy)
Journal Articles

The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments

Vlastimil Juříček, Michal Košťál, Evžen Losa, Tomáš Czakoj, Zdeněk Matěj, František Cvachovec, Martin Schulc, Jan Šimon, Filip Mravec, Václav Přenosil, Vojtěch Rypar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 022005.
Paper No: NERS-20-1153
https://doi.org/10.1115/1.4049726
Published Online: February 19, 2021
View Article titled, The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments
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Topics: Filters, Iron, Neutrons, Silicon, Spectra (Spectroscopy), Neutron flux, Steel
Journal Articles

Testing Oxygen Nuclear Data Libraries in Research Center Rez

Martin Schulc, Michal Košťál, Evžen Novák, Jan Šimon, Luiz Leal
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021501.
Paper No: NERS-20-1017
https://doi.org/10.1115/1.4048763
Published Online: October 30, 2020
View Article titled, Testing Oxygen Nuclear Data Libraries in Research Center Rez
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Topics: Neutrons, Oxygen, Spectra (Spectroscopy), Water, Testing, Fuels, Neutron sources, Leakage
Journal Articles

Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing

Massimo Sarotto, Gabriele Firpo, Anatoly Kochetkov, Antonin Krása, Emil Fridman, Jerzy Cetnar, Grazyna Domanska
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011402.
Paper No: NERS-18-1132
https://doi.org/10.1115/1.4044000
Published Online: November 29, 2019
View Article titled, Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing
Open the PDF for Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing in another window
Topics: Design, Fast neutron reactors, Nuclear fission, Nuclides, Uncertainty, Uncertainty analysis, Licensing, Neutrons, Rods, Simulation
Journal Articles

Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor

Michal Košťál, Zdeněk Matěj, Filip Mravec, František Cvachovec, Martin Schulc, Vlastimil Juříček, Vojtěch Rypar, Jaroslav Šoltés, Evžen Losa, Ladislav Viererbl
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030915.
Paper No: NERS-18-1054
https://doi.org/10.1115/1.4043197
Published Online: May 29, 2019
View Article titled, Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor
Open the PDF for Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor in another window
Topics: Neutrons, Scintillation counters, Silicon, Spectra (Spectroscopy), Testing, Neutron beams, Resolution (Optics)
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

Statistical Modeling of Stratified Two-Phase Flow

M. Benz, T. Schulenberg
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 021001.
Paper No: NERS-16-1039
https://doi.org/10.1115/1.4035564
Published Online: March 1, 2017
View Article titled, Statistical Modeling of Stratified Two-Phase Flow
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Topics: Flow (Dynamics), Turbulence, Waves, Kinetic energy, Spectra (Spectroscopy), Two-phase flow
Journal Articles

Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration

Davide Chersola, Guglielmo Lomonaco, Guido Mazzini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031004.
Paper No: NERS-14-1027
https://doi.org/10.1115/1.4029521
Published Online: May 20, 2015
View Article titled, Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration
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Topics: Cross section (Physics), Density, Flux (Metallurgy), Fuels, Nuclides, Spectra (Spectroscopy), Nuclear fission, Fast neutron reactors