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Journal Articles

Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor

Xiaolin Wang, Youqing Shi, Grant Bickel, DeAbreu Robert

ASME J of Nuclear Rad Sci. July 2023, 9(3): 034501.

Paper No: NERS-22-1039

DOI: https://doi.org/10.1115/1.4055931

Published Online: February 8, 2023

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Topics: Fluence (Radiation measurement), Irradiation (Radiation exposure), Isotopes, Neutrons, Zirconium

Journal Articles

On Cyclotron-Based Production of Gallium-68 Isotope: A Computational Benchmark for the Production Yield & Shielding Considerations

Luis Fernando Salas-Tapia, Tian Zhang

ASME J of Nuclear Rad Sci. April 2023, 9(2): 022001.

Paper No: NERS-21-1126

DOI: https://doi.org/10.1115/1.4055257

Published Online: September 13, 2022

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Topics: Cyclotrons, Gallium, Irradiation (Radiation exposure), Isotopes, Particulate matter, Protons, Uncertainty

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

ASME J of Nuclear Rad Sci. January 2023, 9(1): 012004.

Paper No: NERS-22-1016

DOI: https://doi.org/10.1115/1.4055010

Published Online: September 2, 2022

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Topics: Accuracy and precision, Anisotropy, Dosimetry, Electron paramagnetic resonance, Electrons, Errors, Microwaves, Signals, Cavities, Spectra (Spectroscopy)

Journal Articles

Review of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in the National Research Universal Reactor

T. Sinh Nguyen, Xiaolin Wang, Blair P. Bromley

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031502.

Paper No: NERS-21-1117

DOI: https://doi.org/10.1115/1.4053691

Published Online: June 1, 2022

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Topics: Fuels, Physics, Irradiation (Radiation exposure)

Journal Articles

Radiation-Induced Surface Wettability Enhancement of an Indium Tin Oxide and Titanium Oxide Film-Coated Sapphire

Kai Wang, Hui Liang, Junya Inoue, Nejdet Erkan, Koji Okamoto

ASME J of Nuclear Rad Sci. July 2022, 8(3): 032001.

Paper No: NERS-21-1070

DOI: https://doi.org/10.1115/1.4051791

Published Online: May 26, 2022

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Topics: Gamma rays, Irradiation (Radiation exposure), Sapphire, Radiation (Physics), Titanium dioxide, Electron beams, Titanium, Nucleate boiling

Journal Articles

Efficient Neutron Irradiation Procedure for Uniform Dopant Distributions in Silicon Doping

Nader M. A. Mohamed, Mosa Osman, Ibrahim Abdelrazek

ASME J of Nuclear Rad Sci. July 2022, 8(3): 034503.

Paper No: NERS-21-1109

DOI: https://doi.org/10.1115/1.4054005

Published Online: May 26, 2022

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Topics: Irradiation (Radiation exposure), Neutron flux, Neutrons, Silicon

Journal Articles

Reevaluation of Spectral Parameters and Neutron Fluxes in IC-7 Irradiation Channel of TRIGA MARK I IPR-R1 Research Nuclear Reactor

Radojko Jaćimović, Maria Ângela de Barros Correia Menezes

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041504.

Paper No: NERS-21-1007

DOI: https://doi.org/10.1115/1.4051249

Published Online: March 22, 2022

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Topics: Flux (Metallurgy), Irradiation (Radiation exposure), Neutrons, Neutron activation analysis, Uncertainty

Journal Articles

Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code

Jakub Lüley, Branislav Vrban, Štefan Čerba, Filip Osuský, Vladimír Nečas

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041601.

Paper No: NERS-21-1030

DOI: https://doi.org/10.1115/1.4052519

Published Online: March 22, 2022

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Topics: Fuels, Grain size, Irradiation (Radiation exposure), Modeling, Nuclear fission, Rods, Pressure, Cladding systems (Building), Stress

Journal Articles

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

Silja Häkkinen

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041901.

Paper No: NERS-21-1015

DOI: https://doi.org/10.1115/1.4051444

Published Online: March 15, 2022

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Topics: Approximation, Coolants, Cycles, Irradiation (Radiation exposure), Manufacturing, Nuclides, Spent nuclear fuels, Heat, Boron, Photons

Journal Articles

Utilizing of Spent Fuel Storage Pool in Gamma Irradiation Experiments

Amr Abdelhady

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021901.

Paper No: NERS-21-1039

DOI: https://doi.org/10.1115/1.4051065

Published Online: October 19, 2021

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Topics: Irradiation (Radiation exposure), Spent nuclear fuels

Journal Articles

Neutronic Analysis of the European Sodium Fast Reactor: Part II—Burnup Results

Emil Fridman, Francisco Álvarez Velarde, Pablo Romojaro Otero, Haile Tsige-Tamirat, Antonio Jiménez Carrascosa, Nuria García Herranz, Franck Bernard, Robert Gregg, Una Davies, Jiri Krepel, Ben Lindley, Simone Massara, Sandra Poumerouly, Enrico Girardi, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011302.

Paper No: NERS-20-1067

DOI: https://doi.org/10.1115/1.4048765

Published Online: July 20, 2021

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Topics: Cycles, Equilibrium (Physics), Fuels, Modeling, Safety, Sodium fast reactors, Irradiation (Radiation exposure)

Journal Articles

Metallic Fast Reactor Separate Effect Studies for Fuel Safety

Fidelma G. Di Lemma, Colby B. Jensen, Joshua J. Kane, Wei-Ying Chen, Xiang Liu, Luca Capriotti, Cynthia A. Adkins, Boopathy Kombaiah, Alexander J. Winston, Lingfeng He, Daniel Wachs

ASME J of Nuclear Rad Sci. October 2021, 7(4): 041602.

Paper No: NERS-20-1097

DOI: https://doi.org/10.1115/1.4049721

Published Online: April 22, 2021

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Topics: Bubbles, Fuels, Instrumentation, Irradiation (Radiation exposure), Nuclear fission, Safety, Transients (Dynamics), Sodium fast reactors, Testing, Fast neutron reactors

Journal Articles

Safety Analysis of Indonesia's Multipurpose Reactor During Irradiation of Natural UO 2 Pin Target at Power Ramp Test Facility

Octaviana Erawati Fadli, Azizul Khakim, S. Suharyana, A. Suparmi

ASME J of Nuclear Rad Sci. July 2021, 7(3): 032002.

Paper No: NERS-20-1013

DOI: https://doi.org/10.1115/1.4048904

Published Online: April 1, 2021

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Topics: Irradiation (Radiation exposure), Safety, Neutron flux, Fuels, Test facilities

Journal Articles

The Use of Polycarbonate as Dosimeter of High Doses

David Zoul, Markéta Koplová, Vít Rosnecký, Michal Košťál, Miroslav Vinš, Jan Šimon, Martin Schulc, Martin Cabalka, Jan Kučera, Vladimír Strunga

ASME J of Nuclear Rad Sci. April 2021, 7(2): 022003.

Paper No: NERS-20-1082

DOI: https://doi.org/10.1115/1.4049717

Published Online: February 19, 2021

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Topics: Dosimeters, Dosimetry, Irradiation (Radiation exposure), Neutrons, Radiation (Physics), Water, Wavelength, Gamma rays, Photons, Nuclear reactors

Journal Articles

Neutron Field Shaping Using Graphite for Reaction Rate Measurements

Mikita Sobaleu, Michal Košťál, Jan Šimon, Evžen Losa

ASME J of Nuclear Rad Sci. April 2021, 7(2): 022004.

Paper No: NERS-20-1129

DOI: https://doi.org/10.1115/1.4049725

Published Online: February 19, 2021

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Topics: Chemical kinetics, Graphite, Irradiation (Radiation exposure), Neutrons, Uncertainty, Dosimetry

Journal Articles

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

Martin Schulc, Michal Košťál, Jan Šimon, Evžen Novák

ASME J of Nuclear Rad Sci. April 2021, 7(2): 024503.

Paper No: NERS-20-1039

DOI: https://doi.org/10.1115/1.4048236

Published Online: November 16, 2020

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Topics: Half-life, Irradiation (Radiation exposure), Isotopes, Neutrons, Nuclear fission, Uncertainty, Gamma ray spectrometry, Emissions

Journal Articles

Study of a Gamma Radiation Impact on Concrete Properties Under Severe Accident Conditions

Zbyněk Hlaváč, Jaroslava Zatloukalová, Michal Košťál, Evžen Losa

ASME J of Nuclear Rad Sci. April 2021, 7(2): 022001.

Paper No: NERS-20-1116

DOI: https://doi.org/10.1115/1.4048768

Published Online: October 30, 2020

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Topics: Concretes, Irradiation (Radiation exposure), Neutrons, Accidents, Neutron flux, Gamma rays, Radiation (Physics)

Journal Articles

Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation

Yong Lu, Zheng Jiang, Linyang Li, Cuiping Wang, Yihui Guo, Jiajia Han, Xingjun Liu

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011605.

Paper No: NERS-19-1151

DOI: https://doi.org/10.1115/1.4047718

Published Online: October 5, 2020

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Topics: Diffusion (Physics), Irradiation (Radiation exposure), Phase diagrams, Zirconium

Journal Articles

Ni + and He + Implantation Effects on the Hardness and Microstructure of Heat-Treated X750 Superalloy

Maisaa N. Tawfeeq, Robert J. Klassen

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011602.

Paper No: NERS-19-1135

DOI: https://doi.org/10.1115/1.4046716

Published Online: October 1, 2020

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Topics: Alloys, Damage, Electron microscopy, Hardening, Heat, Helium, Ion implantation, Irradiation (Radiation exposure), Superalloys, Testing

Journal Articles

Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel

Petra Pónya, Gyula Csom, Sándor Fehér

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031110.

Paper No: NERS-19-1079

DOI: https://doi.org/10.1115/1.4046354

Published Online: June 5, 2020

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Topics: Coolants, Flow (Dynamics), Irradiation (Radiation exposure), Neutron flux, Neutrons, Reactor vessels, Supercritical water reactors, Design, Fuels, Temperature

Journal citation

NARROW

Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor

On Cyclotron-Based Production of Gallium-68 Isotope: A Computational Benchmark for the Production Yield & Shielding Considerations

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

Review of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in the National Research Universal Reactor

Radiation-Induced Surface Wettability Enhancement of an Indium Tin Oxide and Titanium Oxide Film-Coated Sapphire

Efficient Neutron Irradiation Procedure for Uniform Dopant Distributions in Silicon Doping

Reevaluation of Spectral Parameters and Neutron Fluxes in IC-7 Irradiation Channel of TRIGA MARK I IPR-R1 Research Nuclear Reactor

Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code

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

Utilizing of Spent Fuel Storage Pool in Gamma Irradiation Experiments

Neutronic Analysis of the European Sodium Fast Reactor: Part II—Burnup Results

Metallic Fast Reactor Separate Effect Studies for Fuel Safety

Safety Analysis of Indonesia's Multipurpose Reactor During Irradiation of Natural UO 2 Pin Target at Power Ramp Test Facility

The Use of Polycarbonate as Dosimeter of High Doses

Neutron Field Shaping Using Graphite for Reaction Rate Measurements

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

Study of a Gamma Radiation Impact on Concrete Properties Under Severe Accident Conditions

Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation

Ni + and He + Implantation Effects on the Hardness and Microstructure of Heat-Treated X750 Superalloy

Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel

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