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Journal Articles

A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset

Lorenzo Loi, Stefano Lorenzi, Antonio Cammi, Carolina Introini

Publisher: ASME

ASME J of Nuclear Rad Sci. January 2024, 10(1): 014502.

Paper No: NERS-23-1029

https://doi.org/10.1115/1.4064308

Published Online: December 22, 2023

View Article titled, A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset

Topics: Cycles, Fuels, Irradiation (Radiation exposure), Manufacturing, Nuclides, Simulation, Temperature, Uncertainty, Geometry, Errors

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

Publisher: ASME

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

Paper No: NERS-22-1039

https://doi.org/10.1115/1.4055931

Published Online: February 8, 2023

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

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

Publisher: ASME

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

Paper No: NERS-21-1126

https://doi.org/10.1115/1.4055257

Published Online: September 13, 2022

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

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

Journal Articles

Superphénix Benchmark Part I: Results of Static Neutronics

Alexander Ponomarev, Konstantin Mikityuk, Liang Zhang, Evgeny Nikitin, Emil Fridman, Francisco Álvarez-Velarde, Pablo Romojaro Otero, Antonio Jiménez-Carrascosa, Nuria García-Herranz, Ben Lindley, Una Baker, Armin Seubert, Romain Henry

Publisher: ASME

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011320.

Paper No: NERS-21-1046

https://doi.org/10.1115/1.4051449

Published Online: October 8, 2021

View Article titled, Superphénix Benchmark Part I: Results of Static Neutronics

Topics: Density, Fuels, Rods, Sodium, Temperature, Steel, Geometry, Cladding systems (Building), Neutrons, Chemical kinetics

Journal Articles

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

Martin Schulc, Michal Košťál, Jan Šimon, Evžen Novák

Publisher: ASME

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

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

Journal Articles

Flame-Free Combustion of Radioactive and Hazardous Wastes in the Salt Melt

Vojtěch Galek, Jaroslav Stoklasa, Jan Hadrava, Roman Vokatý

Publisher: ASME

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041305.

Paper No: NERS-19-1180

https://doi.org/10.1115/1.4046911

Published Online: June 3, 2020

View Article titled, Flame-Free Combustion of Radioactive and Hazardous Wastes in the Salt Melt

Topics: Combustion, Flames, Flue gases, Metals, Oxidation, Temperature, Radioisotopes, Hazardous wastes, Oxygen, Heavy metals

Journal Articles

Determination of β eff for ININ ' s TRIGA Reactor

J. Galicia-Aragón, R. Raya-Arredondo, H. S. Cruz-Galindo

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031502.

Paper No: NERS-19-1084

https://doi.org/10.1115/1.4046355

Published Online: May 15, 2020

View Article titled, Determination of β eff for ININ ' s TRIGA Reactor

Topics: Fuels, Neutrons, Isotopes, Uranium, Particulate matter

Journal Articles

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

Luis M. Palomino, Mohamed S. El-Genk, Timothy M. Schriener

Publisher: ASME

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

Topics: Cladding systems (Building), Emissions, Fuels, Neutrons, Photons, Steel, Vessels, Storage, Radioactivity, Isotopes

Journal Articles

Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location

Bie Yewang, Zhang Donghui, Xiong Wenbin, Li Huwei, Wu Mingyu, Wang Xinzhe

Publisher: ASME

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041018.

Paper No: NERS-17-1272

https://doi.org/10.1115/1.4040029

Published Online: September 10, 2018

View Article titled, Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location

Topics: China, Fast neutron reactors, Fuels, Manufacturing, Fuel rods, Isotopes, Heat transfer, Failure, Cladding systems (Building), Design

Journal Articles

Sputtering of Graphite by Hydrogen Isotopes in the Fusion Environment: A Molecular Dynamics Simulation Study

Qiang Zhao, Yang Li, Zheng Zhang, Xiaoping Ouyang

Publisher: ASME

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041022.

Paper No: NERS-17-1279

https://doi.org/10.1115/1.4040495

Published Online: September 10, 2018

View Article titled, Sputtering of Graphite by Hydrogen Isotopes in the Fusion Environment: A Molecular Dynamics Simulation Study

Topics: Carbon, Graphite, Hydrogen, Ions, Isotopes, Sputtering (Irradiation), Temperature, Molecular dynamics simulation, Atoms

Journal Articles

Methodology to Design Simulated Irradiated Fuel by Maximizing Integral Indices (ck, E, G)

Jason R. Sharpe, Adriaan Buijs, Jeremy Pencer

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021017.

Paper No: NERS-15-1079

https://doi.org/10.1115/1.4031074

Published Online: February 29, 2016

View Article titled, Methodology to Design Simulated Irradiated Fuel by Maximizing Integral Indices (ck, E, G)

Topics: Design, Fuels, Isotopes, Nuclear fission, Optimization, Spent nuclear fuels, Supercritical water reactors, Uncertainty, Density, Nuclides

Journal Articles

Theoretical Investigations on Laser-Assisted Depletion of Gd 152 Isotope From Natural Gadolinium

M. Sankari, M. V. Suryanarayana

Publisher: ASME

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041017.

Paper No: NERS-15-1002

https://doi.org/10.1115/1.4030504

Published Online: September 3, 2015

View Article titled, Theoretical Investigations on Laser-Assisted Depletion of Gd 152 Isotope From Natural Gadolinium

Topics: Excitation, Gadolinium, Ionization, Isotope shift, Isotopes, Lasers, Photoionization, Resonance, Atoms

Journal Articles

High-Efficiency Gamma-Beta Blind Alpha Spectrometry for Nuclear Energy Applications

Jeffrey A. Webster, Alexander Hagen, Brian C. Archambault, Nicholas Hume, Rusi Taleyarkhan

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2015, 1(3): 031006.

Paper No: NERS-14-1044

https://doi.org/10.1115/1.4029926

Published Online: May 20, 2015

View Article titled, High-Efficiency Gamma-Beta Blind Alpha Spectrometry for Nuclear Energy Applications

Topics: Alpha decay, Fluids, Isotopes, Nuclear fission, Pressure, Sensors, Spectroscopy, Tension, Neutrons, Simulation

Journal citation

NARROW

A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset

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

Superphénix Benchmark Part I: Results of Static Neutronics

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

Flame-Free Combustion of Radioactive and Hazardous Wastes in the Salt Melt

Determination of β eff for ININ ' s TRIGA Reactor

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

Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location

Sputtering of Graphite by Hydrogen Isotopes in the Fusion Environment: A Molecular Dynamics Simulation Study

Methodology to Design Simulated Irradiated Fuel by Maximizing Integral Indices (ck, E, G)

Theoretical Investigations on Laser-Assisted Depletion of Gd 152 Isotope From Natural Gadolinium

High-Efficiency Gamma-Beta Blind Alpha Spectrometry for Nuclear Energy Applications

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