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Journal Articles

Benchmarking Fast Neutrons Leakage Spectrum From Copper Block with 252cf Source in Center

Tomas Czakoj, Michal Kostal, Martin Schulc, Vojtech Rypar, Evzen Novak, Evzen Losa

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1038

DOI: https://doi.org/10.1115/1.4056508

Published Online: December 16, 2022

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Topics: Copper, Leakage, Neutrons, Uncertainty, Density, Calibration, Cross section (Physics), Engineering simulation, Manufacturing, Nuclear industry

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

Comparative Study on the Impact of endf/b-vii.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled Accelerator-Driven System Calculation Results Using Monte Carlo Method Codes

Thanh Mai Vu, Donny Hartanto

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011502.

Paper No: NERS-21-1143

DOI: https://doi.org/10.1115/1.4054080

Published Online: June 7, 2022

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Topics: Cermets, Uncertainty, Ceramics

Journal Articles

Radon Equilibrium Equivalent Concentration Uncertainty of Calibration System With Alpha Self-Absorption Consideration

Mostafa Y. A. Mostafa, M. Vasyanovich, M. Zhukovsky

ASME J of Nuclear Rad Sci. July 2022, 8(3): 032002.

Paper No: NERS-20-1146

DOI: https://doi.org/10.1115/1.4048633

Published Online: May 27, 2022

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Topics: Equilibrium (Physics), Uncertainty, Calibration, Absorption, Filters, Radiation measurement, Sensors

Journal Articles

Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA

Emmanuel K. Boafo, Emmanuel Numapau Gyamfi

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031703.

Paper No: NERS-21-1094

DOI: https://doi.org/10.1115/1.4053050

Published Online: May 26, 2022

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Topics: Accidents, Hydrogen, Sensitivity analysis, Uncertainty, Uncertainty quantification, Uncertainty analysis, Design, Optimization

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

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

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041902.

Paper No: NERS-21-1029

DOI: https://doi.org/10.1115/1.4051447

Published Online: March 16, 2022

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Topics: Accidents, Fuels, Hardware, Neutrons, Nuclear power stations, Particulate matter, Spent nuclear fuels, Storage, Uncertainty, Manufacturing

Journal Articles

Cross Section and Fission Yields Induced Uncertainty in the Water–Water Energetic Reactor-440 Burnup Calculation

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

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041502.

Paper No: NERS-21-1010

DOI: https://doi.org/10.1115/1.4051613

Published Online: March 16, 2022

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Topics: Fuels, Nuclear fission, Uncertainty, Water, Nuclides, Neutrons

Journal Articles

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

Riku Tuominen, Ville Valtavirta

ASME J of Nuclear Rad Sci. October 2022, 8(4): 044503.

Paper No: NERS-21-1019

DOI: https://doi.org/10.1115/1.4051445

Published Online: March 15, 2022

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Topics: Boiling water reactors, Emissions, Heat, Manufacturing, Nuclear fission, Photons, Probability, Resonance, Spent nuclear fuels, Nuclides

Journal Articles

Nuclear Regulatory Acceptance of Certified Process Data Reconciliation

Andy Jansky, Magnus Langenstein

ASME J of Nuclear Rad Sci. April 2022, 8(2): 022101.

Paper No: NERS-20-1199

DOI: https://doi.org/10.1115/1.4051619

Published Online: October 19, 2021

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Topics: Measurement uncertainty, Nuclear power stations, Uncertainty, Safety, Feedwater, Flow (Dynamics)

Journal Articles

Visualization of Radioactive Substances Using a Freely Moving Gamma-Ray Imager Based on Structure From Motion

Sato Yuki, Minemoto Kojiro, Nemoto Makoto, Torii Tatsuo

ASME J of Nuclear Rad Sci. October 2021, 7(4): 042003.

Paper No: NERS-20-1073

DOI: https://doi.org/10.1115/1.4048843

Published Online: April 16, 2021

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Topics: Atomic force microscopy, Gamma rays, Imaging, Radioactive substances, Uncertainty, Radiation (Physics), Radiation sources, Sensors

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 on Description of Plant Status at Fukushima Accident by Emergency Action Level

Kazufumi Nagashima, Nakahiro Yasuda

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011701.

Paper No: NERS-19-1030

DOI: https://doi.org/10.1115/1.4046841

Published Online: October 1, 2020

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Topics: Accidents, Emergencies, Evacuations, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Protective actions, Decision making, Uncertainty

Journal Articles

Best-Estimate Plus Uncertainty Analysis of CANDU Fuel Reliability Using Manufacturing and Simulated Core Data

Jason J. Song, Paul K. Chan, Hugues W. Bonin, Mahesh Pandey

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041111.

Paper No: NERS-19-1167

DOI: https://doi.org/10.1115/1.4047162

Published Online: September 4, 2020

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Topics: Fuels, Manufacturing, Simulation, Transients (Dynamics), Temperature, Uncertainty, Pressure

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

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041113.

Paper No: NERS-19-1170

DOI: https://doi.org/10.1115/1.4047552

Published Online: September 4, 2020

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Topics: Boiling water reactors, Containment, Explosions, Failure, Steam, Vessels, Risk, Accidents, Uncertainty

Journal Articles

The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors

M. D. Tucker, D. R. Novog

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031401.

Paper No: NERS-19-1065

DOI: https://doi.org/10.1115/1.4045485

Published Online: March 9, 2020

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Topics: Algorithms, Cross section (Physics), Feedback, Fuels, Simulation, Uncertainty, Uncertainty analysis, Uranium, Physics, Diffusion (Physics)

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

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011402.

Paper No: NERS-18-1132

DOI: https://doi.org/10.1115/1.4044000

Published Online: November 29, 2019

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Topics: Design, Fast neutron reactors, Nuclear fission, Nuclides, Uncertainty, Uncertainty analysis, Licensing, Neutrons, Rods, Simulation

Journal Articles

Application of Cross Sections Uncertainty Propagation Framework to Light and Heavy Water Reactor Systems

Dongli Huang, Hany S. Abdel-Khalik

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011104.

Paper No: NERS-18-1134

DOI: https://doi.org/10.1115/1.4045032

Published Online: November 8, 2019

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Topics: Uncertainty

Journal citation

NARROW

Manuscript

Benchmarking Fast Neutrons Leakage Spectrum From Copper Block with 252cf Source in Center

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

Comparative Study on the Impact of endf/b-vii.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled Accelerator-Driven System Calculation Results Using Monte Carlo Method Codes

Radon Equilibrium Equivalent Concentration Uncertainty of Calibration System With Alpha Self-Absorption Consideration

Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA

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

Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One

Cross Section and Fission Yields Induced Uncertainty in the Water–Water Energetic Reactor-440 Burnup Calculation

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

Nuclear Regulatory Acceptance of Certified Process Data Reconciliation

Visualization of Radioactive Substances Using a Freely Moving Gamma-Ray Imager Based on Structure From Motion

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 on Description of Plant Status at Fukushima Accident by Emergency Action Level

Best-Estimate Plus Uncertainty Analysis of CANDU Fuel Reliability Using Manufacturing and Simulated Core Data

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

The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors

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

Application of Cross Sections Uncertainty Propagation Framework to Light and Heavy Water Reactor Systems

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