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Nuclear Science and Engineering Volume 194, 2020 - Issue 11: Selected papers from the 2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2019)
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TECHNICAL PAPERS

serpentTools: A Python Package for Expediting Analysis with Serpent

Andrew E. Johnsona Georgia Institute of Technology, Atlanta, Georgia30316Correspondence[email protected]
ORCID Iconhttps://orcid.org/0000-0003-2125-8775
ORCID Icon,
Dan Kotlyara Georgia Institute of Technology, Atlanta, Georgia30316ORCID Iconhttps://orcid.org/0000-0002-5581-7400
ORCID Icon,
Stefano Terlizzia Georgia Institute of Technology, Atlanta, Georgia30316ORCID Iconhttps://orcid.org/0000-0002-2179-6963
ORCID Icon &
Gavin Ridleyb Massachusetts Institute of Technology, Cambridge, Massachusetts02139ORCID Iconhttps://orcid.org/0000-0003-1635-8042
ORCID Icon
Pages 1016-1024 | Received 15 Nov 2019, Accepted 28 Jan 2020, Published online: 06 Mar 2020

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Nicolo’ Abrate, Alex Aimetta, Sandra Dulla & Nicola Pedroni. (2023) Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design. Nuclear Science and Engineering 197:12, pages 2977-2999.
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Articles from other publishers (17)

Alexander A. Ryzhkov, Georgy V. Tikhomirov & Mikhail Yu. Ternovykh. (2024) Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel. Annals of Nuclear Energy 197, pages 110248.
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Nicholas Dunkle, Jarod Richardson, Visura Pathirana, Alex Wheeler, Ondrej Chvala & Steven E. Skutnik. (2023) NERTHUS thermal spectrum molten salt reactor neutronics and dynamic model. Nuclear Engineering and Design 411, pages 112390.
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C. Reiter, A. Bergeron, D. Bonete-Wiese, M. Kirst, J. Mercz, R. Schönecker, K. Shehu, B. Ozar, F. Puig, J. Licht, W. Petry & P. Müller-Buschbaum. (2023) A Low-Enriched Uranium (LEU) option for the conversion of FRM II. Annals of Nuclear Energy 183, pages 109599.
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Nicholas Jon Dunkle, Jarod Richardson, Visura Pathirana, Alexander Wheeler, Ondrej Chvala & Steven E. Skutnik. (2023) Nerthus Thermal Spectrum Molten Salt Reactor Neutronics and Dynamic Model. SSRN Electronic Journal.
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V. Mishra, Zs. Elter, E. Branger & S. Grape. (2023) Statistical analysis of fuel cycle data from Swedish Pressurized Water Reactors and the impact of simplifying assumptions on simulated nuclide inventories. Progress in Nuclear Energy 155, pages 104483.
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César A. Cárdenas R.Carlos Andrés Collazos Morales, Juan Carlos Amaya, Fabian C. Castro, César E. Mora, Ramón E. R. Gonzalez, José L. Simancas-García & Farid A. Meléndez Pertuz. 2023. Computational Science and Its Applications – ICCSA 2023. Computational Science and Its Applications – ICCSA 2023 3 18 .
M. Krecicki & D. Kotlyar. (2022) Thermal hydraulic modeling of solid-fueled nuclear thermal propulsion reactors part II: Full-core coupled neutronic and thermal hydraulic analysis. Annals of Nuclear Energy 179, pages 109397.
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C. Erika Moss, Ondřej Chvála, Harrison Reisinger, Alexander M. Wheeler & Dallas Moser. (2022) Neutronics and fuel cycle modeling of a thorium-fueled two-fluid molten salt iso-breeder reactor. Annals of Nuclear Energy 177, pages 109299.
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Mattia Massone, Nicolò Abrate, Giuseppe Francesco Nallo, Domenico Valerio, Sandra Dulla & Piero Ravetto. (2022) Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors. Annals of Nuclear Energy 174, pages 109124.
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M. Krecicki, J. Wang & D. Kotlyar. (2022) Thermal hydraulic modeling of solid fueled nuclear thermal propulsion reactors Part I: Development and verification. Annals of Nuclear Energy 173, pages 109113.
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Nicolò Abrate, Sandra Dulla & Piero Ravetto. (2021) Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors. Annals of Nuclear Energy 164, pages 108623.
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Andrew Johnson & Dan Kotlyar. (2021) Hybrid depletion framework using mixed-fidelity transport solutions and substeps. Annals of Nuclear Energy 155, pages 108120.
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V. Mishra, Zs. Elter, S. Grape, P. Jansson, E. Branger, S. Vaccaro & M. Hedberg. (2020) Estimating gamma and neutron radiation fluxes around BWR quivers for nuclear safeguards verification purposes. Journal of Instrumentation 15:12, pages P12023-P12023.
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John P. Carter & R.A. Borrelli. (2020) Integral molten salt reactor temperature sensitivities using Serpent target motion sampling. Nuclear Engineering and Design 369, pages 110863.
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Victor Petitgenet, Christopher D. Roper, Matthew Krecicki, Andrew J. Yatsko, Dan Kotlyar, Dimitri N. Mavris & David Shalat. (2020) A Coupled Approach to the Design Space Exploration of Nuclear Thermal Propulsion Systems. A Coupled Approach to the Design Space Exploration of Nuclear Thermal Propulsion Systems.
Nicholas Jon Dunkle, Visura Pathirana, Alexander Wheeler, Ondrej Chvala & Steven E. Skutnik. (2022) NERTHUS Thermal Molten Salt Reactor Neutronics and Fuel Cycle Model. SSRN Electronic Journal.
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Vaibhav Mishra, Zsolt Elter, Erik Branger & Sophie Grape. (2022) Statistical Analysis of Fuel Cycle Data from Swedish Pressurized Water Reactors and the Impact of Simplifying Assumptions on Simulated Nuclide Inventories. SSRN Electronic Journal.
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