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Journal of Nuclear Science and Technology Volume 57, 2020 - Issue 8
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Article

Modeling of gap conductance for LWR fuel rods applied in the BISON code

Aysenur Toptana Computational Mechanics and Materials, Idaho National Laboratory, Idaho Falls, ID, USACorrespondence[email protected]
ORCID Iconhttps://orcid.org/0000-0003-4250-6336
ORCID Icon,
Jason D. Halesa Computational Mechanics and Materials, Idaho National Laboratory, Idaho Falls, ID, USAORCID Iconhttps://orcid.org/0000-0003-0836-0476
ORCID Icon,
Richard L. Williamsona Computational Mechanics and Materials, Idaho National Laboratory, Idaho Falls, ID, USA
,
Stephen R. Novasconea Computational Mechanics and Materials, Idaho National Laboratory, Idaho Falls, ID, USAORCID Iconhttps://orcid.org/0000-0002-3938-4326
ORCID Icon,
Giovanni Pastorea Computational Mechanics and Materials, Idaho National Laboratory, Idaho Falls, ID, USAORCID Iconhttps://orcid.org/0000-0003-2812-506X
ORCID Icon &
David J. Kropaczekb Reactor and Nuclear Systems, Oak Ridge National Laboratory, Oak Ridge, TN, USAORCID Iconhttps://orcid.org/0000-0002-9111-8682
ORCID Icon
Pages 963-974 | Received 06 Dec 2019, Accepted 03 Mar 2020, Published online: 09 Apr 2020

Citations (9)

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Read on this site (3)

Alexander Duenas, Daniel Wachs, Guillaume Mignot, Jose N. Reyes, Qiao Wu & Wade Marcum. (2022) Dynamical System Scaling Application to Zircaloy Cladding Thermal Response During Reactivity-Initiated Accident Experiment. Nuclear Science and Engineering 196:2, pages 193-208.
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Richard L. Williamson, Jason D. Hales, Stephen R. Novascone, Giovanni Pastore, Kyle A. Gamble, Benjamin W. Spencer, Wen Jiang, Stephanie A. Pitts, Albert Casagranda, Daniel Schwen, Adam X. Zabriskie, Aysenur Toptan, Russell Gardner, Christoper Matthews, Wenfeng Liu & Hailong Chen. (2021) BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms. Nuclear Technology 207:7, pages 954-980.
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HyeonTae Kim & Yonghee Kim. (2021) Unstructured Mesh–Based Neutronics and Thermomechanics Coupled Steady-State Analysis on Advanced Three-Dimensional Fuel Elements with Monte Carlo Code iMC. Nuclear Science and Engineering 195:5, pages 464-477.
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Articles from other publishers (6)

Federico Antonello, Jacopo Buongiorno & Enrico Zio. (2023) Insights in the safety analysis of an early microreactor design. Nuclear Engineering and Design 404, pages 112203.
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Federico Antonello, Jacopo Buongiorno & Enrico Zio. (2022) A methodology to perform dynamic risk assessment using system theory and modeling and simulation: Application to nuclear batteries. Reliability Engineering & System Safety 228, pages 108769.
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Nathan Capps, Ryan Sweet, Jason Harp & Christian M. Petrie. (2021) High-burnup fuel stress analysis prior to and during a LOCA transient. Journal of Nuclear Materials 556, pages 153194.
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Aysenur Toptan, Wen Jiang, Jason D. Hales, Benjamin W. Spencer, Albert Casagranda & Stephen R. Novascone. (2021) FEA-aided investigation of the effective thermal conductivity in a medium with embedded spheres. Nuclear Engineering and Design 381, pages 111355.
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Mohamed Y.M. Mohsen, Mohamed A.E. Abdel-Rahman, Mohamed Safaa Hassan & A. Abdelghafar Galahom. (2021) Investigating the possible advantage of using LM bonded gap instead of helium in Ap-1000 nuclear power reactor. Nuclear Engineering and Design 380, pages 111302.
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Aysenur Toptan, Nathan W. Porter, Jason D. Hales, Benjamin W. Spencer, Martin Pilch & Richard L. Williamson. (2020) Construction of a Code Verification Matrix for Heat Conduction With Finite Element Code Applications. Journal of Verification, Validation and Uncertainty Quantification 5:4.
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