Machine learning-assisted surrogate construction for full-core fuel performance analysis

Che, Yifeng; Yurko, Joseph; Seurin, Paul; Shirvan, Koroush

doi:10.1016/j.anucene.2021.108905

Title: Machine learning-assisted surrogate construction for full-core fuel performance analysis

Journal Article · 01 April 2022 · Annals of Nuclear Energy

DOI:https://doi.org/10.1016/j.anucene.2021.108905· OSTI ID:1976816

Che, Yifeng; Yurko, Joseph; Seurin, Paul; Shirvan, Koroush

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Research Organization:: Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

DOE Contract Number:: NE0008752

OSTI ID:: 1976816

Journal Information:: Annals of Nuclear Energy, Vol. 168, Issue C; ISSN 0306-4549

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

References (11)

The PROMETRA Program: Fuel Cladding Mechanical Behavior under High Strain Rate Cazalis, B.; Desquines, J.; Poussard, C. Nuclear Technology, Vol. 157, Issue 3 https://doi.org/10.13182/NT07-A3814	journal	March 2007
Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response Deng, Yangbin; Shirvan, Koroush; Wu, Yingwei Journal of Nuclear Materials, Vol. 507 https://doi.org/10.1016/j.jnucmat.2018.04.023	journal	August 2018
Application of the Critical Heat Flux Look-Up Table to Large Diameter Tubes El Nakla, M.; Habib, M.; Ahmed, W. Science and Technology of Nuclear Installations, Vol. 2013 https://doi.org/10.1155/2013/868163	journal	January 2013
Lookup Tables for Predicting CHF and Film-Boiling Heat Transfer: Past, Present, and Future Groeneveld, D. C.; Leung, L. K. H.; Guo, Y. Nuclear Technology, Vol. 152, Issue 1 https://doi.org/10.13182/NT152-87	journal	October 2005
Lookup tables of critical heat fluxes Kirillov, P. L.; Bobkov, V. P.; Boltenko, �. A. Soviet Atomic Energy, Vol. 71, Issue 1 https://doi.org/10.1007/BF01137996	journal	July 1991
Physics-informed reinforcement learning optimization of nuclear assembly design Radaideh, Majdi I.; Wolverton, Isaac; Joseph, Joshua Nuclear Engineering and Design, Vol. 372 https://doi.org/10.1016/j.nucengdes.2020.110966	journal	February 2021
Light water reactor fuel performance modeling and multi-dimensional simulation Rashid, Joseph Y. R.; Yagnik, Suresh K.; Montgomery, Robert O. JOM, Vol. 63, Issue 8 https://doi.org/10.1007/s11837-011-0144-9	journal	August 2011
Coupled fuel performance calculations in VERA and demonstration on Watts Bar unit 1, cycle 1 Stimpson, S.; Clarno, K.; Pawlowski, R. Annals of Nuclear Energy, Vol. 145 https://doi.org/10.1016/j.anucene.2020.107554	journal	September 2020
Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1–3 Stimpson, Shane; Powers, Jeffrey; Clarno, Kevin Nuclear Engineering and Design, Vol. 327 https://doi.org/10.1016/j.nucengdes.2017.12.015	journal	February 2018
The Virtual Environment for Reactor Applications (VERA): Design and architecture Turner, John A.; Clarno, Kevin; Sieger, Matt Journal of Computational Physics, Vol. 326 https://doi.org/10.1016/j.jcp.2016.09.003	journal	December 2016
Modeling the tension–compression asymmetric yield behavior of β-treated Zircaloy-4 Zhai, Jinyuan; Gao, Xiaosheng; Sobotka, James C. Journal of Nuclear Materials, Vol. 451, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.04.017	journal	August 2014

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