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Works (7)
2025 article
BWR core thermal–hydraulic uncertainty and sensitivity analysis with improved bypass modeling features
Ziyad, D., Abarca, A., & Avramova, M. (2025, February 26). Nuclear Engineering and Design, Vol. 435.
2025 article
Development of Serpent/CTF External Coupling for the OECD/NEA TVA-WB1 Benchmark Activities
Albagami, T., Rouxelin, P., Abarca, A., Palmtag, S., Avramova, M., & Ivanov, K. (2025, April 25). Nuclear Science and Engineering, Vol. 4.
2023 journal article
Development of an efficient and improved core thermal-hydraulics predictive capability for fast reactors: Summary of research and development activities at the North Carolina state University
Nuclear Engineering and Design, 412, 112474.
2022 journal article
CTF-PARCS Core Multi-Physics Computational Framework for Efficient LWR Steady-State, Depletion and Transient Uncertainty Quantification
Energies, 15(14), 5226.
open access via www.mdpi.com (publisher PDF)
2021 article
Incorporation and testing of refrigerant fluids (R-134a) in the subchannel analysis code CTF (COBRA-TF)
Shahid, U., Liu, Y., Abarca, A., & Novog, D. R. (2021, November 1). Progress in Nuclear Energy.
2019 article
A multi-scale and multi-physics simulation methodology with the state-of-the-art tools for safety analysis in Light Water Reactors applied to a Turbine Trip scenario (Part II)
Hidalga, P., Abarca, A., Miró, R., Sekrhi, A., & Verdú, G. (2019, May 24). Nuclear Engineering and Design.
2019 article
A multi-scale and multi-physics simulation methodology with the state-of-the-art tools for safety analysis in light water reactors applied to a turbine trip scenario (PART I)
Hidalga, P., Abarca, A., Miró, R., Sekrhi, A., & Verdú, G. (2019, May 23). Nuclear Engineering and Design.