@article{eace176525f64744887e4626c95ac6b6,
title = "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",
abstract = "The improved understanding of the safety, technical gaps, and major uncertainties of advanced fast reactors will result in designing their safe and economical operation. This paper focuses on the development of efficient and improved core thermal-hydraulics predictive capabilities for fast reactor modeling and simulation at the North Carolina State University. The described research and development activities include applying results of high-fidelity thermal-hydraulic simulations to inform the improved use of lower-order models within fast-running design and safety analysis tools to predict improved estimates of local safety parameters for efficient evaluation of realistic safety margins for fast reactors. The above-described high-to-low model information improvements are being verified and validated using benchmarks such as the OECD/NRC Liquid Metal Fast Reactor Core Thermal-Hydraulic Benchmark and code-to-code comparisons.",
keywords = "CTF, Hi2Lo, Multi-physics, Sodium fast reactors",
author = "C. Takasugi and A. Aly and D. Holler and A. Abarca and B. Beeler and M. Avramova and K. Ivanov",
note = "Funding Information: The data and information presented in the paper were accepted for the “IAEA Technical Meeting on State-of-the-art Thermal Hydraulics of Fast Reactors” and presented at the meeting in ENEA-Brasimone the 26-30 September 2022. A portion of this research made use of the resources of the High-Performance Computing Center at Idaho National Laboratory, which is supported by the Office of Nuclear Energy of the U.S. Department of Energy and the Nuclear Science User Facilities. A portion of this work was supported by the United States Nuclear Regulatory Commission, Grant 31310021M0009. The described benchmark activities are endorsed by OECD-NEA. This material is based upon work supported under an Integrated University Program Graduate Fellowship. Publisher Copyright: {\textcopyright} 2023 Elsevier B.V.",
year = "2023",
month = oct,
doi = "10.1016/j.nucengdes.2023.112474",
language = "English",
volume = "412",
journal = "Nuclear Engineering and Design",
issn = "0029-5493",
publisher = "Elsevier B.V.",
}