APA (7th ed.) Citation

Wilson, D., Iacovides, H., Tatli, E., Stansbury, C., & Ferroni, P. (2025). Thermal-hydraulic analysis of a representative Westinghouse lead-cooled fast reactor fuel bundle using CFD. Nuclear Engineering & Design, 439, N.PAG. https://doi.org/10.1016/j.nucengdes.2025.114117

Chicago Style (17th ed.) Citation

Wilson, D., H. Iacovides, E. Tatli, C. Stansbury, and P. Ferroni. "Thermal-hydraulic Analysis of a Representative Westinghouse Lead-cooled Fast Reactor Fuel Bundle Using CFD." Nuclear Engineering & Design 439 (2025): N.PAG. https://doi.org/10.1016/j.nucengdes.2025.114117.

MLA (9th ed.) Citation

Wilson, D., et al. "Thermal-hydraulic Analysis of a Representative Westinghouse Lead-cooled Fast Reactor Fuel Bundle Using CFD." Nuclear Engineering & Design, vol. 439, 2025, p. N.PAG, https://doi.org/10.1016/j.nucengdes.2025.114117.