Simulation Analysis Based on Sodium-Cooled Fast Reactor Fuel Assembly Under Blockage Accident
Author:
Affiliation:
1. Shanghai University of Electric Power, Shanghai, China
Publisher
Informa UK Limited
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2024.2381391
Reference22 articles.
1. M. J. LINEBERRY and T. R. ALLEN “The Sodium-Cooled Fast Reactor (SFR) ” Argonne National Laboratory (2002).
2. Numerical investigation on thermal-hydraulic characteristics of NaK in a helical wire wrapped annulus
3. M. RAGHEB “Fermi-1 Fuel Meltdown Incident ” NPRE 457 Course Syllabus “Safety Analysis of Nuclear Reactor System ” University of Illinois at Urbana-Champaign (2019); https://mragheb.com/NPRE%20457%20CSE%20462%20Safety%20Analysis%20of%20Nuclear%20Reactor%20Systems/Fermi%20I%20Fuel%20Meltdown%20Incident.pdf.
4. High-fidelity experimental measurements for modeling and simulation of nuclear engineering applications
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