Burst Safety Analysis of Strengthened FeCrAl Claddings in APR1400 Fuel Rods Subject to LOCA Conditions

• Published in: Energy science & engineering Vol. 13; no. 2; pp. 728 - 741
• Main Authors: Ubaid, Jabir, Alaleeli, Maithah, Yi, Yongsun, Alameri, Saeed A., Schiffer, Andreas
• Format: Journal Article
• Language: English
• Published: London John Wiley & Sons, Inc 01.02.2025
• Subjects: accident tolerant fuel; Alloying elements; Alloys; Aluminum; Bursting strength; Chromium; cladding failure; Claddings; Design; Diameters; FeCrAl; Ferrous alloys; finite element analysis; Heat conductivity; Loss of coolant accidents; loss‐of‐coolant accident; Material properties; Mechanical properties; Molybdenum; nuclear fuel; Nuclear fuel elements; Nuclear safety; Oxidation; Pellets; Performance evaluation; Plasma sintering; Radiation; Safety; Stainless steel; Temperature; Thermomechanical analysis; Thickness; Ultimate tensile strength; Yield strength; Zircaloys (trademark); Zirconium alloys

ABSTRACT Because of their greater accident tolerance, iron‐chromium‐aluminum (FeCrAl) alloys hold great promise for applications in nuclear fuel claddings. Here, a finite element‐based computational framework is developed to analyze the thermomechanical performance of APR1400 fuel rods with FeCrAl c...