SiC and FeCrAl as Potential Cladding Materials for APR-1400 Neutronic Analysis

The aim of this study is to investigate the potential improvement of accident-tolerant fuels in pressurized water reactors for replacing existing reference zircaloy (Zr) fuel-cladding systems. Three main strategies for improving accident-tolerant fuels are investigated: enhancement of the present st...

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Bibliographic Details
Published in:Energies
Main Authors: Mohammad Alrwashdeh, Saeed A. Alameri
Format: Article
Language:English
Published: MDPI AG 2022-05-01
Subjects:
light water reactor
nuclear fuel
cladding
SiC
FeCrAl
Online Access:https://www.mdpi.com/1996-1073/15/10/3772

Internet

https://www.mdpi.com/1996-1073/15/10/3772

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