article · Annals of Nuclear Energy

A comprehensive assessment of neutronic and thermal–hydraulic behavior of some advanced accident-tolerant fuels in solid and dual-cooled annular PWR assemblies

Ouadie Kabach
Yasin Genç
Sinem Uzun
Bedrettin Uzun
El Mahjoub Chakir
Hamid Amsil

2026Ibn Tofail University

In plain language

No abstract is available for this record, so no summary has been generated.

Research topics

Nuclear Materials and Properties
Nuclear reactor physics and engineering
Nuclear Engineering Thermal-Hydraulics

Read the original research

This page summarises published work. The authoritative version sits with the publisher.

View on publisher site Record on OpenAlex

DOI: 10.1016/j.anucene.2026.112378

Is something wrong with this record? Report it or request removal.

Discussion

Discuss this research

Have you built on this work, tried to replicate it, or seen it applied in practice? Share what you know. Verified researchers and MARATTO™ domain experts can open a discussion, and any member can reply. Contributions are reviewed before they appear.

No discussion yet. Open the first thread.

New to MARATTO™? Create a free account.