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Article detail · 2026

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

Journal

Annals of Nuclear Energy
OpenAlex SJR Q1 JCR Q1 Citations 2 Top 10% Percentile 94.2% FWCI 4.22
Year
2026
DOI
10.1016/j.anucene.2026.112378
Type
article

Data source split

  • YÖKSİS venue Annals of Nuclear Energy
  • OpenAlex OpenAlex enrichment (abstract, citations, topics)

OpenAlex record

Abstract

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Topics

Citations

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2 citations

OpenAlex cited_by_count (cache / database)

2 publications in the local catalog that cite this work (OpenAlex reference match; not the full global list).

  1. A Data‐Driven Hybrid Uranium–Thorium Index for Revealing Nonlinear Nuclear–Gas Substitution Dynamics in Emerging Energy Systems 2026 Citations 0 · OpenAlex
  2. Coupled Neutronic and Thermal-Hydraulic Analysis of Inner Moderator Radius Effects in Dual-Cooled Annular UO 2 and Thorium-Based Fuels for a LW-SMR 2026 Citations 0 · OpenAlex

Authors

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