Graphite, nuclear technology, radiation studies

This cluster of papers focuses on the characterization, behavior, and properties of nuclear graphite materials used in high temperature gas-cooled reactors. It covers topics such as oxidation behavior, microstructural characterization, irradiation damage, thermal properties, Raman spectroscopy, pore structure analysis, fracture behavior, and decontamination methods.

Journals publishing in this area

1

Carbon

ISSN 0008-62232,162 articles in this topic

383h-index

9.69Impact

30.4KArticles

1.5MCitations

2

IEEE Transactions on Nuclear Science

ISSN 0018-94991,319 articles in this topic

181h-index

1.21Impact

32.9KArticles

475KCitations

3

Journal of Nuclear Materials

ISSN 0022-31151,086 articles in this topic

212h-index

2.50Impact

33.4KArticles

770.3KCitations