Ferritic/martensitic steels for next-generation reactors
By R. Klueh, A. Nelson. 2007
825 citations recorded by the source corpus.
Subfields: Aerospace Engineering, Materials Chemistry
View Paper: https://www.semanticscholar.org/paper/30ca40a2c9365c5bd7915c5ad63690cef1096911
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In Aerospace Engineering
In Materials Chemistry
Citations in the corpus
- Selection of fuel cladding material for nuclear fission reactors (2011, background): “Additionally, thermal and irradiation-induced microstructural instabilities, such as the precipitation of brittle phases; the growth of the lath-packet substructures and the M23C6 and (V or Nb)C precipitates; and the formation of grain boundary cavities degrade the mechanical properties of F/M steel”