High-Chromium Ferritic and Martensitic Steels for Nuclear Applications
By R. Klueh, D. Harries. 2001
472 citations recorded by the source corpus.
Subfields: Materials Chemistry, Mechanical Engineering
View Paper: https://www.semanticscholar.org/paper/f83655ed73130a96eb32675a28035ac69a83ef4e
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In Materials Chemistry
In Mechanical Engineering
- Zhongwen Yao
- Mercedes Hernández-Mayoral
- Mark Kirk
- G. Odette
- E. Marquis
- S. Zinkle
- Mike Jenkins
- David N. Seidman
Citations in the corpus
- α′ precipitation in neutron-irradiated Fe–Cr alloys (2014, background): “[1] R.”
- Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 2: Damage evolution in thin-foils at higher doses (2008, background): “superior alternatives to austenitic steels because of their better thermal properties and higher swelling resistance [1-3].”
- Microstructure of Neutron-irradiated Iron Before and After Tensile Deformation (2006, background): “international research to understand the effects of neutron irradiation on the physical and mechanical properties of ferritic/martensitic steels [1,5].”
- Progress in corrosion resistant materials for supercritical water reactors (2009, background): “Their microstructures usually consist of temperedmartensites laths forming subgrains in a ferrite matrix with carbides and carbonitrides precipitated on subgrain, lath boundaries, packet and prior austenite grain boundaries (PAGBs) [95–97].”
- Development of benchmark reduced activation ferritic/martensitic steels for fusion energy applications (2017, background): “Here the Cr equivalent concentration is described as follows [13].”