Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors

By R. Klueh. 2005

578 citations recorded by the source corpus.

Subfields: Aerospace Engineering, Materials Chemistry

View Paper: https://www.semanticscholar.org/paper/1e062096051b18e76cb5badca0a88305eda95c23

How researchers see this paper

The researchers whose trusted networks rank it highest, strongest advocate first. Every researcher gets a different order.

In Aerospace Engineering

1. J. Rothwell
2. D. Abson
3. C. Azevedo

In Materials Chemistry

1. W. Qu
2. J. Rothwell
3. R. Hui
4. D. Crawford
5. Chunwen Sun
6. D. Abson
7. S. Yick
8. C. Azevedo

Citations in the corpus

• 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].”
• Fuels for sodium-cooled fast reactors: US perspective (2007, background): “These potential limitations for austenitic alloys have driven cladding material development to the ferritic–martensitic alloys [76] and oxide disper-sion-strengthened (ODS) varieties where very high-cladding temperatures are required.”
• Review of type IV cracking of weldments in 9–12%Cr creep strength enhanced ferritic steels (2013, background): “The dislocation density reduces during tempering, PWHT and service, and the martensitic laths break down into softer equiaxed sub-grains as the martensite tempers further to ferrite.(49)”