High Chromium Ferritic and Martensitic Steels for Nuclear Applications

By G. Lucas. 2002

168 citations recorded by the source corpus.

Subfields: Materials Chemistry, Mechanical Engineering

View Paper: https://www.semanticscholar.org/paper/07fd26757865c7005a2d2a3a589e18e33418686c

How researchers see this paper

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

In Materials Chemistry

1. K. Terrani
2. L. Snead
3. S. Zinkle
4. J. Bischoff
5. T. Allen
6. D. Crawford
7. A. Motta
8. C. Azevedo

In Mechanical Engineering

1. L. Snead
2. K. Terrani
3. J. Bischoff
4. T. Allen
5. D. Crawford
6. S. Zinkle
7. A. Motta

Citations in the corpus

• Advanced Oxidation Resistant Iron-Based Alloys for LWR Fuel Cladding (2014, background): “Dimensional changes due to void swelling or irradiation creep in austenitic [117,118] and ferritic/martensitic [119,126] steels are not expected to be of concern for LWR cladding conditions ( 300 C, 15 dpa).”
• Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment (2014, background): “5Mo, 2W) [32], a development of the Type 91 from which the EUROFERtype RAFM steels were developed.”
• Oxidation behavior of ferritic-martensitic and ODS steels in supercritical water (2012, background): “This metallurgic process creates alloys containing the martensitic lath structure and where all the carbon in solution has precipitated as Cr23C6 along the lath and prior austenite grain boundaries [45].”
• Lead-Cooled Fast Reactor Systems and the Fuels and Materials Challenges (2007, background): “Recent work has shown that the embrittlement of T91 correlates strongly with the available He produced in the material during irradiation, with DBTT reaching values above 100◦C [27].”