Development of new generation reduced activation ferritic-martenstic steels for advanced fusion reactors
Abstract
International development of reduced activation ferritic-martensitic (RAFM) steels has focused on 9 wt percentage Cr, which primarily contain M23C6 (M = Cr-rich) and small amounts of MX (M = Ta/V, X = C/N) precipitates, not adequate to maintain strength and creep resistance above ~500 °C. To enable applications at higher temperatures for better thermal efficiency of fusion reactors, computational alloy thermodynamics coupled with strength modeling have been employed to explore a new generation RAFM steels. The new alloys are designed to significantly increase the amount of MX nanoprecipitates, which are manufacturable through standard and scalable industrial steelmaking methods. Preliminary experimental results of the developed new alloys demonstrated noticeably increased amount of MX, favoring significantly improved strength, creep resistance, and Charpy impact toughness as compared to current RAFM steels. Furthermore, the strength and creep resistance were comparable or approaching to the lower bound of, but impact toughness was noticeably superior to 9–20Cr oxide dispersion-strengthened ferritic alloys.
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Fusion Energy Sciences (FES)
- OSTI Identifier:
- 1255666
- Alternate Identifier(s):
- OSTI ID: 1325370
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 478; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; precipitates; strengthening; toughness; ODS ferritic steel; reduced activation ferritic-martensitic steels
Citation Formats
Tan, Lizhen, Snead, Lance Lewis, and Katoh, Yutai. Development of new generation reduced activation ferritic-martenstic steels for advanced fusion reactors. United States: N. p., 2016.
Web. doi:10.1016/j.jnucmat.2016.05.037.
Tan, Lizhen, Snead, Lance Lewis, & Katoh, Yutai. Development of new generation reduced activation ferritic-martenstic steels for advanced fusion reactors. United States. https://doi.org/10.1016/j.jnucmat.2016.05.037
Tan, Lizhen, Snead, Lance Lewis, and Katoh, Yutai. Thu .
"Development of new generation reduced activation ferritic-martenstic steels for advanced fusion reactors". United States. https://doi.org/10.1016/j.jnucmat.2016.05.037. https://www.osti.gov/servlets/purl/1255666.
@article{osti_1255666,
title = {Development of new generation reduced activation ferritic-martenstic steels for advanced fusion reactors},
author = {Tan, Lizhen and Snead, Lance Lewis and Katoh, Yutai},
abstractNote = {International development of reduced activation ferritic-martensitic (RAFM) steels has focused on 9 wt percentage Cr, which primarily contain M23C6 (M = Cr-rich) and small amounts of MX (M = Ta/V, X = C/N) precipitates, not adequate to maintain strength and creep resistance above ~500 °C. To enable applications at higher temperatures for better thermal efficiency of fusion reactors, computational alloy thermodynamics coupled with strength modeling have been employed to explore a new generation RAFM steels. The new alloys are designed to significantly increase the amount of MX nanoprecipitates, which are manufacturable through standard and scalable industrial steelmaking methods. Preliminary experimental results of the developed new alloys demonstrated noticeably increased amount of MX, favoring significantly improved strength, creep resistance, and Charpy impact toughness as compared to current RAFM steels. Furthermore, the strength and creep resistance were comparable or approaching to the lower bound of, but impact toughness was noticeably superior to 9–20Cr oxide dispersion-strengthened ferritic alloys.},
doi = {10.1016/j.jnucmat.2016.05.037},
journal = {Journal of Nuclear Materials},
number = ,
volume = 478,
place = {United States},
year = {Thu May 26 00:00:00 EDT 2016},
month = {Thu May 26 00:00:00 EDT 2016}
}
Web of Science
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Works referencing / citing this record:
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