Development of new generation reduced activation ferritic-martenstic steels for advanced fusion reactors

Tan, Lizhen; Snead, Lance Lewis; Katoh, Yutai

doi:10.1016/j.jnucmat.2016.05.037

Title: Development of new generation reduced activation ferritic-martenstic steels for advanced fusion reactors

Journal Article · Thu May 26 00:00:00 EDT 2016 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2016.05.037· OSTI ID:1255666

Tan, Lizhen ^[1]; Snead, Lance Lewis ^[2]; Katoh, Yutai ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

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.

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Research Organization:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1255666

Alternate ID(s):: OSTI ID: 1325370

Journal Information:: Journal of Nuclear Materials, Vol. 478; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 94 works

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References (40)

Low-activation ferritic and martensitic steels for fusion application Kohyama, A.; Hishinuma, A.; Gelles, D. S. Journal of Nuclear Materials, Vol. 233-237 https://doi.org/10.1016/S0022-3115(96)00327-3	journal	October 1996
Impurity effects on reduced-activation ferritic steels developed for fusion applications Klueh, R. L.; Cheng, E. T.; Grossbeck, M. L. Journal of Nuclear Materials, Vol. 280, Issue 3 https://doi.org/10.1016/S0022-3115(00)00060-X	journal	August 2000
Stability of MX-type strengthening nanoprecipitates in ferritic steels under thermal aging, stress and ion irradiation Tan, L.; Byun, T. S.; Katoh, Y. Acta Materialia, Vol. 71 https://doi.org/10.1016/j.actamat.2014.03.015	journal	June 2014
Coarsening of precipitates in an advanced creep resistant 9% chromium steel—quantitative microscopy and simulations Gustafson, Åsa; Hättestrand, Mats Materials Science and Engineering: A, Vol. 333, Issue 1-2 https://doi.org/10.1016/S0921-5093(01)01874-3	journal	August 2002
Recent Developments in Irradiation-Resistant Steels Odette, G. R.; Alinger, M. J.; Wirth, B. D. Annual Review of Materials Research, Vol. 38, Issue 1, p. 471-503 https://doi.org/10.1146/annurev.matsci.38.060407.130315	journal	August 2008
Microstructure of oxide dispersion strengthened Eurofer and iron–chromium alloys investigated by means of small-angle neutron scattering and transmission electron microscopy Heintze, C.; Bergner, F.; Ulbricht, A. Journal of Nuclear Materials, Vol. 416, Issue 1-2 https://doi.org/10.1016/j.jnucmat.2010.11.102	journal	September 2011
Creep mechanisms of ferritic oxide dispersion strengthened alloys Wasilkowska, A.; Bartsch, M.; Messerschmidt, U. Journal of Materials Processing Technology, Vol. 133, Issue 1-2 https://doi.org/10.1016/S0924-0136(02)00237-6	journal	February 2003
Characterization of oxide nanoprecipitates in an oxide dispersion strengthened 14YWT steel using aberration-corrected STEM Hirata, A.; Fujita, T.; Liu, C. T. Acta Materialia, Vol. 60, Issue 16 https://doi.org/10.1016/j.actamat.2012.06.042	journal	September 2012
Designing Radiation Resistance in Materials for Fusion Energy Zinkle, S. J.; Snead, L. L. Annual Review of Materials Research, Vol. 44, Issue 1 https://doi.org/10.1146/annurev-matsci-070813-113627	journal	July 2014
Effect of thermomechanical treatment on 9Cr ferritic–martensitic steels Tan, L.; Busby, J. T.; Maziasz, P. J. Journal of Nuclear Materials, Vol. 441, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.01.323	journal	October 2013
Creep-strengthening of steel at high temperatures using nano-sized carbonitride dispersions Taneike, Masaki; Abe, Fujio; Sawada, Kota Nature, Vol. 424, Issue 6946 https://doi.org/10.1038/nature01740	journal	July 2003
Effect of tungsten and tantalum on the low cycle fatigue behavior of reduced activation ferritic/martensitic steels Shankar, Vani; Mariappan, K.; Nagesha, A. Fusion Engineering and Design, Vol. 87, Issue 4 https://doi.org/10.1016/j.fusengdes.2012.01.020	journal	May 2012
The effect of tungsten on dislocation recovery and precipitation behavior of low-activation martensitic 9Cr steels Abe, F.; Araki, H.; Noda, T. Metallurgical Transactions A, Vol. 22, Issue 10 https://doi.org/10.1007/BF02664988	journal	October 1991
Development of India-specific RAFM steel through optimization of tungsten and tantalum contents for better combination of impact, tensile, low cycle fatigue and creep properties Laha, K.; Saroja, S.; Moitra, A. Journal of Nuclear Materials, Vol. 439, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.03.073	journal	August 2013
Effect of tungsten on tensile properties and flow behaviour of RAFM steel Vanaja, J.; Laha, K.; Nandagopal, M. Journal of Nuclear Materials, Vol. 433, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.10.040	journal	February 2013
Effect of fine precipitation and subsequent coarsening of Fe2W laves phase on the creep deformation behavior of tempered martensitic 9Cr-W steels ABe, Fujio Metallurgical and Materials Transactions A, Vol. 36, Issue 2 https://doi.org/10.1007/s11661-005-0305-y	journal	February 2005
Effect of thermal aging on the microstructure and mechanical properties of 7–11 CrW steels de Carlan, Y.; Alamo, A.; Mathon, M. H. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/S0022-3115(00)00277-4	journal	December 2000
Influence of tantalum and nitrogen contents, normalizing condition and TMCP process on the mechanical properties of low-activation 9Cr–2W–0.2V–Ta steels for fusion application Hasegawa, T.; Tomita, Y.; Kohyama, A. Journal of Nuclear Materials, Vol. 258-263 https://doi.org/10.1016/S0022-3115(98)00138-X	journal	October 1998
Effects of alloying elements and thermomechanical treatment on 9Cr Reduced Activation Ferritic–Martensitic (RAFM) steels Tan, L.; Yang, Y.; Busby, J. T. Journal of Nuclear Materials, Vol. 442, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.10.015	journal	November 2013
Effect of W and Ta on creep–fatigue interaction behavior of reduced activation ferritic–martensitic (RAFM) steels Shankar, Vani; Mariappan, K.; Sandhya, R. Fusion Engineering and Design, Vol. 100 https://doi.org/10.1016/j.fusengdes.2015.06.191	journal	November 2015
Effect of silicon on the microstructure and mechanical properties of reduced activation ferritic/martensitic steel Chen, Shenghu; Rong, Lijian Journal of Nuclear Materials, Vol. 459 https://doi.org/10.1016/j.jnucmat.2015.01.004	journal	April 2015
Precipitation behavior of laves phase and its effect on toughness of 9Cr-2Mo Ferritic-martensitic steel Hosoi, Y.; Wade, N.; Kunimitsu, S. Journal of Nuclear Materials, Vol. 141-143 https://doi.org/10.1016/S0022-3115(86)80083-6	journal	November 1986
Thermodynamic modeling and kinetics simulation of precipitate phases in AISI 316 stainless steels Yang, Y.; Busby, J. T. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.02.008	journal	May 2014
Reduced-activation steels: Future development for improved creep strength Klueh, R. L. Journal of Nuclear Materials, Vol. 378, Issue 2 https://doi.org/10.1016/j.jnucmat.2008.05.010	journal	August 2008
Microstructure control for high strength 9Cr ferritic–martensitic steels Tan, L.; Hoelzer, D. T.; Busby, J. T. Journal of Nuclear Materials, Vol. 422, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.12.011	journal	March 2012
Conversion of MX nitrides to Z-phase in a martensitic 12% Cr steel Cipolla, Leonardo; Danielsen, Hilmar K.; Venditti, Dario Acta Materialia, Vol. 58, Issue 2 https://doi.org/10.1016/j.actamat.2009.09.045	journal	January 2010
Effect of creep deformation on Z phase formation in Gr.91 steel Sawada, K.; Kushima, H.; Tabuchi, M. Materials Science and Technology, Vol. 30, Issue 1 https://doi.org/10.1179/1743284713Y.0000000309	journal	December 2013
High-temperature mechanical properties and microstructure of 9Cr oxide dispersion strengthened steel compared with RAFMs Li, Yanfen; Nagasaka, Takuya; Muroga, Takeo Fusion Engineering and Design, Vol. 86, Issue 9-11 https://doi.org/10.1016/j.fusengdes.2011.03.004	journal	October 2011
Advances in Physical Metallurgy and Processing of Steels. Strengthening Mechanisms of Creep Resistant Tempered Martensitic Steel. Maruyama, Kouichi; Sawada, Kota; Koike, Jun-ichi ISIJ International, Vol. 41, Issue 6 https://doi.org/10.2355/isijinternational.41.641	journal	January 2001
The relation between polycrystal deformation and single-crystal deformation Kocks, U. F. Metallurgical and Materials Transactions B, Vol. 1, Issue 5 https://doi.org/10.1007/BF02900224	journal	May 1970
Formulating the strength factor α for improved predictability of radiation hardening Tan, L.; Busby, J. T. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.07.009	journal	October 2015
TEM characterization of precipitates in EUROFER 97 Klimenkov, M.; Lindau, R.; Materna-Morris, E. Progress in Nuclear Energy, Vol. 57 https://doi.org/10.1016/j.pnucene.2011.10.006	journal	May 2012
Quantitative TEM analysis of precipitation and grain boundary segregation in neutron irradiated EUROFER 97 Dethloff, Christian; Gaganidze, Ermile; Aktaa, Jarir Journal of Nuclear Materials, Vol. 454, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.07.078	journal	November 2014
Materials design data for reduced activation martensitic steel type F82H Tavassoli, A. -A. F.; Rensman, J. -W; Schirra, M. Fusion Engineering and Design, Vol. 61-62 https://doi.org/10.1016/S0920-3796(02)00255-7	journal	November 2002
Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys Klueh, R. L.; Shingledecker, J. P.; Swindeman, R. W. Journal of Nuclear Materials, Vol. 341, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2005.01.017	journal	May 2005
Present development status of EUROFER and ODS-EUROFER for application in blanket concepts Lindau, R.; Möslang, A.; Rieth, M. Fusion Engineering and Design, Vol. 75-79 https://doi.org/10.1016/j.fusengdes.2005.06.186	journal	November 2005
Thermal creep behaviour of the EUROFER 97 RAFM steel and two European ODS EUROFER 97 steels Yu, G.; Nita, N.; Baluc, N. Fusion Engineering and Design, Vol. 75-79 https://doi.org/10.1016/j.fusengdes.2005.06.311	journal	November 2005
Effects of carbide precipitation on the strength and Charpy impact properties of low carbon Mn–Ni–Mo bainitic steels Im, Young-Roc; Jun Oh, Yong; Lee, Byeong-Joo Journal of Nuclear Materials, Vol. 297, Issue 2 https://doi.org/10.1016/S0022-3115(01)00610-9	journal	August 2001
Effect of Carbide Size Distribution on the Impact Toughness of Tempered Martensitic Steels with Two Different Prior Austenite Grain Sizes Evaluated by Instrumented Charpy Test Takebayashi, Shigeto; Ushioda, Kohsaku; Yoshinaga, Naoki MATERIALS TRANSACTIONS, Vol. 54, Issue 7 https://doi.org/10.2320/matertrans.M2013079	journal	January 2013
Notch Impact Behavior of Oxide-Dispersion-Strengthened (ODS) Fe20Cr5Al Alloy Chao, J.; Capdevila, C.; Serrano, M. Metallurgical and Materials Transactions A, Vol. 44, Issue 10 https://doi.org/10.1007/s11661-013-1815-7	journal	June 2013

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