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Title: Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications

Abstract

Reduced activation ferritic/martensitic steels are currently the most technologically mature option for the structural material of proposed fusion energy reactors. Advanced next-generation higher performance steels offer the opportunity for improvements in fusion reactor operational lifetime and reliability, superior neutron radiation damage resistance, higher thermodynamic efficiency, and reduced construction costs. The two main strategies for developing improved steels for fusion energy applications are based on (1) an evolutionary pathway using computational thermodynamics modelling and modified thermomechanical treatments (TMT) to produce higher performance reduced activation ferritic/martensitic (RAFM) steels and (2) a higher risk, potentially higher payoff approach based on powder metallurgy techniques to produce very high strength oxide dispersion strengthened (ODS) steels capable of operation to very high temperatures and with potentially very high resistance to fusion neutron-induced property degradation. The current development status of these next-generation high performance steels is summarized, and research and development challenges for the successful development of these materials are outlined. In conclusion, material properties including temperature-dependent uniaxial yield strengths, tensile elongations, high-temperature thermal creep, Charpy impact ductile to brittle transient temperature (DBTT) and fracture toughness behaviour, and neutron irradiation-induced low-temperature hardening and embrittlement and intermediate-temperature volumetric void swelling (including effects associated with fusion-relevant helium and hydrogenmore » generation) are described for research heats of the new steels.« less

Authors:
 [1];  [2];  [3];  [4];  [5];  [6];  [5];  [3];  [7]
  1. Univ. of Tennessee, Knoxville, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Alternative Energies and Atomic Energy Commission (CEA), Gif sur Yvette (France)
  3. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  4. Kyoto Univ. (Japan). Inst. of Advanced Energy
  5. Karlsruhe Inst. of Technology (KIT) (Germany)
  6. Univ. of California, Santa Barbara, CA (United States)
  7. Japan Atomic Energy Agency (JAEA), Rokkasho, Aomori (Japan)
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) (SC-24); European Union (EU)
OSTI Identifier:
1364282
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Fusion
Additional Journal Information:
Journal Volume: 57; Journal Issue: 9; Journal ID: ISSN 0029-5515
Publisher:
IOP Science
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; radiation effects; thermal creep strength; ductility; void swelling; yield strength; fracture toughness; point defect sink strength

Citation Formats

Zinkle, S. J., Boutard, J. L., Hoelzer, D. T., Kimura, A., Lindau, R., Odette, G. R., Rieth, M., Tan, L., and Tanigawa, H. Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications. United States: N. p., 2017. Web. doi:10.1088/1741-4326/57/9/092005.
Zinkle, S. J., Boutard, J. L., Hoelzer, D. T., Kimura, A., Lindau, R., Odette, G. R., Rieth, M., Tan, L., & Tanigawa, H. Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications. United States. doi:10.1088/1741-4326/57/9/092005.
Zinkle, S. J., Boutard, J. L., Hoelzer, D. T., Kimura, A., Lindau, R., Odette, G. R., Rieth, M., Tan, L., and Tanigawa, H. Fri . "Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications". United States. doi:10.1088/1741-4326/57/9/092005. https://www.osti.gov/servlets/purl/1364282.
@article{osti_1364282,
title = {Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications},
author = {Zinkle, S. J. and Boutard, J. L. and Hoelzer, D. T. and Kimura, A. and Lindau, R. and Odette, G. R. and Rieth, M. and Tan, L. and Tanigawa, H.},
abstractNote = {Reduced activation ferritic/martensitic steels are currently the most technologically mature option for the structural material of proposed fusion energy reactors. Advanced next-generation higher performance steels offer the opportunity for improvements in fusion reactor operational lifetime and reliability, superior neutron radiation damage resistance, higher thermodynamic efficiency, and reduced construction costs. The two main strategies for developing improved steels for fusion energy applications are based on (1) an evolutionary pathway using computational thermodynamics modelling and modified thermomechanical treatments (TMT) to produce higher performance reduced activation ferritic/martensitic (RAFM) steels and (2) a higher risk, potentially higher payoff approach based on powder metallurgy techniques to produce very high strength oxide dispersion strengthened (ODS) steels capable of operation to very high temperatures and with potentially very high resistance to fusion neutron-induced property degradation. The current development status of these next-generation high performance steels is summarized, and research and development challenges for the successful development of these materials are outlined. In conclusion, material properties including temperature-dependent uniaxial yield strengths, tensile elongations, high-temperature thermal creep, Charpy impact ductile to brittle transient temperature (DBTT) and fracture toughness behaviour, and neutron irradiation-induced low-temperature hardening and embrittlement and intermediate-temperature volumetric void swelling (including effects associated with fusion-relevant helium and hydrogen generation) are described for research heats of the new steels.},
doi = {10.1088/1741-4326/57/9/092005},
journal = {Nuclear Fusion},
number = 9,
volume = 57,
place = {United States},
year = {2017},
month = {6}
}

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Cited by: 24 works
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    Works referencing / citing this record:

    Microstructure Characterization and Mechanical Properties of Al Alloyed 9Cr ODS Steels with Different Al Contents
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    • Xu, Shuai; Zhou, Zhangjian; Jia, Haodong
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    Microstructure Characterization and Mechanical Properties of Al Alloyed 9Cr ODS Steels with Different Al Contents
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    • Xu, Shuai; Zhou, Zhangjian; Jia, Haodong
    • steel research international, Vol. 90, Issue 7
    • DOI: 10.1002/srin.201800594