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

S.J. Zinkle, J.L. Boutard, D.T. Hoelzer, A. Kimura, R. Lindau, G.R. Odette, M. Rieth, L. Tan, H. Tanigawa2017年被引用 184Nuclear FusionIF 3出版社

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. 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.

日本語訳

低活性フェライト/マルテンサイト鋼は、現在、提案されている核融合エネルギー炉の構造材料として最も技術的に成熟した選択肢である。先進的な次世代高性能鋼は、核融合炉の運転寿命と信頼性の向上、優れた中性子放射線損傷耐性、より高い熱力学的効率、および建設コストの低減の機会を提供する。核融合エネルギー用途向けの改良鋼を開発するための2つの主要な戦略は、(1)計算熱力学モデリングと修正された熱機械的処理(TMT)を用いて、より高性能な低活性フェライト/マルテンサイト(RAFM)鋼を製造する進化的経路、および(2)粉末冶金技術を用いて、非常に高温での運転が可能で、核融合中性子誘起特性劣化に対する潜在的に非常に高い耐性を有する超高強度酸化物分散強化(ODS)鋼を製造する、より高リスクで潜在的に高い見返りをもたらすアプローチに基づいている。これらの次世代高性能鋼の現在の開発状況が要約され、これらの材料の開発を成功させるための研究開発課題が概説されている。温度依存性の一軸降伏強度、引張伸び、高温熱クリープ、シャルピー衝撃延性-脆性遷移温度(DBTT)および破壊靭性挙動、ならびに中性子照射誘起低温硬化および脆化、および中間温度体積ボイドスエリング(核融合関連のヘリウムおよび水素生成に関連する影響を含む)を含む材料特性が、新しい鋼の研究用ヒートについて記述されている。

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Reduced activation ferritic/martensitic steelOxide dispersion strengthened steel
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