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Nitrogen effects on radiation response in 12Cr ferritic/martensitic alloys
Scripta Materialia ( IF 5.3 ) Pub Date : 2020-12-01 , DOI: 10.1016/j.scriptamat.2020.08.005
E. Aydogan , J.G. Gigax , S.S. Parker , B.P. Eftink , M. Chancey , J. Poplawsky , S.A. Maloy

Abstract Ferritic/martensitic steels are one of the best candidates for structural materials for high dose applications in next generation nuclear reactors. The composition of structural materials must be optimized for reliable service during irradiation. This study reports the effect of interstitial nitrogen on radiation response in 12Cr ferritic/martensitic HT9 steels having a controlled nitrogen concentration. Results show that a high amount of ‘free’ nitrogen in the matrix stabilizes the interstitial clusters which leads to (i) larger loop sizes (ii) lower loop density and (iii) slightly reduced radiation induced hardening. It also affects diffusion mechanism of Ni and formation of Ni/Si-rich precipitates.

中文翻译:

氮对 12Cr 铁素体/马氏体合金辐射响应的影响

摘要 铁素体/马氏体钢是下一代核反应堆高剂量应用结构材料的最佳候选材料之一。必须优化结构材料的成分,以便在辐照期间可靠地使用。本研究报告了间隙氮对具有受控氮浓度的 12Cr 铁素体/马氏体 HT9 钢的辐射响应的影响。结果表明,基质中大量的“游离”氮稳定了间隙簇,这导致 (i) 较大的环尺寸 (ii) 较低的环密度和 (iii) 略微降低辐射诱发硬化。它还影响 Ni 的扩散机制和富 Ni/Si 沉淀物的形成。
更新日期:2020-12-01
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