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铁素体、铁素体-马氏体和奥氏体氧化物弥散强化合金中的辐照效应综述

The Irradiation Effects in Ferritic, Ferritic-Martensitic and Austenitic Oxide Dispersion Strengthened Alloys: A Review.

作者信息

Luptáková Natália, Svoboda Jiří, Bártková Denisa, Weiser Adam, Dlouhý Antonín

机构信息

Institute of Physics of Materials, Czech Academy of Sciences, Žižkova 22, 616 62 Brno, Czech Republic.

出版信息

Materials (Basel). 2024 Jul 10;17(14):3409. doi: 10.3390/ma17143409.

DOI:10.3390/ma17143409
PMID:39063702
原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC11277775/
Abstract

High-performance structural materials (HPSMs) are needed for the successful and safe design of fission and fusion reactors. Their operation is associated with unprecedented fluxes of high-energy neutrons and thermomechanical loadings. In fission reactors, HPSMs are used, e.g., for fuel claddings, core internal structural components and reactor pressure vessels. Even stronger requirements are expected for fourth-generation supercritical water fission reactors, with a particular focus on the HPSM's corrosion resistance. The first wall and blanket structural materials in fusion reactors are subjected not only to high energy neutron irradiation, but also to strong mechanical, heat and electromagnetic loadings. This paper presents a historical and state-of-the-art summary focused on the properties and application potential of irradiation-resistant alloys predominantly strengthened by an oxide dispersion. These alloys are categorized according to their matrix as ferritic, ferritic-martensitic and austenitic. Low void swelling, high-temperature He embrittlement, thermal and irradiation hardening and creep are typical phenomena most usually studied in ferritic and ferritic martensitic oxide dispersion strengthened (ODS) alloys. In contrast, austenitic ODS alloys exhibit an increased corrosion and oxidation resistance and a higher creep resistance at elevated temperatures. This is why the advantages and drawbacks of each matrix-type ODS are discussed in this paper.

摘要

裂变和聚变反应堆的成功与安全设计需要高性能结构材料(HPSMs)。它们的运行伴随着前所未有的高能中子通量和热机械载荷。在裂变反应堆中,HPSMs用于例如燃料包壳、堆芯内部结构部件和反应堆压力容器。对于第四代超临界水裂变反应堆,预计要求更高,特别关注HPSM的耐腐蚀性。聚变反应堆中的第一壁和包层结构材料不仅受到高能中子辐照,还受到强烈的机械、热和电磁载荷。本文对主要通过氧化物弥散强化的抗辐照合金的性能和应用潜力进行了历史和最新综述。这些合金根据其基体分为铁素体、铁素体-马氏体和奥氏体。低空洞肿胀、高温氦脆化、热硬化和辐照硬化以及蠕变是铁素体和铁素体-马氏体氧化物弥散强化(ODS)合金中最常研究的典型现象。相比之下,奥氏体ODS合金在高温下表现出更高的耐腐蚀性和抗氧化性以及更高的抗蠕变性。这就是本文讨论每种基体类型ODS优缺点的原因。

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3
Fundamental Improvement of Creep Resistance of New-Generation Nano-Oxide Strengthened Alloys via Hot Rotary Swaging Consolidation.
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Materials (Basel). 2020 Nov 18;13(22):5217. doi: 10.3390/ma13225217.
4
Development of an oxide-dispersion-strengthened steel by introducing oxygen carrier compound into the melt aided by a general thermodynamic model.利用通用热力学模型,通过在熔体中引入氧载体化合物来开发氧化物弥散强化钢。
Sci Rep. 2016 Dec 12;6:38621. doi: 10.1038/srep38621.
5
Vacancy-controlled ultrastable nanoclusters in nanostructured ferritic alloys.纳米结构铁素体合金中的空位控制超稳定纳米团簇
Sci Rep. 2015 May 29;5:10600. doi: 10.1038/srep10600.
6
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7
Key role for nuclear energy in global biodiversity conservation.核能在全球生物多样性保护中的关键作用。
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