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首页> 外文期刊>International Materials Reviews >Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors
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Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors

机译：高温铁素体和马氏体钢及其在未来核反应堆中的应用

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摘要

In the 1970s, high chromium (9-12 percent Cr) ferritic/martensitic steels became candidates for elevated temperature applications in the core of fast reactors. Steels developed for conventional power plants, such as Sandvik HT9, a nominally Fe-12Cr-1Mo-0.5W-0.5Ni-0.25V-0.2C steel (composition in wt-percent), were considered in the USA, Europe and Japan. Now, a new generation of fission reactors is in the planning stage, and ferritic, bainitic and martensitic steels are again candidates for in-core and out-of-core applications. Since the 1970s, advances have been made in developing steels with 2-12 percent Cr for conventional power plants that are significant improvements over steels originally considered. The present study will review the development of the new steels to illustrate the advantages they offer for the new reactor concepts. Elevated temperature mechanical properties will be emphasised. Effects of alloying additions on long-time thermal exposure with and without stress (creep) will be examined. Information on neutron radiation effects will be discussed as it applies to ferritic and martensitic steels.
机译：在1970年代，高铬（9-12％Cr）铁素体/马氏体钢成为快速反应堆堆芯中高温应用的候选者。在美国，欧洲和日本，已考虑为常规发电厂开发的钢，例如山特维克HT9，名义上的Fe-12Cr-1Mo-0.5W-0.5Ni-0.25V-0.2C钢（以重量百分比计）。现在，新一代裂变反应堆正处于计划阶段，铁素体，贝氏体和马氏体钢再次成为核内和核外应用的候选者。自1970年代以来，在常规发电厂中开发的Cr含量为2-12％的钢已取得了进步，这是对最初考虑的钢的重大改进。本研究将回顾新型钢的发展，以说明它们为新型反应堆概念提供的优势。将强调高温机械性能。将研究合金添加对有或无应力（蠕变）的长时间热暴露的影响。关于中子辐射效应的信息将被讨论，因为它适用于铁素体和马氏体钢。

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