首页> 外文期刊>Nuclear fusion >Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part Ⅱ: steels pre-damaged with 20 MeV W ions and high heat flux
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Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part Ⅱ: steels pre-damaged with 20 MeV W ions and high heat flux

机译:低能氘等离子体暴露下还原活化钢的表面改性和氘保留。第二部分:预损坏了20 MeV W离子和高热通量的钢

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摘要

The reduced-activation ferritic/martensitic (RAFM) steels including Eurofer (9Cr) and oxide dispersion strengthened (ODS) steels by the addition of Y_2O_3 particles investigated in Part Ⅰ were pre-damaged either with 20 MeV W ions at room temperature at IPP (Garching) or with high heat flux at FZJ (Juelich) and subsequently exposed to low energy (~20-200 eV per D) deuterium (D) plasma up to a fluence of 2.9 × 10~(25) D m~(-2) in the temperature range from 290 K to 700 K. The pre-irradiation with 20 MeV W ions at room temperature up to 1 displacement per atom (dpa) has no noticeable influence on the steel surface morphology before and after the D plasma exposure. The pre-irradiation with W ions leads to the same concentration of deuterium in all kinds of investigated steels, regardless of the presence of nanoparticles and Cr content. It was found that (ⅰ) both kinds of irradiation with W ions and high heat flux increase the D retention in steels compared to undamaged steels and (ⅱ) the D retention in both pre-damaged and undamaged steels decreases with a formation of surface roughness under the irradiation of steels with deuterium ions with incident energy which exceeds the threshold of sputtering. The increase in the D retention in RAFM steels pre-damaged either with W ions (damage up to ~3 μm) or high heat flux (damage up to ~10 μm) diminishes with increasing the temperature. It is important to mention that the near surface modifications caused by either implantation of high energy ions or a high heat flux load, significantly affect the total D retention at low temperatures or low fluences but have a negligible impact on the total D retention at elevated temperatures and high fluences because, in these cases, the D retention is mainly determined by bulk diffusion.
机译:在室温下在IPP下用20 MeV W离子对受损的铁素体/马氏体(RAFM)钢(包括Eurofer(9Cr)和氧化物弥散强化(ODS)钢)进行了预损伤(通过在第一部分中研究Y_2O_3颗粒的加入)(固结)或在FZJ(Juelich)处具有高热通量,然后暴露于低能量(约20-200 eV / D)氘(D)等离子体中,通量为2.9×10〜(25)D m〜(-2 )在290 K至700 K的温度范围内进行。在室温下以20 MeV W离子进行预辐照,直至D等离子体暴露前后,每个原子(dpa)位移高达1个位移对钢的表面形态没有明显影响。 W离子的预辐照导致所有研究钢种中的氘浓度相同,而与是否存在纳米粒子和Cr含量无关。发现(ⅰ)与未损坏的钢相比,(W)的两种W离子辐照和高热通量都增加了钢中的D保留率;(ⅱ)在预损坏和未损坏的钢中,D保留率均随着表面粗糙度的形成而降低。在钢中,氘离子的入射能量超过了溅射的阈值。随着温度的升高,RAFM钢中的D保留量的增加,无论是被W离子(高达〜3μm的损伤)还是由高热通量(高达〜10μm的损伤)预先破坏。值得一提的是,由高能离子注入或高热通量负载引起的近表面改性会显着影响低温或低通量下的总D保留量,但对高温下的总D保留量的影响可忽略不计和高通量,因为在这些情况下,D保留主要由体扩散决定。

著录项

  • 来源
    《Nuclear fusion》 |2017年第3期|036011.1-036011.9|共9页
  • 作者单位

    National Research Nuclear University 'MEPhI' (Moscow Engineering Physics Institute), Kashirskoe sh. 115409, Moscow, Russia;

    University of Science and Technology Beijing, Beijing 100083, People's Republic of China;

    Max-Planck Institute fuer Plasmaphysik, Garching, Germany;

    Max-Planck Institute fuer Plasmaphysik, Garching, Germany;

    Forschungszentrum Juelich GmbH 52425 Juelich, Germany;

    National Research Nuclear University 'MEPhI' (Moscow Engineering Physics Institute), Kashirskoe sh. 115409, Moscow, Russia;

    National Research Nuclear University 'MEPhI' (Moscow Engineering Physics Institute), Kashirskoe sh. 115409, Moscow, Russia;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    radiation-induced defects; simulation neutron irradiation; deuterium retention; ODS steels;

    机译:辐射引起的缺陷;模拟中子辐照氘retention留ODS钢;
  • 入库时间 2022-08-18 00:41:34

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