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Tritium release and retention in beryllium and titanium beryllide after neutron irradiation up to damage doses of 23-38 dpa

机译:中子照射后铍和钛铍在23-38dPa的损伤剂量后氚释放和保留

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摘要

Titanium beryllide is considered as an advanced neutron multiplier in the Helium Cooled Pebble Bed (HCPB) blanket of DEMO. Neutron irradiation of titanium beryllide together with beryllium as a reference material in material testing nuclear reactors can give essential data for the DEMO blanket design. Be-7at.%Ti (Be-7Ti) as well as Be were irradiated in the HFR, Petten, the Netherlands, at four temperatures of 710, 800, 940, 1040 K up to 23, 31, 36, 38 dpa, respectively. The post-irradiation examination (PIE) included thermal-programmed desorption (TPD) and Vickers hardness tests as well as microstructure study by optical metallography. Be and Be-7Ti pellets maintained their integrity after irradiation. Microstructure of Be-7Ti contains two phases, mainly, TiBe12, and also small amount of Be. Under irradiation, gas bubbles were formed in Be samples as well as in Be-phase in Be-7Ti samples. These bubbles contain helium and tritium produced in Be under irradiation. TPD tests showed a much lower tritium retention in Be-7Ti than in Be for all four irradiation temperatures. Vickers hardness of TiBe12 phase is much higher than that of Be-phase. According to the obtained data, Be-7Ti could be considered more preferred than Be as a neutron multiplier material in future fusion reactors due to the enhanced radiation damage resistance.
机译:钛铍被认为是氦气冷却卵石床(HCPB)毯子中的先进中子倍增器。中子照射钛的铍与铍作为材料测试中的参考材料,可以为演示毯设计提供必要的数据。 BE-7AT。%TI(BE-7TI)以及在HFR,PETTEN,荷兰,在710,800,940,1040K的四个温度下,分别在23,31,36,38 dPA的四个温度下辐照。后照射后检查(PIE)包括热编程的解吸(TPD)和维氏硬度测试以及光学金属间隙的微观结构研究。 BE和BE-7TI颗粒在照射后保持完整性。 BE-7TI的微观结构含有两阶段,主要是TIBE12,也是少量的。在辐照下,在BE-7TI样品中形成气泡,并在BE-7TI样品中形成。这些气泡含有氦气和在照射下产生的氚。 TPD试验表明,BE-7TI的氚保持大于所有四个照射温度。 TIBE12阶段的维克斯硬度远高于阶段的高。根据所获得的数据,由于增强的辐射损伤阻力,可以将BE-7TI更优选在未来的熔体反应堆中的中子倍增器材料。

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  • 来源
    《Fusion Engineering and Design》 |2020年第12期|111938.1-111938.7|共7页
  • 作者单位

    Karlsruhe Inst Technol Inst Appl Mat Hermann von Helmholtz Pl 1 D-76344 Eggenstein Leopoldshafen Germany;

    Karlsruhe Inst Technol Inst Appl Mat Hermann von Helmholtz Pl 1 D-76344 Eggenstein Leopoldshafen Germany;

    Karlsruhe Inst Technol Inst Appl Mat Hermann von Helmholtz Pl 1 D-76344 Eggenstein Leopoldshafen Germany;

    Karlsruhe Inst Technol Radioanalyt Lab Dept Safety & Environm Hermann von Helmholtz Pl 1 D-76344 Eggenstein Leopoldshafen Germany;

    Rokkasho Fusion Inst Quantum & Radiol Sci & Technol 2-166 Omotedate Aomori 0393212 Japan;

    Fus Energy F4E Josep Pla 2 Barcelona Spain;

  • 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

    Beryllium; Titanium beryllide; Neutron irradiation; Tritium retention;

    机译:铍;钛铍;中子辐照;氚保留;

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