Analysis of trapping sites for deuterium in W-Cr-Y SMART alloy

被引：4

作者：

Harutyunyan, Z. ^{[1
]}

Gasparyan, Yu. ^{[1
]}

Efimov, V. ^{[1
]}

Litnovsky, A. ^{[2
]}

Klein, F. ^{[2
]}

Pisarev, A. ^{[1
]}

Coenen, J. W. ^{[2
]}

Linsmeier, Ch. ^{[2
]}

机构：

[1] Natl Res Nucl Univ MEPhI, Moscow Engn Phys Inst, Kashirskoe Shosse 31, Moscow 115409, Russia

[2] Forschungszentrum Julich, Inst Energie & Klimaforsch, D-52425 Julich, Germany

来源：

VACUUM | 2022年 / 199卷

基金：

俄罗斯科学基金会;

关键词：

Smart tungsten alloys; Helium; Deuterium; Thermal desorption spectroscopy; Plasma facing materials; Nuclear fusion; PASSIVATING TUNGSTEN ALLOYS; PLASMA-FACING MATERIALS; THERMAL-DESORPTION; FUSION DEMO; SAFETY; RETENTION; ISSUES; HYDROGEN; IMPURITIES; TRITIUM;

D O I：

10.1016/j.vacuum.2022.110956

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Deuterium (D) retention in tungsten-chromium-yttrium (W-Cr-Y) alloy depending on the irradiation fluence of 1019(-5) x 10(21) D/m(2) at various sample temperatures in the range of 300-900 K was investigated using in-situ thermal desorption spectroscopy (TDS). The irradiation was carried out using 2 keV D-3(+) ions (670eV/D). An increased D retention compared to that of pure polycrystalline W and additional high-temperature peaks were observed in TDS. The de-trapping energy of 2.21 +/- 0.05 eV for these traps was determined by the Kissinger method using the series of experiment with different heating rates. The total D retention dropped down at elevated irradiation temperatures and was rather small at 900 K, but has a local maximum at about 700 K.

引用

页数：6

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