D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation

Oya Y.; Sun F.; Yamauchi Y.; Nobuta Y.; Shimada M.; Taylor C. N.; Wampler W. R.; Nakata M.; Garrison L. M.; Hatano Y.

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D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation

机译：具有高温中子辐射的单晶钨的保留和深度型谱

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摘要

Single crystalline W (tungsten) samples irradiated at 633, 963 and 1073 K by neutrons to a damage level of 0.1 dpa were exposed to a high-flux D (deuterium) plasma at 673, 873 and 973 K, respectively, in TPE (Tritium Plasma Experiment) at INL (Idaho National Laboratory). Deuterium desorption was analyzed by TDS (Thermal Desorption Spectroscopy), and D depth profiles were determined by NRA (Nuclear Reaction Analysis) at SNL (Sandia National Laboratories). HIDT (Hydrogen Isotope Diffusion and Trapping) simulation code was applied to evaluate D behavior for neutron-damaged W at higher temperature.

机译：在633,963和1073k处照射到0.1dPa的损伤水平的单晶W（钨）样品在TPE（氚）分别在673,873和973k处暴露于高通量D（氘）血浆（氚血浆实验）在INL（爱达荷国家实验室）。通过TDS（热解吸光谱）分析氘解吸，DDS深度曲线由SNL（Sandia National Laboratories）的NA（核反应分析）确定。 HIDT（氢同位素扩散和捕获）仿真代码被应用于在较高温度下评估中子损伤W的D行为。

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来源
《Journal of Nuclear Materials: Materials Aspects of Fission and Fusion》 |2020年第1期|共7页
作者
Oya Y.; Sun F.; Yamauchi Y.; Nobuta Y.; Shimada M.; Taylor C. N.; Wampler W. R.; Nakata M.; Garrison L. M.; Hatano Y.;
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作者单位

Shizuoka Univ Shizuoka Japan;

Shizuoka Univ Shizuoka Japan;

Hokkaido Univ Sapporo Hokkaido Japan;

Hokkaido Univ Sapporo Hokkaido Japan;

Idaho Natl Lab Idaho Falls ID USA;

Idaho Natl Lab Idaho Falls ID USA;

Sandia Natl Labs POB 5800 Albuquerque NM 87185 USA;

Shizuoka Univ Shizuoka Japan;

Oak Ridge Natl Lab Oak Ridge TN USA;

Univ Toyama Toyama Japan;

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原文格式 PDF
正文语种 eng
中图分类原子能技术;
关键词
Single crystal tungsten; Deuterium retention; Neutron irradiation; TDS; NRA; HIDT; Nuclear fusion;

机译：单晶钨;氘保留;中子辐照;TDS;NRA;HIDT;核聚变;

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专利

1. D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation [J] . Oya Y., Sun F., Yamauchi Y., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2020,第1期

机译：具有高温中子辐射的单晶钨的保留和深度型谱
2. Deuterium retention in neutron-irradiated single-crystal tungsten [J] . M. Shimada, Y. Oya, W.R. Wampler, Fusion Engineering and Design . 2018,第PTaB期

机译：中子辐照单晶钨中的氘保留
3. Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron [J] . Kobayashi Makoto, Shimada Masashi, Taylor Chase N., Fusion Engineering and Design . 2019,第Sepa期

机译：辐照缺陷的动态退火对中子辐照钨中氘保留行为的影响
4. (0090)Evaluation of depth profile of hardness in ion-irradiated tungsten (W) single crystal [C] . Eva HASENHUETL, Yoosung HA, Kiyohiro YABUUCHI 日本金属学会春期大会 . 2015

机译：（0090）在离子辐照钨（W）单晶中的硬度深度分布评估
5. Effects of Argon on Deuterium Retention in Polycrystalline Tungsten under Sequential and Simultaneous Ion Irradiation [D] . Shanahan, Julian Alexander. 2018

机译：氩气对序贯和同时离子辐射下多晶硅钨氘保留的影响
6. Homogenization of Radial Temperature by a Tungsten Sink in Sublimation Growth of 45 mm AlN Single Crystal [O] . Yue Yu, Botao Liu, Xia Tang, 2020

机译：钨罐升温升温升华生长升高的均质化45毫米ALN单晶
7. Deuterium retention in neutron-irradiated single-crystal tungsten [O] . M. Shimada, Y. Oya, W.R. Wampler, 2018

机译：中子辐照单晶钨的氘保持

D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation

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