Deuterium retention in W and W-Re alloy irradiated with high energy Fe and W ions: Effects of irradiation temperature

Hatano, Yuji; Ami, K.; Alimov, V.Kh.; Kondo, Sosuke; Hinoki, Tatsuya; Toyama, Takeshi; Fukuda, Makoto; Hasegawa, Akira; Sugiyama, K.; Oya, Yasuhisa; Oyaidzu, M.; Hayashi, Takao

doi:10.1016/j.nme.2016.06.016

Cited by 35 publications

(26 citation statements)

References 24 publications

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“…However, the suppression of void growth by adding Re to W crystals is still observed at high temperatures where no I-loop is formed8, so the mechanism discovered in Fe-Cr alloys seems irrelevant in W-Re alloys. Consequently, annihilation of vacancies at isolated interstitials seems to be a remaining possible explanation for the vacancy suppression observed in the experiment15. On top of that, all the above numerical analyses support this mechanism.…”

Section: Discussionsupporting

confidence: 62%

“…It is also known that inclusion of Re and Os into W crystals suppresses swelling13 and void growth14; such experiments suggest that Re or Os addition makes the material radiation-resistant. In addition, a recent study15 made another discovery that inclusion of Re reduces deuterium retention associated with the suppression of surviving vacancies; this is demonstrated by the fact that positron lifetime for W-Re alloys hardly increase after Fe-ion irradiation15. This implies that Re and Os not only cause RIP but also enhance vacancy-interstitial recombination that probably causes the suppression of void swelling.…”

mentioning

confidence: 99%

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Suppression of radiation-induced point defects by rhenium and osmium interstitials in tungsten

Suzudo

Hasegawa

2016

Sci Rep

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Modeling the evolution of radiation-induced defects is important for finding radiation-resistant materials, which would be greatly appreciated in nuclear applications. We apply the density functional theory combined with comprehensive analyses of massive experimental database to indicate a mechanism to mitigate the effect of radiation on W crystals by adding particular solute elements that change the migration property of interstitials. The resultant mechanism is applicable to any body-centered-cubic (BCC) metals whose self-interstitial atoms become a stable crowdion and is expected to provide a general guideline for computational design of radiation-resistant alloys in the field of nuclear applications.

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Section: Discussionsupporting

confidence: 62%

mentioning

confidence: 99%

Suppression of radiation-induced point defects by rhenium and osmium interstitials in tungsten

Suzudo

Hasegawa

2016

Sci Rep

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“…Universities are active research bodies for fundamental plasma-wall interactions using their infrastructure. Among the examples are the effects of re-deposition layer 68 , He implantation 69 , and displacing irradiation 70 on hydrogen isotope retention in plasma-facing materials.…”

Section: Iiid Plasma-wall Interaction Studiesmentioning

confidence: 99%

Overview of Fusion Engineering Research in Japan Focusing on Activities in NIFS and Universities

Muroga

Fukada

Hayashi

2019

Fusion Science and Technology

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This paper provides an overview of Japanese fusion engineering research activities focusing on those being carried out by NIFS and Japanese universities (Universities). NIFS is promoting the Fusion Engineering Research Project as one of the three research projects. The majority of the activity in the project is being carried out by collaboration with Universities. Utilizing core facilities installed in NIFS and the unique infrastructures of Universities, collaboration between NIFS and Universities is performed in superconducting magnet, liquid breeder blanket, advanced materials, high heat flux components, and tritium safety. NIFS also carries out international collaboration programs, such as Japan-China, Japan-USA, and IEA-based collaborations, promoting participation of University researchers. Responsibility division with QST, and contributions to ITER-BA and "Action Plan toward DEMO Development" are also reported.

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“…Работа [47] Зависимости интегрального накопления в исследованных образцах от дозы облучения представлены на рис. 3 из [48].…”

Section: накопление водорода в сплавах вольфрамаunclassified

“…Интересное наблюдение сделали авторы [47]: оказалось, что в некоторых условиях примесь рения подавляет формирование дефектов вакансионного типа (моновакансий и вакансионных кластеров) при облучении ионами высокой энергией. Такое легирование будет весьма полезно и востребовано, если оно позволит подавить формирование дефектов под действием нейтронного облучения.…”

Section: выводыunclassified

Hydrogen Retention in Doped Tungsten Materials Developed for Fusion

Голубева¹,

Черкез²

2018

PAST-TF

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Данный обзор посвящён влиянию легирования различными элементами на накопление в вольфраме. Вольфрам-один из наиболее перспективных обращённых к плазме материалов (ОПМ), обладающий тем не менее рядом недостатков. Для повышения пригодности вольфрама в качестве ОПМ предлагают легировать вольфрам различными добавками. К настоящему времени в рамках термоядерных разработок создано достаточно большое количество сплавов вольфрама. Легирование может изменить накопление водорода в вольфраме, и это должно быть тщательно учтено при выборе материалов для использования в термоядерных установках.

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Deuterium retention in W and W-Re alloy irradiated with high energy Fe and W ions: Effects of irradiation temperature

Cited by 35 publications

References 24 publications

Suppression of radiation-induced point defects by rhenium and osmium interstitials in tungsten

Suppression of radiation-induced point defects by rhenium and osmium interstitials in tungsten

Overview of Fusion Engineering Research in Japan Focusing on Activities in NIFS and Universities

Hydrogen Retention in Doped Tungsten Materials Developed for Fusion

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