Thermal desorption behavior of deuterium for 6 MeV Fe ion irradiated W with various damage concentrations

Oya, Yasuhisa; Li, Xiao-Chun; Sato, Masayuki; Yuyama, Kenta; Zhang, Long; Kondo, Sosuke; Hinoki, Tatsuya; Hatano, Yuji; Watanabe, Hideo; Yoshida, N.; Chikada, Takumi

doi:10.1016/j.jnucmat.2015.03.032

Cited by 43 publications

(16 citation statements)

References 25 publications

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“…Even the lowest damage dose of 0.0003 dpa lead to an increase in retention determined by TDS by more than a factor of two. A further increase by a factor of 4.6 was reported for the highest dose of 1 dpa [54]. They claim saturation above 0.1 dpa.…”

Section: Integrated D Amountsmentioning

confidence: 82%

“…It is possible that defect creation was minimized due to the floating target arrangement and thus low deuterium ion energy. Oya et al [54] also saw a clear increase in retention with damage dose for their 6 MeV Fe-irradiated tungsten after 1 keV D 2 + low-flux ion implantation at 300 K (black circles). Even the lowest damage dose of 0.0003 dpa lead to an increase in retention determined by TDS by more than a factor of two.…”

Section: Integrated D Amountsmentioning

confidence: 87%

Section: Integrated D Amountsmentioning

confidence: 99%

“…Numerous experiments fulfilling the above selection criteria were conducted to study the influence of radiation damage on fuel retention [34,[42][43][44][45][46][47][48][49][50][51][52][53][54][55][56][57][58][59][60]. In many of these studies, only thermal desorption spectroscopy (TDS) is applied to determine the amount of deuterium released from the sample [48,54,56]. In other studies, ion beam analysis (IBA) is applied to determine the total amount of deuterium retained within the first few microns from the surface [55] or to quantify the local absolute concentrations [49,51,57].…”

Section: Integrated D Amountsmentioning

confidence: 99%

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A critical review of experiments on deuterium retention in displacement-damaged tungsten as function of damaging dose

Schwarz-Selinger

2023

Mater. Res. Express

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Experimental results from the literature on the evolution of deuterium retention in displacement-damaged tungsten as a function of damaging dose are presented. Except for a few outliers, retention is generally found to increase with the presence of displacement damage. However, total retention results scatter by three orders of magnitude for similar exposure temperatures and are difficult to compare, because they depend on experiment-specific parameters such as the irradiation energy used to produce the displacement damage or the deuterium exposure parameters such as fluence. Even local deuterium concentration measurements were found to scatter by more than one order of magnitude. An experimental methodology is proposed that allows robust conclusions about the evolution of deuterium retention with damage dose and the results are discussed in detail. Recrystallized tungsten is irradiated with 20.3 MeV self-ions at room temperature with different damage doses ranging from 0.001 to 2.3 displacements per atom. The defects are then decorated with a low flux, low-energy deuterium plasma at 450 K sample temperature. 3He Nuclear Reaction Analysis (NRA) shows that the deuterium concentration levels off from the linear increase already at very low damage dose of about 0.005 dpa. At a damage dose of 0.23 dpa a maximum deuterium concentration of about 1.4 at% is reached. Thermal Desorption Spectroscopy (TDS) shows that with damage increasing above 0.005 dpa, the overall shape of the desorption spectra does not change substantially, only their intensities increase. Total amounts derived from TDS are in quantitative agreement with results from 3He-NRA. Experimental results following this methodology also agree quantitatively with very recent parameter-free modeling of damage evolution.

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Section: Integrated D Amountsmentioning

confidence: 82%

Section: Integrated D Amountsmentioning

confidence: 87%

Section: Integrated D Amountsmentioning

confidence: 99%

Section: Integrated D Amountsmentioning

confidence: 99%

See 2 more Smart Citations

A critical review of experiments on deuterium retention in displacement-damaged tungsten as function of damaging dose

Schwarz-Selinger

2023

Mater. Res. Express

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“…Heavy ion and self-ion implantation experiments have been carried out by various authors to study the effect of dpa in the damage and defect microstructure (Hideo et al, 2014; Ogorodnikova et al, 2014; Oya et al, 2015). They have shown that ion irradiation primarily results in vacancy and interstitial clustering at room temperature.…”

Section: Introductionmentioning

confidence: 99%

Effect of Heavy Mass Ion (Gold) and Light Mass Ion (Boron) Irradiation on Microstructure of Tungsten

et al. 2019

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The difference in the defect structures produced by different ion masses in a tungsten lattice is investigated using 80 MeV Au7+ ions and 10 MeV B3+ ions. The details of the defects produced by ions in recrystallized tungsten foil samples are studied using transmission electron microscopy. Dislocations of type b = 1/2[111] and [001] were observed in the analysis. While highly energetic gold ion produced small clusters of defects with very few dislocation lines, boron has produced large and sparse clusters with numerous dislocation lines. The difference in the defect structures could be due to the difference in separation between primary knock-on atoms produced by gold and boron ions.

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Interaction of Hydrogen Isotopes with Radiation Damaged Tungsten

Oya

Azuma

Togari

et al. 2017

Advances in Intelligent Systems and Computing

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Thermal desorption behavior of deuterium for 6 MeV Fe ion irradiated W with various damage concentrations

Cited by 43 publications

References 25 publications

A critical review of experiments on deuterium retention in displacement-damaged tungsten as function of damaging dose

A critical review of experiments on deuterium retention in displacement-damaged tungsten as function of damaging dose

Effect of Heavy Mass Ion (Gold) and Light Mass Ion (Boron) Irradiation on Microstructure of Tungsten

Interaction of Hydrogen Isotopes with Radiation Damaged Tungsten

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