03Da08
欠陥導入タングステン−10%レニウム合金における重水素滞留挙動に及ぼす照射温度影響
Influence of irradiation temperature on D retention behavior
in damaged W-10%Re alloy
猪爪菜央 1、小池彩華 2、山﨑翔太 2、和田拓郎 2、芦沢京祐 2、孫飛 1、
吉田直亮 3、檜木達也 4、大矢恭久 1
1
INOZUME Nao , KOIKE Ayaka2, YAMAZAKI Shota2, WADA Takuro2, ASHIZAWA Kyosuke2,SUN Fei1, YOSHIDA Naoaki3, HINOKI Tatsuya4, OYA Yasuhisa1
1

静岡大理、2 静岡大院総合科学技術、3 九大応力研、4 京大エネ研
1
Faculty of Science, Shizuoka University,
2
Graduate School of Integrated Science and Technology, Shizuoka University,
3Research Institute for Applied Mechanics, Kyushu University, 4Institute of Advanced Energy,Kyoto University

2. Experiment
The polycrystalline W-10%Re samples (6mmφ,0.5mmt) purchased from A.L.M.T. Co. Ltd were used.
These samples were annealed in vacuum at 1173 K
for 30 minutes to remove residual defects andhydrogen. Thereafter, 6.4 MeV Fe3+ was irradiated tothese samples at room temperature (R.T.) and 573 K
with damage level of 1 dpa by DuET (Dual-Beam
Facility for Energy Science and Technology, KyotoUniversity). 1.0 keV D2+ irradiation was performed
with the ion flux of 1.0 × 1018 D+ m-2 s-1 up to the ion
fluence of 1.0 × 1022 D+ m-2 at R.T.. After that, TDS
measurement was performed from R.T. up to 1173 K
with the heating rate of 0.5 K s-1.
3. Results and Discussion
Fig. 1 shows the D2 TDS spectra for W-10%Re(undamaged and Fe3+ damaged) samples and W(damaged at R.T.) sample[2]. The highest D retention
was found for W-10%Re sample irradiated at R.T..
Large D desorption was found at higher temperatureside, namely 600 K and 850 K, indicating that stable
D trapping sites would be formed by Fe3+ irradiation
at R.T.. For the samples irradiated at R.T., the valueof the D retention in the W-10%Re sample wasreached to be 4.2×1020 D/m2 while that of W was
2.4×1020 D/m2. From the results, it was found that thepresence of Re affects the D retention.
On the other hand, W-10%Re sample irradiated at573 K had no D desorption at higher temperature side,
indicating that the defects in W-10%Re sample wererecovered by annealing during Fe3+ irradiation at 573
K, considering that Re atoms would be precipitatedaround trapping sites such as vacancies and voids[1],due to higher mobility of Re atoms compared to thatof W atoms at 573 K, and Re atoms would beoccupied at the irradiation defects.

Desorption rate/ 1017 D2m-2s-1

1. Introduction
Tungsten (W) is a candidate material for plasma
facing materials (PFMs) in the fusion reactors due toits higher melting point and lower sputtering yield.
During the operation, W will be irradiated byenergetic particles, like deuterium (D) tritium (T) andneutrons, which would introduce irradiation defects,leading to the enhancement of hydrogen isotope
retention. In addition, since W will be irradiated by
14MeV neutrons (n), rhenium (Re) could begenerated by nuclear transmutation. Therefore, it isimportant to investigate the hydrogen isotope
retention behavior of W-Re alloys.

undamaged W-10Re
W-10Re damaged at R.T.
W-10Re damaged at 573K
W damaged at R.T. [2]

3.0

2.0

1.0

0.0

400

600

800

1000

Temperature / KFig. 1. D2 TDS spectra of W and W-10%Re samples
damaged at various temperature
4. References[1] T.Hwang et al., J. Nucl. Mater., 507 (2018) 78-86.
[2] Y.Oya et al., J. Nucl. Mater., 461 (2015) 336-340.