Studies on accelerated hydrogen isotopes permeation through plasma-facing components of fusion reactors

Wang, Lu; Zhou, Helin; Liu, Hao-Dong; Xu, Qianfan; Oya, Yasuhisa; Zhao, Mingzhong; Tanabe, T.; Luo, Guang–Nan

doi:10.1088/1402-4896/ab4966

Cited by 2 publications

(2 citation statements)

References 14 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…He plasma pre-irradiation experiments were performed in the Permeation and Retention Evaluation FACility for fusion Experiments (PREFACE) [18] at the Institute of Plasma Physics, Chinese Academy of Sciences. More details on PREFACE can be found in our previous works [18][19][20]. The microwave power for generating He plasma was 400 W. Plasma parameters were measured by a Langmuir probe.…”

Section: He Plasma Pre-irradiationmentioning

confidence: 99%

In situ measurements of low energy D plasma-driven permeation through He pre-damaged W

Zhou

Liu

et al. 2022

Nucl. Fusion

Self Cite

View full text Add to dashboard Cite

Experiments concerning the effect of helium (He) plasma exposure on deuterium (D) plasma-driven permeation (PDP) through tungsten (W) foils in a linear plasma facility has been performed. 0.05 mm thick W foils were exposed to ~2×1020 m-2s-1 He plasma with various fluences at 883 K. After He irradiating, D permeation tests were performed for the samples and retention was also measured by high-resolution thermal desorption spectroscopy (TDS). It was observed that He pre-irradiation resulted in a significant reduction of D permeation and retention in W. Microstructure observation indicated that the surfaces of samples after He irradiation turned rough and He nanobubbles were formed near the surface. The defective structure including He nanobubbles very likely enhances D reemission and accordingly reduces the permeation and retention in He pre-irradiated W.

show abstract

Section: He Plasma Pre-irradiationmentioning

confidence: 99%

In situ measurements of low energy D plasma-driven permeation through He pre-damaged W

Zhou

Liu

et al. 2022

Nucl. Fusion

Self Cite

View full text Add to dashboard Cite

show abstract

“…Hydrogen isotopes (deuterium and tritium) are the primary fuel for nuclear fusion; however, the migration and retention of hydrogen in structural materials affect the fuel efficiency, which could lead to hydrogen embrittlement [ 1 , 2 , 3 , 4 , 5 ]. Therefore, research on preparing stable hydrogen permeation barriers to reduce hydrogen solubility and diffusivity has become an important issue in the study of nuclear materials [ 6 , 7 , 8 , 9 ].…”

Section: Introductionmentioning

confidence: 99%

Investigation of the Oxidation Behavior of Cr20Mn17Fe18Ta23W22 and Microdefects Evolution Induced by Hydrogen Ions before and after Oxidation

Zhu

Cao

et al. 2022

Materials

View full text Add to dashboard Cite

The oxidation behavior of body-centered cubic (bcc) structure Cr20Mn17Fe18Ta23W22 refractory high-entropy alloy (RHEA) and the microdefects induced by hydrogen ions before and after oxidation were investigated. The results revealed that compared with oxidizing Cr20Mn17Fe18Ta23W22 at 800 °C (6.7 °C/min) for 4 h (ST3, Ar:O2 = 3:1), the heating procedure of oxidizing Cr20Mn17Fe18Ta23W22 at 300 °C (6 °C/min) for 2 h and then increased to 800 °C (5 °C/min) for 4 h is more conducive to the production of oxides without spalling on the surface, i.e., HT1 (Ar:O2 = 1:1), HT2 (Ar:O2 = 2:1) and HT3 (Ar:O2 = 3:1) samples. The oxidation of Cr20Mn17Fe18Ta23W22 RHEA is mainly controlled by the diffusion of cations instead of affinities with O. Additionally, HT1 and HT3 samples irradiated with a fluence of 3.9 × 1022 cm−2 hydrogen ions (60 eV) were found to have a better hydrogen irradiation resistance than Cr20Mn17Fe18Ta23W22 RHEA. The microdefects in irradiated Cr20Mn17Fe18Ta23W22 mainly existed as hydrogen bubbles, hydrogen-vacancy (H-V) complexes and vacancy/vacancy clusters. The microdefects in irradiated HT3 were mainly vacancies and H-V complexes, while the microdefects in irradiated HT1 mainly existed as vacancies and vacancy clusters, as large amounts of hydrogen were consumed to react with oxides on the HT1 surface. The oxides on the surface of the HT3 sample were more stable than those on HT1 under hydrogen irradiation.

show abstract

Studies on accelerated hydrogen isotopes permeation through plasma-facing components of fusion reactors

Cited by 2 publications

References 14 publications

In situ measurements of low energy D plasma-driven permeation through He pre-damaged W

In situ measurements of low energy D plasma-driven permeation through He pre-damaged W

Investigation of the Oxidation Behavior of Cr20Mn17Fe18Ta23W22 and Microdefects Evolution Induced by Hydrogen Ions before and after Oxidation

Contact Info

Product

Resources

About