Quantitative characterization of deuterium and helium retention in the marked tiles with various materials exposed to HL-2A tokamak

• D and He retention features in HL-2A tokamak tiles were analyzed using ex-situ LID-QMS with 2D space-resolution. • LID-QMS results indicate D and He retention in HL-2A tokamak has a uniform distribution along the poloidal direction. • D retention is C-film>W-film>Fe-film/bulk S.S>bulk W, while He retention is Fe-film>bulk S.S>W-film>bulk W>C-film. • D retention is higher than He in all marked tiles, with higher retention in films compared to bulk material. The retention of hydrogen isotopes in the fusion device is critical due to safety concerns. In this work, the deuterium (D) and helium (He) retention features in the different marked tiles exposed to HL-2A tokamak discharge plasma were quantitatively characterized using long pulse laser induced desorption-quadrupole mass spectrometer (LID-QMS) combined with SEM and EDX. The D retention originates primarily from D plasma discharges of HL-2A during 2021 campaign, and the He retention comes primarily from the helium glow discharge cleaning (He-GDC). The marked tiles materials include pure bulk W, bulk stainless steel (S.S) and W-, C-, Fe-films deposited on titanium-zirconium-molybdenum alloy (TZM) or W substrates. The LID-QMS results indicate that the D and He retention distribution along the poloidal direction of HL-2A device exhibited an overall uniformity. The sequence of the D concentration trapped in the marked tiles is C-film > W-film > Fe-film/bulk S.S > bulk W, whereas the He retention is Fe-film > bulk S.S > W-film > bulk W > C-film. The D retention is higher than the He retention in all measured materials. And the D and He trapped in the film tiles are higher than those in bulk tiles. The probable reasons for the differences were discussed in combination with the changes of the surface micro-morphology and the elemental compositions of the marked tiles. This investigation would provide a reference for future in-situ application of LID-QMS to monitor the D and He retention in bulk tiles and deposited materials, and also gives the data support for fuel particle transport modelling.

Authors

Institutions

Publication Details

Journal
Nuclear Materials and Energy
Published
2025-02-13
DOI
https://doi.org/10.1016/j.nme.2025.101902
Citations
1
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
0.52
Controls
|||
ALL TIME
JAN
FEB
MAR
APR
MAY
JUN
JUL
AUG
SEP
OCT
article

Quantitative characterization of deuterium and helium retention in the marked tiles with various materials exposed to HL-2A tokamak

Huace Wu, Cong Li, Ding Wu, Chengzhi Cao et al.
1 citations
Nuclear Materials and Energy
Fusion materials and technologies
0.52
article

Quantitative characterization of deuterium and helium retention in the marked tiles with various materials exposed to HL-2A tokamak

Huace Wu, Cong Li, Ding Wu, Chengzhi Cao, Laizhong Cai, Dongye Zhao, Yi Hu, Xue Bai, Yan Lyu, Wei Qian, Chengming Wang, Hongbin Ding
article en
1 citations

Abstract

• D and He retention features in HL-2A tokamak tiles were analyzed using ex-situ LID-QMS with 2D space-resolution. • LID-QMS results indicate D and He retention in HL-2A tokamak has a uniform distribution along the poloidal direction. • D retention is C-film>W-film>Fe-film/bulk S.S>bulk W, while He retention is Fe-film>bulk S.S>W-film>bulk W>C-film. • D retention is higher than He in all marked tiles, with higher retention in films compared to bulk material. The retention of hydrogen isotopes in the fusion device is critical due to safety concerns. In this work, the deuterium (D) and helium (He) retention features in the different marked tiles exposed to HL-2A tokamak discharge plasma were quantitatively characterized using long pulse laser induced desorption-quadrupole mass spectrometer (LID-QMS) combined with SEM and EDX. The D retention originates primarily from D plasma discharges of HL-2A during 2021 campaign, and the He retention comes primarily from the helium glow discharge cleaning (He-GDC). The marked tiles materials include pure bulk W, bulk stainless steel (S.S) and W-, C-, Fe-films deposited on titanium-zirconium-molybdenum alloy (TZM) or W substrates. The LID-QMS results indicate that the D and He retention distribution along the poloidal direction of HL-2A device exhibited an overall uniformity. The sequence of the D concentration trapped in the marked tiles is C-film > W-film > Fe-film/bulk S.S > bulk W, whereas the He retention is Fe-film > bulk S.S > W-film > bulk W > C-film. The D retention is higher than the He retention in all measured materials. And the D and He trapped in the film tiles are higher than those in bulk tiles. The probable reasons for the differences were discussed in combination with the changes of the surface micro-morphology and the elemental compositions of the marked tiles. This investigation would provide a reference for future in-situ application of LID-QMS to monitor the D and He retention in bulk tiles and deposited materials, and also gives the data support for fuel particle transport modelling.

Nuclear Materials and EnergyVol. 42
Ministry of Education (ET), Southwestern Institute of Physics (CN)
Openalex Percentile: Top 42%
Fusion materials and technologies
0.52
AI Navigator

Ask Laika to Summarize, Analyze, and Connect papers live on the map.

Summarize Papers & Methodologies

Extract key findings, datasets, and comparative methods across publications.

Benchmark Rankings & Visual Analytics

Rank top research institutions, authors, funders, topics, and journals by Field-Weighted Citation Impact (FWCI) and paper volume with instant charts.

Connect Distant Disciplines

Bridge topological clusters on the map to find hidden collaborative intersections.