Tritium retention characteristics of the dust in LHD after the deuterium plasma experiment
Tritium (T) retention of the dust particles collected at ten toroidal sections of the Large Helical Device (LHD) after the 21st experimental campaign, in which deuterium (DD) plasma experiments were conducted, were evaluated by an enhanced full combustion method (EFCM), and their individual T retent...
Saved in:
| Main Authors: | Teppei Otsuka, Yuya Ando, Miyuki Yajima, Gen Motojima, Suguru Masuzaki |
|---|---|
| Format: | Article |
| Language: | English |
| Published: |
Elsevier
2025-06-01
|
| Series: | Nuclear Materials and Energy |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S2352179125000705 |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
Similar Items
-
Deuterium tritium fusion experiment device radiation shielding analysis and optimization
by: Zhao Shengqiang, et al.
Published: (2025-05-01) -
Helium plasma-induced surface modifications of unirradiated and pre-ion irradiated tungsten at LHD divertor leg position
by: Mingzhong Zhao, et al.
Published: (2025-01-01) -
Deuterium and tritium density determination at JET using neutron diagnostics
by: B. Vingren, et al.
Published: (2025-01-01) -
Non-linear dependence of ion heat flux on plasma density at the L–H transition of JET NBI-heated deuterium–tritium plasmas
by: P. Vincenzi, et al.
Published: (2024-01-01) -
Feasibility of main thermal ion heating by ICRF waves using a top launcher in a tokamak with deuterium–tritium plasmas
by: Jungpyo Lee, et al.
Published: (2025-01-01)