Abstract
Understanding the permeation behavior of tritium from a pebble bed breeding blanket is essential for establishing a self-sufficient fuel cycle in a nuclear fusion reactor. It is known that double corrosion layers forms on reduced activation ferritic-martensitic (RAFM) steel surface by gas release from a ceramic breeder material, however, its effect on hydrogen permeation behavior has not been elucidated. Herein, in-situ measurement of hydrogen permeation through an F82H RAFM wall of a ceramic breeder pebble bed was performed under H2-added sweep gas conditions. The corrosion layer formed on the F82H sample had a dense microstructure, which reduced hydrogen permeation flux at least by one order of magnitude. The permeation reduction factors were 20–50 at the water-coolant temperature of a blanket. A self-repairing ability is expected for the surface oxide layer as the corrosion occurs spontaneously inside a breeding blanket.
Original language | English |
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Pages (from-to) | 6154-6163 |
Number of pages | 10 |
Journal | International Journal of Hydrogen Energy |
Volume | 47 |
Issue number | 9 |
Early online date | 18 Dec 2021 |
DOIs | |
Publication status | Published - 29 Jan 2022 |
Bibliographical note
Funding Information:This work was financially supported by a Grant-in-Aid for Scientific Research B ( 19H01873 ) and a Grant-in-Aid for young scientists ( 20K14442 ) from Japan Society for the Promotion of Science . H. Tanigawa, T. Nozawa, M. Nakamichi, T. Hoshino, and J.H. Kim from National Institutes for Quantum Science and Technology (QST) are thanked for supplying F82H and LTZO pebbles.
Funding Information:
This work was financially supported by a Grant-in-Aid for Scientific Research B (19H01873) and a Grant-in-Aid for young scientists (20K14442) from Japan Society for the Promotion of Science. H. Tanigawa, T. Nozawa, M. Nakamichi, T. Hoshino, and J.H. Kim from National Institutes for Quantum Science and Technology (QST) are thanked for supplying F82H and LTZO pebbles.
Publisher Copyright:
© 2021 Hydrogen Energy Publications LLC
Keywords
- Tritium permeation
- Chemical compatibility
- Nuclear fusion
- Breeding blanket
- Reduced activation ferritic martensitic steel