Deuterium retention in reduced activation ferritic martensitic steels exposed 
to D plasmas and irradiated with D ions

Alimov, V. Kh.; Hatano, Y.; Roth, J.; Sugiyama, K.; Oyaidzu, M.; Baldwin, M.; Doerner, R.; 't Hoen, M. H. J.; Lee, H. T.; Ueda, Y.; Matsuyama, M.; Hayashi, T.

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Deuterium retention in reduced activation ferritic martensitic steels exposed to D plasmas and irradiated with D ions

Alimov, V. K., Hatano, Y., Roth, J., Sugiyama, K., Oyaidzu, M., Baldwin, M., et al. (2014). Deuterium retention in reduced activation ferritic martensitic steels exposed to D plasmas and irradiated with D ions. Talk presented at 12th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-12). Toyama. 2014-06-02 - 2014-06-04.

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Item Permalink: https://hdl.handle.net/11858/00-001M-0000-0019-D696-7 Version Permalink: https://hdl.handle.net/11858/00-001M-0000-0019-D697-5

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Creators:
Alimov, V. Kh.¹, Author
Hatano, Y.¹, Author
Roth, J.², Author
Sugiyama, K.², Author
Oyaidzu, M.¹, Author
Baldwin, M.¹, Author
Doerner, R.¹, Author
't Hoen, M. H. J.¹, Author
Lee, H. T.¹, Author
Ueda, Y.¹, Author
Matsuyama, M.¹, Author
Hayashi, T.¹, Author

Affiliations:
1External Organizations, ou_persistent22
2Plasma Edge and Wall (E2M), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856327

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Language(s): eng - English

Dates: Submitted: 2014

Publication Status: Submitted

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Title: 12th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-12)

Place of Event: Toyama

Start-/End Date: 2014-06-02 - 2014-06-04

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