Tritium retention in tungsten exposed to intense fluxes of 100 eV tritons
Causey, R, Wilson, K, Venhaus, T, R. Wampler, W
Published in Journal of nuclear materials (01.03.1999)
Published in Journal of nuclear materials (01.03.1999)
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Journal Article
The effect of surface state on the kinetics of cerium-hydride formation
Bach, H.T., Venhaus, T.J., Paglieri, S.N., Oona, H., Allen, T.H., Schwarz, R.B., Wermer, J.R.
Published in Journal of alloys and compounds (31.10.2007)
Published in Journal of alloys and compounds (31.10.2007)
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Journal Article
Hydrogen release from 800 MeV proton-irradiated tungsten
Oliver, B.M., Venhaus, T.J., Causey, R.A., Garner, F.A., Maloy, S.A.
Published in Journal of nuclear materials (01.12.2002)
Published in Journal of nuclear materials (01.12.2002)
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Journal Article
Hydrogen recycling study by Balmer lines emissions in linear plasma machine TPE
Shimada, K., Tanabe, T., Causey, R., Venhaus, T., Okuno, K.
Published in Journal of nuclear materials (01.03.2001)
Published in Journal of nuclear materials (01.03.2001)
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Journal Article
Hydrogen release from 800 MeV proton-irradiated tungsten rods
Oliver, B M, Garner, F A, Hamilton, M L, Venhaus, T J, Causey, R A, Maloy, S A
Published in Physica scripta (01.01.2001)
Published in Physica scripta (01.01.2001)
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Journal Article
Tritium permeation experiment using a tungsten armored divertor-simulating module
Nakamura, H, O’hira, S, Shu, W, Nishi, M, Venhaus, T.J, Causey, R.A, Hyatt, D.R, Willms, R.S
Published in Journal of nuclear materials (01.12.2000)
Published in Journal of nuclear materials (01.12.2000)
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Journal Article
Analysis of Thermal Desorption Spectra to Understand the Migration of Hydrogen in Tungsten
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Journal Article
Conference Proceeding
Tritium retention behavior in tungsten exposed to off-normal plasma condition
Nakamura, H., O'hira, S., Nishi, M., Venhaus, T., Causey, R., Hyatt, D., Willms, S.
Published in 18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050) (1999)
Published in 18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050) (1999)
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Conference Proceeding
Tritium retention behavior in tungsten exposed to off-normal plasma condition
Nakamura, H., O'hira, S., Nishi, M., Venhaus, T., Causey, R., Hyatt, D., Willms, S.
Published in 18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050) (1999)
Published in 18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050) (1999)
Get full text
Conference Proceeding
Measurement of the{sup 3}He permeability of DT-filled fused silica inertial confinement fusion (ICF) targets to study the effects of{sup 3}He on neutron emission during implosion
Wermer, J. R., Murdock, H. M., Nobile Jr, A., Herrmann, H. W., Venhaus, T. J., Paglieri, S. N., Langenbrunner, J. R., Mack, J. M.
Published in Fusion science and technology (15.07.2008)
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Published in Fusion science and technology (15.07.2008)
Journal Article
Tritium retention in tungsten exposed to intense fluxes of 100eV tritons
Causey, R, Wilson, K, Venhaus, T, Wampler, W R
Published in Journal of nuclear materials (18.03.1999)
Get full text
Published in Journal of nuclear materials (18.03.1999)
Journal Article
The effect of surface state on the kinetics of cerium-hydride formation
BACH, H. T, VENHAUS, T. J, PAGLIERI, S. N, OONA, H, ALLEN, T. H, SCHWARZ, R. B, WERMER, J. R
Published in Journal of alloys and compounds (2007)
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Published in Journal of alloys and compounds (2007)
Conference Proceeding