Home News About Us Contact Contributors Disclaimer Privacy Policy Help FAQ

Quick Search
My eDoc
Session History
Support Wiki
Direct access to
document ID:

          Display Documents

Print in Citation style Print version     Display:
Sort by: Display records with Fulltext only
Entries: 1-6  
Deuterium retention in tungsten exposed to low-energy, high-flux clean and carbon-seeded deuterium plasmas
Authors: Alimov, V. Kh.; Roth, J.; Causey, R. A.; Komarov, D. A.; Linsmeier, C.; Wiltner, A.; Kost, F.; Lindig, S.
Date of Publication (YYYY-MM-DD): 2008
Title of Journal: Journal of Nuclear Materials
Volume: 375
Issue / Number: 2
Start Page: 192
End Page: 201
Document Type: Article
ID: 362279.0
Full text / Content available
Tritium inventory in ITER plasma-facing materials and tritium removal procedures
Authors: Roth, J.; Tsitrone, E.; Loarer, T.; Philipps, V.; Brezinsek, S.; Loarte, A.; Counsell, G. F.; Doerner, R. P.; Schmid, K.; Ogorodnikova, O. V.; Causey, R. A.
Date of Publication (YYYY-MM-DD): 2008
Title of Journal: Plasma Physics and Controlled Fusion
Volume: 50
Issue / Number: 10
Sequence Number of Article: 103001 (20pp)
Document Type: Article
ID: 366536.0
Full text / Content available
Recent Advances on Hydrogen Retention in ITER's Plasma Facing Materials: Beryllium, Carbon, and Tungsten
Authors: Skinner, C. H.; Haasz, A. A.; Alimov, V. Kh.; Bekris, N.; Causey, R. A.; Clark, R. E. H.; Coad, J. P.; Davis, J. W.; Doerner, R. P.; Mayer, M.; Pisarev, A.; Roth, J.; Tanabe, T.
Date of Publication (YYYY-MM-DD): 2008
Title of Journal: Fusion Science and Technology
Volume: 54
Issue / Number: 4
Start Page: 891
End Page: 945
Document Type: Article
ID: 391258.0
Full text / Content available
Be–W alloy formation in static and divertor-plasma simulator experiments
Authors: Baldwin, M. J.; Doerner, R. P.; Nishijima, D.; Buchenauer, D.; Clift, W. M.; Causey, R. A.; Schmid, K.
Date of Publication (YYYY-MM-DD): 2007
Title of Journal: Journal of Nuclear Materials
Volume: 363-365
Start Page: 1179
End Page: 1183
Document Type: Article
ID: 320086.0
High thermal conductivity of graphite fiber silicon carbide composites for fusion reactor application
Authors: Snead, L. L.; Balden, M.; Causey, R. A.; Atsumi, H.
Date of Publication (YYYY-MM-DD): 2002
Title of Journal: Journal of Nuclear Materials
Volume: 307-311
Start Page: 1200
End Page: 1204
Document Type: Article
ID: 21342.0
In-vessel tritium retention and removal in ITER
Authors: Federici, G.; Anderl, R. A.; Andrew, P.; Brooks, J. N.; Causey, R. A.; Coad, J. P.; Cowgill, D.; Doerner, R. P.; Haasz, A. A.; Janeschitz, G.; Jacob, W.; Longhurst, G. R.; Nygren, R.; Peacock, A.; Pick, M. A.; Philipps, V.; Roth, J.; Skinner, C. H.; Wampler, W. R.
Date of Publication (YYYY-MM-DD): 1999
Title of Journal: Journal of Nuclear Materials
Volume: 266
Start Page: 14
End Page: 29
Document Type: Article
ID: 625737.0
Entries: 1-6  
The scope and number of records on eDoc is subject to the collection policies defined by each institute - see "info" button in the collection browse view.