Researcher Portfolio

 
   

Barabash, V.

Material Research (MF), Max Planck Institute for Plasma Physics, Max Planck Society, Surface Science (OP), Max Planck Institute for Plasma Physics, Max Planck Society  

 

Researcher Profile

 
Position: Material Research (MF), Max Planck Institute for Plasma Physics, Max Planck Society
Position: Surface Science (OP), Max Planck Institute for Plasma Physics, Max Planck Society
Researcher ID: https://pure.mpg.de/cone/persons/resource/persons108614

External references

 

Publications

 
  (1 - 25 of 29)
 : Ioki, K., Akiba, M., Barabaschi, P., Barabash, V., Chiocchio, S., Daenner, W., Elio, F., Enoeda, M., Ezato, K., Federici, G., Gervash, A., Grebennikov, D., Jones, L., Kajiura, S., Krylov, V., Kuroda, T., Lorenzetto, P., Maruyama, S., Merola, M., Miki, N., Morimoto, M., Nakahira, M., Ohmori, J., Onozuka, M., Rozov, V., Sato, K., Strebkov, Y., Suzuki, S., Tanchuk, V., Tivey, R., & Utin, Y. (2004). ITER nuclear components preparing for the construction and R&D results. Journal of Nuclear Materials, 329-333, 31-38. [PubMan] : Barabash, V. (2004). Role and contribution of ITER in research of materials and reactor components. Journal of Nuclear Materials, 329-333, 156-160. [PubMan] : Barabash, V., & Snead, L. (2004). Modified formula for the assessment of the thermal response of neutron irradiated CFC. Journal of Nuclear Materials, 329-333, 860-864. [PubMan] : Bolt, H., Barabash, V., Krauss, W., Linke, J., Neu, R., Suzuki, S., Yoshida, N., & ASDEX Upgrade Team (2004). Materials for the plasma-facing components of fusion reactors. Journal of Nuclear Materials, 329-333, 66-73. Retrieved from http://dx.doi.org/10.1016/j.jnucmat.2004.04.005. [PubMan] : Peacock, A., Barabash, V., Daenner, W., Roedig, M., Lorenzetto, P., Marmy, P., Merola, M., Singh, B., Taehtinen, S., van der Laan, J., & Wu C.H. (2004). Overview of recent european materials R&D activities related to ITER. Journal of Nuclear Materials, 329-333, 173-177. [PubMan] : Ioki, K., Barabaschi, P., Barabash, V., Chiocchio, S., Dänner, W., Elio, F., Enoeda, M., Gervash, A., Ibbott, C., Jones, L., Krylov, V., Kuroda, T., Lorenzetto, P., Martin, E., Mazul, I., Merola, M., Nakahira, M., Rozov, V., Strebkov, Y., Suzuki, S., Tanchuk, V., Tivey, R., Utin, Y., & Yamada, M. (2003). Design Improvements and R&D Achievements for Vacuum Vessel and in-Vessel Components Towards ITER Construction. In 19th Conference on Fusion Energy (pp. CT-4). [PubMan] : Barabash, V., Federici, G., Linke, J., & Wu, C. (2003). Material/Plasma Surface Interaction Issues Following Neutron Damage. Journal of Nuclear Materials, 313-316, 42-51. [PubMan] : Ioki, K., Barabaschi, P., Barabash, V., Chiocchio, S., Daenner, W., Elio, F., Enoeda, M., Gervash, A., Ibbott, C., Jones, L., Krylov, V., Kuroda, T., Lorenzetto, P., Martin, E., Mazul, I., Merola, M., Nakahira, M., Rozov, V., Strebkov, Y., Suzuki, S., Tanchuk, V., Tivey, R., Utin, Y., Yamada, M., & et al. (2003). Design Improvements and R&D Achievements for Vacuum Vessel and in-Vessel Components Towards ITER Construction. Nuclear Fusion, 43, 268-273. [PubMan] : Barabash, V., Mazul, I., Latypov, R., Pokrovsky, A., & Wu, C. (2002). The Effect of Low Temperature Neutron Irradiation and Annealing on the Thermal Conductivity of Advanced Carbon-Based Materials. 10. International Conference on Fusion Reactor Materials (ICFRM-10), 307-311, 1300-1304. [PubMan] : Bolt, H., Barabash, V., Federici, G., Linke, J., Loarte, A., Roth, J., & Sato, K. (2002). Plasma facing and high heat flux materials - needs for ITER and beyond. Journal of Nuclear Materials, 307, 43-52. [PubMan] : Merola, M., Akiba, M., Barabash, V., & Mazul, I. (2002). Overview on Fabrication and Joining of Plasma Facing and High Heat Flux Materials for ITER. 10. International Conference on Fusion Reactor Materials (ICFRM-10), 307-311, 1524-1532. [PubMan] : Ioki, K., Barabash, V., Cardella, A., Elio, F., Kalinin, G., Miki, N., Onozuka, M., Osaki, T., Rozov, V., Sannazzaro, G., Utin, Y., Yamada, M., & Yoshimura, H. (2001). Design and Fabrication Methods of FW/ Blanket and Vessel for ITER-FEAT. Proceedings of the 21. Symposium on Fusion Technology (SOFT-21), 58-59, 573-578. [PubMan] : Ulrickson, M., Tivey, R., Akiba, M., Ando, T., Antipenkov, A., Araki, M., Barabash, V., Chappuis, P., Chiocchio, S., Divavin, V., Driemeyer, D., Ezato, K., Federici, G., Grattarola, M., Janeschitz, G., Kuzmin, E., Makhankov, A., Mazul, I., Merola, M., Nakamura, K., Nygren, R., Pacher, H., Ploechl, L., Riccardi, B., & et al. (1999). The ITER Divertor Cassette Project. Fusion Energy 1998, Vol. 3, 1053-1056. [PubMan] : Barabash, V., Federici, G., Matera, R., Raffray, A., & ITER-Home-Teams (1999). Armour Materials for the ITER Plasma Facing Components. 8. International Workshop on Carbon Materials, T81, 74-83. [PubMan] : Tivey, R., Ando, T., Antipenkov, A., Barabash, V., Chiocchio, S., Federici, G., Ibbott, C., Jakeman, R., Janeschitz, R., Raffray, R., Akiba, M., Mazul, I., Pcher, H., Ulrickson, E., & Vieider, G. (1999). ITER Divertor, Design Issues and Research and Development. Proceedings of the 20. Symposium on Fusion Technology (SOFT-20), 46, s. 2-4, 207-220. [PubMan] : Chiocchio, S., Tivey, R., Antipenkov, A., Barabash, V., Federici, G., Ibbott, C., Janeschitz, G., & Martin, E. (1999). The Divertor for the Reduced Technical Objective/Reduced Cost ITER. 18. IEEE/NPSS Symposium on Fusion Engineering, 103-108. [PubMan] : Janeschitz, G., Abdou, M., Ando, T., et al., Antipenkov, A., Barabash, V., Chiocchio, S., Federici, G., Ibbott, C., Jakeman, R., Matera, R., Matin, E., Pacher, H., Parker, R., & Tivey, R. (1998). Divertor Development for ITER. Proceedings of the 4. International Symposium on Fusion Nuclear Technology, Part A; s. 39-40, 173-187. [PubMan] : Barabash, V., Beaumont, B., Kalinin, G., Libeyre, P., Matera, R., De Gentile, B., ITER-Home-Teams, & et al. (1998). Joining Technologies for the Plasma Facing Components of ITER. Fusion Technology 1998, Vol. 1, 215-218. [PubMan] : Matera, R., Beaumont, B., Barabash, V., Libeyre, P., De Gentile, B., & et al. (1998). Solid, Castellated, Lamellar, and Brush-Like Armours for the High Heat Flux Components of ITER. Fusion Technology 1998, Vol. 1, 207-210. [PubMan] : Barabash, V., Federici, G., Matera, R., Pacher, H., Vieider, G., Wu, C., & et al. (1998). Carbon Fiber Composites Application in ITER Plasma Facing Components. Fusion Reactor Materials, Part A; s. 258-263, 149-159. [PubMan] : Ioki, K., Barabash, V., Cardella, A., Elio, F., Gohar, Y., Janeschitz, G., Johnson, G., Kalinin, G., Lousteau, G., Onozuka, M., Parker, R., Sannazzaro, G., & Tivey, R. (1998). Design and Material Selection for ITER First Wall/Blanket, Divertor and Vacuum Vessel. Fusion Reactor Materials, Part A; s. 258-263, 74-84. [PubMan] : Vieider, G., Abdou, M., Barabash, V., et al., Cardella, A., Ibbott, C., Jakeman, R., Merola, M., Pacher, H., & et al. (1998). Overview of the EU Small Scale Mock-up Tests for ITER High Heat Flux Components. Proceedings of the 4. International Symposium on Fusion Nuclear Technology, Part A; s. 39-40, 211-218. [PubMan] : Burtseva, T., Barabash, V., Mazul, I., Garcia-Rosales, C., Deschka, S., Behrisch, R., & Herrmann, A. (1997). Performance of the Ti Doped Graphite RG-Ti-91 at the Divertor of the Tokamak ASDEX-Upgrade. Journal of Nuclear Materials, 241-243, 716-721. doi:10.1016/S0022-3115(97)80128-6. [PubMan] : Barabash, V., Varandas, C., Dietz, J., Serra, F., Ioki, K., Janeschitz, G., Kalinin, G., Matera, R., Mohri, K., & ITER-Home-Teams (1997). Materials Aspects of ITER In-Vessel Components. Fusion Technology, Vol. 1, 347-350. [PubMan] : Raffray, A., Federici, G., Barabash, V., & et al. (1997). Beryllium Application in ITER Plasma Facing Components. Fusion Engineering and Design, 37, 261-286. [PubMan]