Ablation of Fusion Materials Exposed to High Heat Flux in an Electrothermal Plasma Discharge as a Simulation for Hard Disruption
Tóm tắt
Từ khóa
Tài liệu tham khảo
V. Barabash, G. Fediritci, R. Matera, A.R. Raffray, The ITER Home Teams, Armour materials for the ITER plasma facing components. Physica Scripta T81, 74–83 (1999)
G.E. Dale, M.A. Bourham, Melt-layer erosion and resolidification of metallic plasma-facing components. In Proceedings of 17th IEEE NPSS Symp. Fusion Eng., San Diego, CA, 2, 892–895 (1997)
A. Hassanein, I. Konkashbaev, Theory and models of material erosion and lifetime during plasma instabilities in a tokamak environment. Fusion Eng. Design 51–52, 681–694 (2000)
A. Hassanein, Prediction of material erosion and lifetime during major plasma instabilities in tokamak devices. Fusion Eng. Design 60, 527–546 (2002)
J.P. Sharpe, M.A. Bourham, J.G. Gilligan, Generation and characterization of carbon particulate in disruption simulation. Fusion Technol. 34, 634–639 (1998)
J.M. Linke, T. Hirai, M. Rödig, L.A. Singheiser, Performance of plasma-facing materials under intense thermal loads in tokamaks and stellarators. Fusion Sci. Technol. 46, 142–151 (2006)
N. Sauthoff, F. Perkins, J. Wesley, T. Amano, D. Boucher, S. Cohen, N. Fujisaw, G. Janeschitz, V. Mukhovatov, W. Nevins, S. Ortolani, D. Post, S. Putvinski, M. Rosenbluth, N. Uckan and K. Young, Physics requirements for ITER engineering systems. In Proceedings of 16th IEEE NPSS Symp. Fusion Eng., Urbana Champaign, IL, 1, 130–137 (1995)
J. Gilligan, M. Bourham, The use of an electrothermal plasma gun to simulate the extremely high heat flux conditions of a tokamak disruption. J. Fusion Energ. 12, 311–316 (1993)
G.E. Dale, M.A. Bourham, Experimental investigation into melt-layer erosion of plasma-facing materials. Fusion Technol. 34, 901–907 (1998)
L. Winfrey, J. Gilligan, A. Saveliev, M. Abd Al-Halim, M. Bourham, A study of plasma parameters in a capillary discharge with calculations using ideal and non-ideal plasma models for comparison with experiment. IEEE Trans. Plasma Science 40, 843–852 (2012)
K. Sugiyama, K. Miyasaka, T. Tanabe, M. Glugla, N. Bekris, P. Coad, Tritium distribution on the surface of plasma facing carbon tiles used in JET. J. Nucl. Mater. 313–316, 507–513 (2003)
A.R. Raffray, M. Akiba, V. Chuyanov, L. Giancarli, S. Malang, Breeding blanket concepts for fusion and materials requirements. J. Nucl. Mater. 307–311, 21–30 (2002)
M. Rubel, J.P. Coad, N. Bekris, S.K. Erents, D. Hole, G.F. Matthews, R. Penzhorn, Beryllium and carbon films in JET following D-T operation. J. Nucl. Mater. 313–316, 321–326 (2003)
J.N. Brooks, J.P. Allain, D.G. Whyte. R. Ochoukov, and B. Lipschultz, Analysis of C-MOD molybdenum divertor erosion and code/data comparison. Plasma Science Fusion center, MIT, PSFC/JA-11-17, (2011)
K.O. Hintermann, R. Wideroe, Tritium production and cycling in a fusion reactor with lithium blanket. In Proceedings of IAEA, Switzerland, P/1471, paper 56, 32, 440–445 (1958)
Y. Hirooka, M. Bourham, J. Brooks, R. Causey, G. Chevalier, R. Conn, W. Eddy, J. Gilligan, M. Khandagle, Y. Ra, Evaluation of tungsten as a plasma-facing material for steady state magnetic fusion devices. J. Nucl.r Mater. 196-198, 149–158 (1992)
R. Neu, R. Dux, A. Geiger, O. Gruber, A. Kallenbach, K. Krieger, H. Maier, R. Pugno, V. Rohde, S. Schweizer, The ASDEX Upgrade Team, Tungsten as plasma-facing material in ASDEX Upgrade. Fusion Eng. and Design 65(3), 367–374 (2003)
A.L. Winfrey, M. Abd Al-Halim, A.V. Saveliev, J.G. Gilligan, M.A. Bourham, Enhanced performance of electrothermal plasma sources as fusion pellet injection drivers and space based mini-thrusters via extension of a flattop discharge current. J. Fusion Energ. 32(3), 371–377 (2013)
J. P. Sharpe, M. A. Bourham, J. G. Gilligan, Experimental investigation of disruption-induced aerosol mobilization in accident scenarios of ITER. In Proceedings of 17th IEEE NPSS Symp. Fusion Eng., San Diego, CA, 1, 153–156 (1997)