Overview on fabrication and joining of plasma facing and high heat flux materials for ITER
作者： M. Merola , M. Akiba , V. Barabash , I. Mazul
DOI: 10.1016/S0022-3115(02)01070-X
关键词:
摘要: This paper presents the results of R&D program on development joining technologies, including non-destructive inspection, for high heat flux components carried out by three ITER Participating Teams. Reliability requirements and design criteria are also discussed. The large amount performed within project has resulted in suitable which meet or even exceed form a solid basis possible future construction machine. However, further developments still needed consolidation positive with improving reliability joints reducing manufacturing cost.
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M. Araki, Y. Kude, Y. Sohda, K. Nakamura, K. Sato, S. Suzuki, M. Akiba, Development of 3D-based CFC with high thermal conductivity for fusion application symposium on fusion technology. pp. 359- 362 ,(1997) , 10.1016/B978-0-444-82762-3.50060-4
T. Huber, L. Plochl, N. Reheis, J.P. Cocat, J. Schlosser, The manufacturing and testing of the toroidal pumped limiter prototype elements for Tore Supra international symposium on fusion engineering. ,vol. 1, pp. 716- 719 ,(1995) , 10.1109/FUSION.1995.534324
V. Barabash, G. Federici, R. Matera, A. R. Raffray, ITER Home Teams, Armour Materials for the ITER Plasma Facing Components Physica Scripta. ,vol. 81, pp. 74- 83 ,(1999) , 10.1238/PHYSICA.TOPICAL.081A00074
R.G Castro, K.E Elliot, R.D Watson, D.L Youchison, K.T Slattery, Fabrication and high heat flux testing of plasma sprayed beryllium ITER first wall mock-ups Journal of Nuclear Materials. ,vol. 258, pp. 252- 257 ,(1998) , 10.1016/S0022-3115(98)00078-6
M. Akiba, S. Suzuki, Overview of the Japanese mock-up tests for ITER high heat flux components Fusion Engineering and Design. ,vol. 39, pp. 219- 225 ,(1998) , 10.1016/S0920-3796(98)00107-0
C.H Wu, C Alessandrini, P Bonal, H Grote, R Moormann, M Rödig, J Roth, H Werle, G Vieider, Overview of EU CFCs development for plasma facing materials Journal of Nuclear Materials. ,vol. 258, pp. 833- 838 ,(1998) , 10.1016/S0022-3115(98)00384-5
A. Cardella, A. Lodato, H.D. Pacher, R.R. Parker, K. Ioki, G. Janeschitz, D. Lousteau, R. Raffray, M. Yamada, C. Gusic, The ITER port limiter design Fusion Engineering and Design. ,vol. 43, pp. 75- 92 ,(1998) , 10.1016/S0920-3796(98)00258-0
R. Tivey, M. Akiba, D. Driemeyer, I. Mazul, M. Merola, M. Ulrickson, ITER R&D: Vacuum vessel and in-vessel components: Divertor cassette Fusion Engineering and Design. ,vol. 55, pp. 219- 229 ,(2001) , 10.1016/S0920-3796(01)00212-5
M Rödig, E Ishitsuka, A Gervash, H Kawamura, J Linke, N Litunovski, M Merola, High heat flux performance of neutron irradiated plasma facing components Journal of Nuclear Materials. ,vol. 307-311, pp. 53- 59 ,(2002) , 10.1016/S0022-3115(02)01030-9
M Merola, L Plöchl, Ph Chappuis, F Escourbiac, M Grattarola, I Smid, R Tivey, G Vieider, Manufacturing and testing of a prototypical divertor vertical target for ITER Journal of Nuclear Materials. ,vol. 283, pp. 1068- 1072 ,(2000) , 10.1016/S0022-3115(00)00150-1