An overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design

Fusion Engineering and Design - Tập 81 - Trang 461-467 - 2006
C.P.C. Wong1, S. Malang2, M. Sawan3, M. Dagher4, S. Smolentsev4, B. Merrill5, M. Youssef6, S. Reyes7, D.K. Sze8, N.B. Morley4, S. Sharafat4, P. Calderoni4, G. Sviatoslavsky3, R. Kurtz9, P. Fogarty10, S. Zinkle10, M. Abdou4
1General Atomics, P.O. Box 85608, San Diego, CA 92186-5608 USA
2Fusion Nuclear Technology Consulting, Linkenheim, Germany
3University of Wisconsin, Madison, WI, USA
4University of California, Los Angeles, CA USA
5INEEL, Idaho Falls, ID, USA
6University of California, Los Angeles, CA, USA
7Lawrence Livermore National Laboratory, Livermore, CA, USA
8University of California San Diego, CA, USA
9Pacific Northwest Laboratory, Richland, WA, USA
10Oak Ridge National Laboratory, Oak Ridge, TN, USA

Tài liệu tham khảo

Thông tin
Thông tin xuất bản

Fusion Engineering and Design

Tập 81

461-467

Thông tin tác giả