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

Tillack, 1997, High performance PbLi blanket, 1000 Sze, 2000, Blanket system selection for ARIES ST, Fusion Eng. Des., 48, 371, 10.1016/S0920-3796(00)00146-0 Norajitra, 2002, The EU advanced dual coolant blanket concept, Fusion Eng. Des., 61–62, 449, 10.1016/S0920-3796(02)00107-2 Wong, 2004, Assessment of liquid breeder first wall and blanket options for the advanced reactor design Morley, 2004, Thermofluid magnetohydrodynamic issues for liquid breeders Malang, 1998, Combination of a self-cooled liquid metal breeder blanket with a gas turbine power conversion system, Fusion Eng. Des., 41, 561, 10.1016/S0920-3796(98)00220-8 Sagara, 2000, Design and development of the Flibe blanket for helical-type fusion reactor FFHR, Fusion Eng. Des., 49–50, 661, 10.1016/S0920-3796(00)00360-4 Peterson, 2003, Multiple-reheat Brayton cycles for nuclear power conversion with molten coolants, Nucl. Technol., 144, 279, 10.13182/NT144-279 Zhao, 2004, Optimized helium-Brayton power conversion for fusion energy systems Smolentsev, 2005, Numerical analysis of MHD flow, heat transfer and tritium transport in a poloidal channel of the DCLL blanket with a SiCf/SiC flow channel insert Smolentsev, 2005, Code development for analysis of MHD pressure drop reduction in a liquid metal blanket using insulation technique based on a fully developed flow model, Fusion Eng. Des., 73, 83, 10.1016/j.fusengdes.2005.01.003 G.R. Longhurst, D.F. Holland, J.L. Jones, B.J. Merrill, TMAP4: tritium migration analysis program user's manual, Idaho National Engineering Laboratory Report, EGG-EP-1035, June (1992).