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

Fusion Engineering and Design

Volumn 81 A, Issue 1-4, 2006, Pages 461-467

  Wong, C P C ^a   Malang, S ^b   Sawan, M ^c   Dagher, M ^d   Smolentsev, S ^d   Merrill, B ^e   Youssef, M ^d   Reyes, S ^f   Sze, D K ^g   Morley, N B ^d   Sharafat, S ^d   Calderoni, P ^d   Sviatoslavsky, G ^c   Kurtz, R ^h   Fogarty, P ⁱ   Zinkle, S ⁱ   Abdou, M ^d  

^a GENERAL ATOMICS   (United States)

^b Fusion Nuclear Technology Consulting   (Germany)

^c UNIVERSITY OF WISCONSIN MADISON   (United States)

^d UNIVERSITY OF CALIFORNIA   (United States)

^e IDAHO NATIONAL LABORATORY   (United States)

^f LAWRENCE LIVERMORE NATIONAL LABORATORY   (United States)

^g UNIVERSITY OF CALIFORNIA   (United States)

^h PACIFIC NORTHWEST NATIONAL LABORATORY   (United States)

ⁱ OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

Blanket; Dual coolant; Helium cooled; ITER TBM; Pb 17Li breeder

Indexed keywords

BREEDER REACTORS; FUSION REACTIONS; HELIUM; LEAD; MAGNETOHYDRODYNAMICS; POWER CONVERTERS; THERMAL INSULATION; TRITIUM;

BLANKETS; DUAL-COOLANT; HELIUM-COOLED; ITER-TBM; PB-17LI BREEDER; REDUCED ACTIVATION FERRITIC STEEL (RAFS);

EXPERIMENTAL REACTORS;

EID: 31744433642     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2005.05.012     Document Type: Conference Paper

References (12)

1. M.S. Tillack, and S. Malang High performance PbLi blanket Proceedings of the 17th IEEE/NPSS Symposium on Fusion Energy San Diego, California 1997 1000 1004
2. D.K. Sze, M. Tillack, and L. El-Guebaly Blanket system selection for ARIES ST Fusion Eng. Des. 48 2000 371 378
3. P. Norajitra, L. Bühler, U. Fischer, S. Malang, G. Reimann, and H. Schnauder The EU advanced dual coolant blanket concept Fusion Eng. Des. 61-62 2002 449 453
4. C.P.C. Wong, S. Malang, M. Sawan, S. Smolentsev, S. Majumdar, B. Merrill, D.K. Sze, N. Morley, S. Sharafat, M. Dagher, P. Peterson, H. Zhao, S.J. Zinkle, M. Abdou, and M. Youssef Assessment of liquid breeder first wall and blanket options for the advanced reactor design Proceedings of 16th ANS Topical Meeting on the Technology of Fusion Energy Madison, Wisconsin 2004
5. N.B. Morley, S. Malang, and I. Kirillov Thermofluid magnetohydrodynamic issues for liquid breeders Proceedings of 16th ANS Topical Meeting on the Technology of Fusion Energy Madison, Wisconsin 2004
6. S. Malang, H. Schnauder, and M.S. Tillack Combination of a self-cooled liquid metal breeder blanket with a gas turbine power conversion system Fusion Eng. Des. 41 1998 561 567
7. A. Sagara, H. Yamanishi, S. Imagawa, T. Muroga, T. Uda, T. Noda, S. Takahashi, K. Fukumoto, T. Yamamoto, and H. Matsui Design and development of the Flibe blanket for helical-type fusion reactor FFHR Fusion Eng. Des. 49-50 2000 661 666
8. P.F. Peterson Multiple-reheat Brayton cycles for nuclear power conversion with molten coolants Nucl. Technol. 144 2003 279 288
9. H. Zhao, G. Fukuda, R.P. Abbott, and P.F. Peterson Optimized helium-Brayton power conversion for fusion energy systems Proceedings of 16th ANS Topical Meeting on the Technology of Fusion Energy Madison, Wisconsin 2004
10. f/SiC flow channel insert Proceedings of the 7th International Symposium on Fusion Nuclear Technology Tokyo, Japan 2005
11. S. Smolentsev, N. Morley, and M. Abdou 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 1 2005 83 93
12. 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).