ITER

ITER is a joint international research and development project that aims to demonstrate the scientific and technical feasibility of fusion power. The partners in the project - the ITER Parties - are the European Union (represented by EURATOM), Japan, the People's Republic of China, India, the Republic of Korea, the Russian Federation and the U.S. ITER will be constructed in Europe, at Cadarache in the South of France.
UW-FTI personnel have been involved in the ITER project since its inception in the late 1980s. Our numerous publications reflect our active involvement as we led the U.S. shielding activity for ITER. With the U.S. rejoining ITER, we resumed our leading role in the nuclear area, offering a novel approach for the 3-D modeling of ITER and its subsystems using the CAD/MCNPX interface.

FTI Publications

Results: 81 to 100 of 100 order by: UWFDM AuthorTitle Date
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retrieve PDF Source Profile Analysis for the ITER First Wall/Shield Module 13; B. Smith, P.P.H. Wilson, M. Sawan, T. Bohm, September 2008 [presented at the 18th ANS Topical Meeting on Fusion Energy, 28 September-2 October 2008, San Francisco CA]. (1 page, 14 MB)

UWFDM-1349   Source Profile Analysis for the ITER First Wall/Shield Module 13; B. Smith, P. Wilson, M. Sawan and T. Bohm, September 2008 [presented at the 18th ANS Topical Meeting on Fusion Energy, 28 September-2 October 2008, San Francisco CA]. (7 pages, 1.7 MB)

retrieve PDF Sealing Faceted Surfaces to Achieve Watertight CAD Models; B.M. Smith, T.J. Tautges, P.P.H. Wilson, October 2010 [Proceedings of the 19th International Meshing Roundtable, 3-6 October 2010, Chattanooga TN]. (32 pages, 2.5 MB) [more]

UWFDM-1389   Sealing Faceted Surfaces to Achieve Watertight CAD Models; B.M. Smith, T.J. Tautges, P.P.H. Wilson, October 2010 [Proceedings of the 19th International Meshing Roundtable, October 3-6, 2010, Chattanooga TN]. (20 pages, 1.2 MB) [more]

UWFDM-1391   Robust Tracking and Advanced Geometry for Monte Carlo Radiation Transport; Brandon M. Smith, March 2011 [Ph.D. thesis]. (147 pages, 6.2 MB)

retrieve PDF Quantifying the Advantages of Counter Flow Helium First Wall Cooling: A Thermal-Hydraulic Comparison of ITER TBM First Wall Cooling Designs; G. Sviatoslavsky, M. Dagher, P. Calderoni, C.P.C. Wong, September 2005 [presented at the 21st IEEE/NPSS Symposium on Fusion Engineering (SOFE), 26-29 September 2005, Knoxville TN]. (1 page, 880 kB) [more]

UWFDM-824   U.S. Aqueous Salt Blanket for ITER; I.N. Sviatoslavsky, M.E. Sawan, L.J. Wittenberg, G.L. Kulcinski, J.P. Blanchard, E.A. Mogahed, February 1990 [published in Fusion Engineering and Design 13 (1990) 33-4]. (28 pages, 4.2 MB)

UWFDM-836   Mechanical Design and Fabrication of the U.S. Solid Breeder Blanket for ITER; I.N. Sviatoslavsky, J.P. Blanchard, Y. Gohar, S. Majumdar, October 1990 [Presented at the 9th Topical Meeting on the Technology of Fusion Energy, 7-11 October 1990, Oak Brook IL]. (9 pages, 852 kB) [more]

UWFDM-936   U.S. Aqueous Salt Blanket for ITER; I.N. Sviatoslavsky, M. Sawan, G.L. Kulcinski, J. Blanchard, L. El-Guebaly, L. Wittenberg, February 1989 [Presented at the U.S./Canada Workshop on Lithium Salt Blankets, Toronto, Canada, 7-9 February 1989]. (32 pages, 1.6 MB)

UWFDM-969   Pulsed Activation Analyses of the ITER Blanket Design Options Considered in the Blanket Trade-Off Study; Q. Wang and D.L. Henderson, June 1994 [presented at the 3rd International Symposium on Fusion Nuclear Technology, June 26 - July 1, 1994, Los Angeles CA; to be published in Fusion Engineering and Design]. (22 pages, 710 kB)

UWFDM-977   Summary Report for ITER Design Task D10: Updating the Activation Code RACC for ITER Design Analysis; Qingming Wang and D.L. Henderson, January 1995 (revised April 1995). (29 pages, 737 kB)

UWFDM-930   MHD, Heat Transfer and Stress Analysis for the ITER Self-Cooled Blanket Design; X.R. Wang, E.A. Mogahed, I.N. Sviatoslavsky, October 1993. (29 pages, 1.5 MB)

retrieve PDF Innovations in 3-Dimensional Neutronics Analysis for Fusion Systems; P. Wilson, T. Tautges, M. Sawan, L. El-Guebaly, D. Henderson, G. Sviatoslavsky, B. Kiedrowski, A. Ibrahim, B. Smith, R. Slaybaugh, November 2006 [presented at the 17th ANS Topical Meeting on Fusion Energy, 13-15 November 2006, Albuquerque NM]. (27 pages, 4.2 MB) [more]

retrieve PDF Nuclear Heating In Critical Components Of Alternative ITER First Wall Attachment Mechanism; P.P.H. Wilson, M.E. Sawan, E.P. Marriott, M.A. Ulrickson, May 2009 [presented at the 23rd Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego CA]. (1 page, 580 kB) [more]

UWFDM-1367   Nuclear Heating in Critical Components of Alternative ITER First Wall Attachment Mechanism; P.P.H. Wilson, M.E. Sawan, E.P. Marriott, M.A. Ulrickson, May 2009 [prepared for the 23rd Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego CA]. (5 pages, 422 kB) [more]

retrieve PDF Acceleration Techniques for the Direct Use of CAD-Based Geometry in Fusion Neutronics Analysis; P.P.H. Wilson, T.J. Tautges, J.A. Kraftcheck, B.M. Smith, D.L. Henderson, October 2009 [presented at the 9th International Symposium on Fusion Nuclear Technology (ISFNT-9), 11-16 October 2009, Dalian, China]. (29 pages, 1.4 MB) [more]

UWFDM-1248   On the Strategy and Requirements for Neutronics Testing in ITER; M.Z. Youssef and M.E. Sawan, September 2004 [Proceedings 16th ANS Topical Meeting on Fusion Energy, Fusion Science and Technology 47 (4), May 2005, pp. 1038-1045]. (11 pages, 947 kB) [more]

UWFDM-1279   Assessment of the Activation, Decay Heat, and Waste Disposal of a Dual Coolant Lithium Lead Test Blanket Module for ITER; M.Z. Youssef and M.E. Sawan, September 2005 [presented at the 21st IEEE/NPSS Symposium on Fusion Engineering (SOFE), 26-29 September 2005, Knoxville TN]. (8 pages, 1.2 MB) [more]

retrieve PDF Assessment of the Activation, Decay Heat, and Waste Disposal of a Dual Coolant Lithium Lead Test Blanket Module for ITER; M.Z. Youssef and M.E. Sawan, September 2005 [presented at the 21st IEEE/NPSS Symposium on Fusion Engineering (SOFE), 26-29 September 2005, Knoxville TN]. (1 page, 821 kB) [more]

UWFDM-1356   Nuclear Analyses for Two "Look-Alike" Helium-Cooled Pebble Bed Test Blanket Sub-Modules Proposed by the US for Testing in ITER; M.Z. Youssef, M.E. Sawan and A. Ying, February 2006 [published in Fusion Engineering and Design, 81 (2006) 1567-1576]. [more]


Results: 81 to 100 of 100 order by: UWFDM AuthorTitle Date
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