FTI Research
- APEX
- ARIES
- Code Development
- D-3He Fuel Cycle
- Environmental Impact
- FIRE
- FRC
- HAPL
- IEC
- ITER
- Liquid Metal Safety
- Lunar Mining
- Medical Isotopes
- RadHydro
- Shock Tube
- Space Propulsion
- X1 Chamber
MFE & IFE Studies UW Neutronics Center of Excellence Inertial Electrostatic Confinement Shock Tube
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
UWFDM-963 Neutronics and Shielding Results of the U.S. ITER Blanket Trade-Off Study; M.E. Sawan and L.A. El-Guebaly, 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]. (18 pages, 513 kB)
UWFDM-940 Shielding Analysis for ITER with Impact of Assembly Gaps and Design Inhomogeneities; L.A. El-Guebaly and M.E. Sawan, January 1994 [prepared for the 8th International Conference on Radiation Shielding, April 24-28, 1994, Arlington TX]. (11 pages, 769 kB)
UWFDM-939 Shielding Effectiveness of Candidate Structural Materials and Liquid Metal Coolants for the ITER Blanket; M.E. Sawan and L.A. El-Guebaly, January 1994 [prepared for the 8th International Conference on Radiation Shielding, April 24-28, 1994, Arlington TX]. (9 pages, 612 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)
UWFDM-923 A Complete Loss of Coolant Accident (LOCA) Analysis for the Inboard Component of ITER CDA; E.A. Mogahed, M.E. Sawan, H.Y. Khater, October 1993 [presented at 15th IEEE/NPSS Symposium on Fusion Engineering,. 11-14 October 1993, Hyannis MA]. (7 pages, 633 kB)
UWFDM-872 Shielding Considerations for ITER: Current Status and Future Directions; L.A. El-Guebaly, M.E. Sawan, December 1991 [presented at ``New Horizons in Radiation Protection and Shielding'', 26 April - 1 May 1992, Pasco WA.]. (11 pages, 781 kB)
UWFDM-868 Magnet Shielding Effectiveness of the Proposed Blankets for ITER; L.A. El-Guebaly, September 1991 [Presented at the 14th IEEE/NPSS Symposium on Fusion Engineering, 30 September - 3 October 1991, San Diego CA; published in Proc. IEEE]. (6 pages, 547 kB)
UWFDM-842 Potential for D-3He Operation in ITER; G.A. Emmert, December 1990. (19 pages, 649 kB)
UWFDM-839 Three-Dimensional Neutronics Analysis of the US Blanket Design for ITER; M.E. Sawan, Y. Gohar, H. Attaya, October 1990 [Presented at the 9th Topical Meeting on the Technology of Fusion Energy, 7-11 October 1990, Oak Brook IL; Fusion Tech. 19 (1991) 1513]. (9 pages, 610 kB) [more]
UWFDM-838 Three-Dimensional Neutronics Analysis for the US Magnet Shield of ITER; M.E. Sawan and L.A. El-Guebaly, October 1990 [Presented at the 9th Topical Meeting on the Technology of Fusion Energy, 7-11 October 1990, Oak Brook IL; Fusion Tech. 19 (1991) 1469]. (9 pages, 602 kB)
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-832 Thermal Analysis of the Blanket and Shield for the U.S. ITER Design; E.A. Mogahed and I.N. Sviatoslavsky, October 1990 [Presented at the 9th Topical Meeting on the Technology of Fusion Energy, 7-11 October 1990, Oak Brook IL (Fus. Tech. 19 (3) Pt. 2A 1546-1551)]. (9 pages, 742 kB)
UWFDM-827 Overview of the US-ITER Magnet Shield: Concept and Problems; L.A. El-Guebaly, October 1990 [Presented at the 9th Topical Meeting on the Technology of Fusion Energy, 7-11 October 1990, Oak Brook IL; Fusion Tech. 19, No. 3, Part 2B, 1475 (1991)]. (9 pages, 667 kB)
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-813 An Aqueous Lithium Salt Blanket for ITER; M.E. Sawan, I.N. Sviatoslavsky, G.L. Kulcinski, J.P. Blanchard, H.Y. Khater, E.A. Mogahed, L.J. Wittenberg, October 1989 [Presented at the 13th Symposium on Fusion Engineering, 2-6 October 1989, Knoxville TN; IEEE Cat. No. 89CH2820-9, Vol. 1, 74]. (7 pages, 607 kB)
UWFDM-811 Shielding Design Options for the TF Magnets of ITER; L.A. El-Guebaly, October 1989 [Presented at the 13th Symposium on Fusion Engineering, 2-6 October 1989, Knoxville TN; published in Proc. IEEE]. (7 pages, 523 kB)
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-777 Activation Analysis for the Aqueous Self-Cooled Blanket and Shield of ITER; H.Y. Khater, M.E. Sawan, S.W. Lomperski, I.N. Sviatoslavsky, October 1988 [presented at the 8th Topical Meeting on the Technology of Fusion Energy, 9-13 October 1988, Salt Lake City UT]. (9 pages, 876 kB)
UWFDM-775 An Aqueous Lithium Salt Self-Cooled Blanket and Shield for ITER; M.E. Sawan, I.N. Sviatoslavsky, G.L. Kulcinski, October 1988 [presented at the 8th Topical Meeting on the Technology of Fusion Energy, 9-13 October 1988, Salt Lake City UT; Fus. Tech. 15/2 (1989) 643]. (9 pages, 824 kB)
UWFDM-774 Tungsten versus Steel in Inboard Shield of ITER: Impact on Magnet Damage, Reactor Size, and Cost; Laila A. El-Guebaly, Mohamed E. Sawan, October 1988 [presented at the 8th Topical Meeting on the Technology of Fusion Energy, 9-13 October 1988, Salt Lake City UT; Fusion Tech. 15, No. 2, Part 2B, 881 (1989)]. (9 pages, 870 kB)