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
Updated DCLL TBM Neutronics Analysis; Mohamed Sawan, August 2008 [presented at the Fusion Nuclear Science and Technology (FNST) meeting, 12-14 August 2008, UCLA, Los Angeles CA]. (32 pages, 5.7 MB)
UWFDM-1257 US Plans and Strategy for ITER Blanket Testing; M. Abdou, D. Sze, C. Wong, M. Sawan, A. Ying, N. Morley, September 2004 [Proceedings 16th ANS Topical Meeting on Fusion Energy, Fusion Science and Technology 47 (3), April 2005, pp. 475-487]. (16 pages, 2.1 MB) [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-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-1393 Two-Dimensional Nuclear Analysis in Support of ITER Blanket Module Design; M.E. Sawan, May 2011. (13 pages, 1.4 MB)
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)
Three-Dimensional Nuclear Analysis for the US Dual Coolant Lithium Lead ITER Test Blanket Module; M. Sawan, B. Smith, E. Marriott, P. Wilson, October 2009 [presented at the 9th International Symposium on Fusion Nuclear Technology (ISFNT-9), 11-16 October 2009, Dalian, China]. (19 pages, 1.8 MB)
UWFDM-1380 Three-Dimensional Nuclear Analysis for the US Dual Coolant Lithium Lead ITER Test Blanket Module; M.E. Sawan, B. Smith, E.P. Marriott, P.P.H. Wilson, December 2010 [published in Fusion Engineering and Design, 85 (2010) 1027-1032]. (15 pages, 2.5 MB)
UWFDM-1397 Three-Dimensional Nuclear Analysis for the US Dual Coolant Lead Lithium ITER Test Blanket Module; M.E. Sawan, B. Smith, E.P. Marriott, P.P.H. Wilson, December 2010 [published in Fusion Engineering and Design 85 (2010) 1027-1032].
UWFDM-1030 Three-Dimensional Neutronics and Shielding Analyses for the ITER Divertor; M.E. Sawan, L. Petrizzi, R.T. Santoro, D. Valenza, June 1996 [Presented at the 12th Topical Meeting on the Technology of Fusion Power, 16-20 June 1996, Reno NV]. (7 pages, 588 kB) [more]
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-1077 Three-Dimensional Neutronics Analysis for the ITER Divertor Cassette Design Options; M.E. Sawan, R.T. Santoro, June 1998 [Presented at the 13th Topical Meeting on the Technology of Fusion Energy, June 7-11, 1998, Nashville TN]. (8 pages, 294 kB) [more]
Three-Dimensional Neutronics Analysis for the ITER Divertor Cassette Design Options; M.E. Sawan, R.T. Santoro, June 1998 [Presented at the 13th Topical Meeting on the Technology of Fusion Energy, June 7-11, 1998, Nashville TN]. (24 pages, 468 kB) [more]
UWFDM-1056 Three-Dimensional Neutronics Analysis for the ITER Divertor Cassette; M.E. Sawan, November 1997 [also ITER/US/97-IV-DV-10]. (22 pages, 261 kB)
UWFDM-1058 Three-Dimensional Activation Analysis for the ITER Divertor Cassette; H.Y. Khater and M.E. Sawan, November 1997 [also ITER/US/97-IV-DV-12]. (73 pages, 867 kB)
UWFDM-1328 Three Dimensional Neutronics Analysis of the ITER First Wall/Shield Module 13; B. Smith, P.P.H. Wilson, M.E. Sawan, June 2007 [presented at the 22nd IEEE/NPSS Symposium on Fusion Engineering, 17-21 June 2007, Albuquerque NM]. (7 pages, 2.9 MB)
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-1007 Summary Report on the Neutronics Activities Performed by the U.S. Home Team as Part of the Blanket Design Task D202 in 1995; M.E. Sawan, H.Y. Khater, L.A. El-Guebaly, March 1996. (30 pages, 665 kB)
UWFDM-1042 Summary Report on Work Performed in the Divertor Design Task D308, Subtask 10: Neutronics and Shielding Support Analyses of the ITER Divertor; M.E. Sawan, February 1997 [also ITER/US/96/IV-DV-21]. (22 pages, 261 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)
Status of the ITER Project and Neutronics Activities; Mohamed Sawan, November 2006 [presented at the Cross Section Evaluation Working Group (CSEWG) Meeting, 6-7 November 2006, Brookhaven National Laboratory, Long Island NY]. (23 pages, 6.5 MB)
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)
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-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-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-964 Shielding Analysis for the ITER Divertor and Vacuum Pumping Ducts; M.E. Sawan, Y. Gohar, R. Santoro, 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]. (19 pages, 683 kB) [more]
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-1075 Self-Shielding Effects in Decay Heat Calculations for Tungsten; M.E. Sawan, H.Y. Khater, H. Iida, R.T. Santoro, June 1998 [Presented at the 13th Topical Meeting on the Technology of Fusion Energy, June 7-11, 1998, Nashville TN]. (6 pages, 196 kB) [more]
Self-Shielding Effects in Decay Heat Calculations for Tungsten; M.E. Sawan, H.Y. Khater, H. Iida, R.T. Santoro, June 1998 [Presented at the 13th Topical Meeting on the Technology of Fusion Energy, June 7-11, 1998, Nashville TN]. (12 pages, 254 kB) [more]
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)
UWFDM-1024 Radiological Dose Rate Calculations for the International Thermonuclear Experimental Reactor (ITER); H.Y. Khater and R.T. Santoro, June 1996 [Presented at the 12th Topical Meeting on the Technology of Fusion Power, 16-20 June 1996, Reno NV]. (8 pages, 615 kB) [more]
Radiation Streaming in Gaps Between ITER First Wall/Shield Modules; T.D. Bohm, M.E. Sawan, P. Wilson, September 2008 [presented at the 18th ANS Topical Meeting on Fusion Energy, 28 September-2 October 2008, San Francisco CA]. (1 page, 1.7 MB)
UWFDM-1348 Radiation Streaming in Gaps Between ITER First Wall/Shield Modules; T.D. Bohm, M.E. Sawan, P. Wilson, September 2008 [presented at the 18th ANS Topical Meeting on Fusion Energy, 28 September-2 October 2008, San Francisco CA].
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-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-842 Potential for D-3He Operation in ITER; G.A. Emmert, December 1990. (19 pages, 649 kB)