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-976 1994 Summary Report for ITER Design Task D4. Shielding 3D Analysis. Afterheat Analysis for the Whole Machine and Cryostat Area. Part A: Neutronics and Shielding; M.E. Sawan, L.A. El-Guebaly, H.Y. Khater, January 1995. (30 pages, 859 kB)
3-D 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]. (1 page, 5.8 MB)
UWFDM-1037 3-D Thermo-Mechanical Analysis of the ITER Limiter Small Scale Specimen; E.A. Mogahed and I.N. Sviatoslavsky, December 1996. (17 pages, 4.6 MB)
UWFDM-1052 3-D Thermo-Mechanical Analysis of the ITER Limiter Small Scale Specimen; E.A. Mogahed and I.N. Sviatoslavsky, October 1997 [Presented at the 17th IEEE/NPSS Symposium on Fusion Engineering, 6-10 October 1997, San Diego CA]. (6 pages, 279 kB)
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)
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-966 Activation Analyses for the Different Options Considered in the U.S. ITER Blanket Trade-Off Study; H.Y. Khater, 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]. (16 pages, 511 kB)
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-1083 Activation Analysis for the ITER Divertor Cassette; H.Y. Khater and M.E. Sawan, June 1998 [Presented at the 13th Topical Meeting on the Technology of Fusion Energy, June 7-11, 1998, Nashville TN]. (6 pages, 177 kB)
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-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-1363 Application of CAD-Neutronics Coupling to Geometrically Complex Fusion Systems; M.E. Sawan, P.P.H. Wilson, T. Tautges, L.A. El-Guebaly, D.L. Henderson, T.D. Bohm, E.P. Marriott, B. Kiedrowski, B. Smith, A. Ibrahim, R. Slaybaugh, May 2009 [prepared for the 23rd Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego CA]. (8 pages, 2.8 MB) [more]
UWFDM-1006 Application of FENDL Nuclear Data to ITER Neutronics and Shielding Analyses; M.E. Sawan, March 1996 [Presented at the 1996 Radiation Protection and Shielding Topical Meeting, North Falmouth, MA, April 21-25, 1996]. (11 pages, 487 kB)
UWFDM-1041 Application of the Processed FENDL Libraries to the Calculational Benchmark and ITER Design; M.E. Sawan, February 1997 [presented at the IAEA Advisory Group Meeting on ``Extension and Improvement of the FENDL Library for Fusion Applications,'' Vienna, Austria, 3-7 March 1997]. (18 pages, 162 kB)
UWFDM-1368 Assessment of Using the Surface Source Approach in 3-D Neutronics of Fusion Systems; T.D. Bohm, B. Smith, M.E. Sawan, P.P.H. Wilson, August 2009. (22 pages, 3.8 MB)
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]
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]
Assessment of the Surface Source Approach in 3-D Fusion Neutronics Analysis; T.D. Bohm, B. Smith, M.E. Sawan, P. Wilson, November 2010 [presented at the 19th ANS Topical Meeting on Fusion Energy, 7-11 November 2010, Las Vegas NV]. (1 page, 4.3 MB)
UWFDM-1361 Benchmarking FENDL-2.1 with Impact of ENDF/B-VII.0 Release on Nuclear Heating and Damage; M.E. Sawan, May 2009 [prepared for the 23rd Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego CA]. (6 pages, 550 kB)
Benchmarking FENDL-2.1 with Impact of ENDF/B-VII.0 Release on Nuclear Heating and Damage; M.E. Sawan, May 2009 [presented at the 23rd Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego CA]. (1 page, 1.7 MB)
Detailed 3-D Nuclear Analysis of ITER Blanket Modules; T.D. Bohm, M.E. Sawan, E.P. Marriott, P. Wilson, M. Ulrickson, J. Bullock, September 2013 [presented at the 11th International Symposium on Fusion Nuclear Technology, 16-20 September 2013, Barcelona, Spain]. (1 page, 1.7 MB) [more]
Detailed Nuclear Analysis of ITER Blanket Modules (Work In Progress); T.D. Bohm, M.E. Sawan, S.T. Jackson, P. Wilson, September 2011 [presented at the 10th International Symposium on Fusion Nuclear Technology (ISFNT), 11-16 September 2011, Portland OR]. (1 page, 2.8 MB)
Detailed Nuclear Analysis of ITER ELM Coils; T.D. Bohm, M.E. Sawan, S.T. Jackson, P. Wilson, September 2011 [presented at the 10th International Symposium on Fusion Nuclear Technology (ISFNT), 11-16 September 2011, Portland OR]. (1 page, 3.1 MB)
ELM Coils: Nuclear Environment and Shielding Issues; M.E. Sawan and T. Bohm, February 2010 [presented at the ITER Neutronics Meeting, 8-9 February 2010, Aix-en-Provence, France]. (20 pages, 2.0 MB)
UWFDM-1411 Environmental Aspects of W-Based Components Employed in ITER, ARIES, and PPCS Fusion Designs; M. Desecures, L. El-Guebaly, June 2012. (34 pages, 1.9 MB) [more]
Global Evaluation of the Prompt Dose in ITER Using the Hybrid Monte Carlo/Deterministic Techniques; Ahmad Ibrahim, Scott Mosher, Thomas Evans, Douglas Peplow, Mohamed Sawan, Paul Wilson, John Wagner, November 2010 [presented at the 19th ANS Topical Meeting on Fusion Energy, 7-11 November 2010, Las Vegas NV]. (13 pages, 1.9 MB) [more]
UWFDM-1020 ITER Limiter First Wall 3-D Thermo-Mechanical Analysis; E.A. Mogahed and I.N. Sviatoslavsky, May 1996 [Presented at the 12th Topical Meeting on the Technology of Fusion Power, 16-20 June 1996, Reno NV]. (7 pages, 727 kB)
UWFDM-1399 ITER Neutronics Modeling Using Hybrid Monte Carlo Deterministic and CAD-Based Monte Carlo Methods; A.M. Ibrahim, S.W. Mosher, T.M. Evans, D.E. Peplow, M.E. Sawan, P.P.H. Wilson, J.C. Wagner, T. Heltemes, July 2011 [published in Nuclear Technology Vol. 175 (July 2011) 251--258]. [more]
ITER Neutronics Modeling Using Hybrid Monte Carlo/Deterministic Techniques and CAD Based Monte Carlo; A.M. Ibrahim, S.W. Mosher, T.M. Evans, D.E. Peplow, M.E. Sawan, P.P.H. Wilson, J.C. Wagner, April 2010 [presented at the American Nuclear Society Radiation Protection and Shielding Division Topical Meeting, 19 April 2010, Las Vegas, NV]. (23 pages, 1.8 MB) [more]
ITER Test Blanket Module Program; M.E. Sawan, December 9, 2003 [FTI Tuesday meeting]. (24 pages, 3.2 MB)
Impact of FENDL-2.1 Updates on Nuclear Analysis of ITER and Other Fusion Systems; M.E. Sawan and T.D. Bohm, April 2010 [presented at the International Conference on Nuclear Data for Science and Technology 2010 (ND2010), 26-30 April 2010, Jeju, Korea]. (1 page, 1.1 MB)
UWFDM-1400 Impact of FENDL-2.1 Updates on Nuclear Analysis of ITER and Other Fusion Systems; M.E. Sawan and T.D. Bohm, August 2011 [published in Journal of the Korean Physical Society, Vol. 59, No. 2, August 2011, pp. 1158-1161].
Improved Geometrical Design of the US DCLL ITER Test Blanket Module; E. Marriott, M. Dagher, M. Sawan, C. Wong, June 2011 [presented at the 24th Symposium on Fusion Engineering (SOFE), 26--30 June 2011, Chicago IL]. (1 page, 2.8 MB) [more]
UWFDM-1395 Improvements to the Helium Flow Path in the US DCLL ITER Test Blanket Module; E.P. Marriott, June 2011. (17 pages, 3.0 MB)
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]
Investigation of Observed Peaking in Nuclear Parameters at Steel/Water Interfaces; T.D. Bohm, M.E. Sawan, B. Smith, P. Wilson, November 2010 [presented at the 19th ANS Topical Meeting on Fusion Energy, 7-11 November 2010, Las Vegas NV]. (1 page, 1.8 MB)
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-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-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-1326 Neutronics Assessment of the ITER First Wall/Shield Modules; M.E. Sawan, B. Smith, P. Wilson, June 2007 [presented at the 22nd IEEE/NPSS Symposium on Fusion Engineering, 17-21 June 2007, Albuquerque NM]. (9 pages, 3.2 MB)