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.
Publications
UWFDM-1364 3-D Assessment of Neutron Streaming through Inboard Assembly Gaps of ARIES Tokamak Power Plant; T.D. Bohm, L.A. El-Guebaly and the ARIES Team, June 2009]. (16 pages, 2.6 MB)
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)
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)
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)
UWFDM-1360 Neutronics Performance Parameters for the US Dual Coolant Lead Lithium ITER Test Blanket Module; M.E. Sawan, E.P. Marriott, M. Dagher, May 2009 [prepared for the 23rd Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego CA]. (6 pages, 1.7 MB)
UWFDM-1349 Source Profile Analysis for the ITER First Wall/Shield Modules; 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].
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].
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-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)
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].
UWFDM-1355 Physics and Technology Conditions for Attaining Tritium Self-Sufficiency for the DT Fuel Cycle; M.E. Sawan and M.A. Abdou, February 2006 [published in Fusion Engineering and Design, 81 (2006) 1131-1144].
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)
UWFDM-1274 Neutronics Features of a Dual Coolant Lithium Lead Test Blanket Module for ITER; M.E. Sawan and M.Z. Youssef, September 2005 [presented at the 21st IEEE/NPSS Symposium on Fusion Engineering (SOFE), 26-29 September 2005, Knoxville TN]. (7 pages, 863 kB)
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)
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)
ITER Test Blanket Module Program;
M.E. Sawan,
December 9, 2003 [FTI Tuesday meeting].
(24 pages, 3.2 MB)
Next Step Options (NSO) Project Update FIRE/ITER;
Mohamed Sawan,
September 9, 2003 [FTI Tuesday meeting].
(29 pages, 403 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-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)
ITER Radiation Shielding and Neutronics Analysis; R.T. Santoro, H. Iida, V. Khripunov, M. Sawan, and T. Inoue, 1998 [Fusion Engineering & Design 39, 593].
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-1057 Neutronics Parameters in the Divertor Diagnostic Cassette of ITER; M.E. Sawan, November 1997 [also ITER/US/97-IV-DV-11]. (17 pages, 202 kB)
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-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)
Activation Analysis for the Plasma Facing Component of ITER Divertor; H.Y. Khater, M. Sawan, and D.L. Henderson, Oct. 1997 [Proc. IEEE 17th Symposium on Fusion Engineering, San Diego, CA].