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
65 publications found » search for others [linked reports are PDF]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)
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)
Nuclear Analysis Capabilities for Fusion Energy Systems; A. Ibrahim, R. Slaybaugh, B. Smith, B. Kiedrowski,
March 2007 [presented at the 2007 ANS Student Conference, Oregon State University, Corvallis OR, 29-31 March 2007]. (1 page, 4.8 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)
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)
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)
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]. (1 page, 1.4 MB)
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)
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)
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)
R.T. Santoro, H. Iida, V. Khripunov, M. Sawan, and T. Inoue, "ITER Radiation Shielding and Neutronics Analysis," Fusion Engineering & Design 39, 593 (1998).
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)
H.Y. Khater, M. Sawan, and D.L. Henderson, "Activation Analysis for the Plasma Facing Component of ITER Divertor," Proc. IEEE 17th Symposium on Fusion Engineering, San Diego, CA (Oct. 1997), IEEE Cat. No. 97CH36131, Vol. 1, pp. 157.
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-1051 Nuclear Heating and Damage Profiles in the ITER Divertor Cassette; M.E. Sawan and R.T. Santoro, September 1997 [Presented at the 17th IEEE/NPSS Symposium on Fusion Engineering, 6-10 October 1997, San Diego CA]. (6 pages, 163 kB)
UWFDM-1043 Summary Report on Work Performed by the U.S. Home Team in the Blanket Design Task D307A, Subtask 1.2: Nuclear Analysis in Support of Blanket and Vacuum Vessel Design; M.E. Sawan and H.Y. Khater, March 1997 [also ITER/US/97/IV-BL-4]. (23 pages, 243 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-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-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-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)
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)
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-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)
M. Sawan, and L. El-Guebaly, "Neutronics and Shielding Results of the U.S. ITER Blanket Trade-off Study," Fusion Engineering & Design 28, 551 (1995).
M. Sawan, Y. Gohar, and R.T. Santoro, "Shielding Analysis for the ITER Divertor and Vacuum Pumping Ducts," Fusion Engineering & Design 28, 429 (1995).
R.T. Santoro, Y. Gohar, R. Parker, G. Shatalov, M. Sawan, and H. Khater, "ITER Shielding Analysis," Fusion Engineering & Design 27, 62 (1995).
M.E. Sawan and L.A. El-Guebaly, "Neutronics and Shielding Results of the U.S. ITER Blanket Trade-Off Study," Fusion Engineering and Design, 28, 551-558 (1995).
M. Sawan, L. El-Guebaly and H. Khater, "ITER 3D Shielding Analysis and Afterheat Analysis for the Whole Machine and Cryostat Area," University of Wisconsin Fusion Technology Institute Report UWFDM-976 (1995).
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-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)
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-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-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)
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)
W. Daenner, L. El-Guebaly, M. Sawan, et al., "Neutron Shielding and Its Impact on the ITER Machine Design," Fusion Engineering & Design, Vol. 16, Part A, 183 (Dec. 1991).
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)
M.E. Sawan and L.A. El-Guebaly, "Three-Dimensional Neutronics Analysis for the US Magnet Shield of ITER," Fusion Technology, Vol. 19, No. 3, Part 2B, 1469 (May 1991).
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, 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)
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, 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)
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)
L.A. El-Guebaly et al., "U.S. Technical Report for the ITER Blanket/Shield," Part B ITER Report, ITER-TN-BL-5-0-6, Garching, Germany (July 1990).
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) 33-44]. (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)

