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

66 publications found » search for others [linked reports are PDF]

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].

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].

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-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].

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].

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].

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].

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].

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].

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].

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].

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].

UWFDM-1057 Neutronics Parameters in the Divertor Diagnostic Cassette of ITER; M.E. Sawan, November 1997 [also ITER/US/97-IV-DV-11].

UWFDM-1056 Three-Dimensional Neutronics Analysis for the ITER Divertor Cassette; M.E. Sawan, November 1997 [also ITER/US/97-IV-DV-10].

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].

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].

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].

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].

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].

UWFDM-1037 3-D Thermo-Mechanical Analysis of the ITER Limiter Small Scale Specimen; E.A. Mogahed and I.N. Sviatoslavsky, December 1996.

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].

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].

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].

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].

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).

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.

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].

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].

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].

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].

UWFDM-946 Experimental Vessel for JUPITER; R.R. Peterson, R.L. Engelstad, H.Y. Khater, Y-M. Lee, S.C. Rutledge, May 1994.

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].

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].

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].

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.

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].

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.]

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].

UWFDM-842 Potential for D-3He Operation in ITER; G.A. Emmert, December 1990.

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].

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].

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].

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)].

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)].

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].

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].

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].

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].

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].

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)].

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].