FTI Publications for Author: Sawan, M.E.
Publications
Nuclear Challenges and Progress in Designing Stellarator Power Plants;
L. El-Guebaly, P. Wilson, D. Henderson, M. Sawan, G. Sviatoslavsky, T. Tautges, R. Slaybaugh, B. Kiedrowski, A. Ibrahim and the ARIES Team,
June 2007 [presented at the 13th International Conference on Emerging Nuclear Energy Systems (ICENES 2007), 3-8 June 2007, Istanbul, Turkey]. (23 pages, 16 MB)
UWFDM-810 Apollo-L2, An Advanced Fuel Tokamak Reactor Utilizing Direct Conversion; G.A. Emmert, G.L. Kulcinski, J.P. Blanchard, L.A. El-Guebaly, H.Y. Khater, J.F. Santarius, M.E. Sawan, I.N. Sviatoslavsky, L.J. Wittenberg, R.J. Witt, October 1989 [Presented at the 13th Symposium on Fusion Engineering, 2-6 October 1989, Knoxville TN; published in IEEE 89CH2820-9 (1990) 1043]. (6 pages, 489 kB)
UWFDM-867 An Improved First Stability Advanced Fuel Tokamak, Apollo-L3; G.A. Emmert, G.L. Kulcinski, J.P. Blanchard, L.A. El-Guebaly, H.Y. Khater, C.W. Maynard, E.A. Mogahed, J.F. Santarius, M.E. Sawan, I.N. Sviatoslavsky, L.J. Wittenberg, September 1991 [Presented at the 14th IEEE/NPSS Symposium on Fusion Engineering, 30 September - 3 October 1991, San Diego CA; published in IEEE 91CH3035-3 (1992) 1106]. (7 pages, 577 kB)
UWFDM-707 Radiological Dose Calculations for the Diode Region of the Light Ion Fusion Target Development Facility; D.L. Henderson, M.E. Sawan and G.A. Moses, October 1986 [Fus. Tech. 13 (May 1988) 594]. (60 pages, 2.3 MB)
UWFDM-508 Neutronics Analysis for the MARS Li-Pb Blanket and Shield; J.H. Huang and M.E. Sawan, May 1983 [Nucl. Tech./Fusion 4 (1983) ]. (9 pages, 795 kB)
UWFDM-539 A Tritium Breeding Calculational Benchmark for Self-Cooled Li17Pb83 Blankets; Jin-Hua Huang and Mohamed E. Sawan, September 1983 [submitted to Nuclear Technology]. (39 pages, 1.6 MB)
UWFDM-1331 Assessment of Radiation Streaming Through ARIES-CS He-Access Pipes using Two- and Three-Dimensional Analyses; A. Ibrahim, D.L. Henderson, L.A. El-Guebaly, P.P.H. Wilson, M.E. Sawan, December 2007. (35 pages, 5.1 MB)
Three Dimensional Analysis of Radiation Streaming Through ARIES-CS He-Access Pipes;
A. Ibrahim, D.L. Henderson, L.A. El-Guebaly, P.P.H. Wilson, and M.E. Sawan,
September 2008 [presented at the 18th ANS Topical Meeting on Fusion Energy, 28 September-2 October 2008, San Francisco CA]. (23 pages, 3.0 MB)
UWFDM-1350 Three Dimensional Analysis of Radiation Streaming Through ARIES-CS He-Access Pipes; A. Ibrahim, D.L. Henderson, L.A. El-Guebaly, P.P.H. Wilson, M.E. Sawan, and the ARIES Team, September 2008 [presented at the 18th ANS Topical Meeting on Fusion Energy, 28 September-2 October 2008, San Francisco CA].
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]
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-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]
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-802 Activation and Safety Analyses for the D-3He Fueled Tokamak Reactor Apollo; H.Y. Khater, M.E. Sawan, S.W. Lomperski, I.N. Sviatoslavsky, October 1989 [Presented at the 13th Symposium on Fusion Engineering, 2-6 October 1989, Knoxville TN; published in IEEE 89CH2820-9 (1990) 728]. (7 pages, 781 kB)
UWFDM-809 Dose Rate Calculations for a Light Ion Beam Fusion Laboratory Microfusion Facility; H.Y. Khater and M.E. Sawan, October 1989 [Presented at the 13th Symposium on Fusion Engineering, 2-6 October 1989, Knoxville TN]. (7 pages, 804 kB)
UWFDM-860 Safety and Environmental Aspects of the Apollo-L2 D-3He Reactor; H.Y. Khater and M.E. Sawan, September 1991 [Presented at the 14th IEEE/NPSS Symposium on Fusion Engineering, 30 September - 3 October 1991, San Diego CA; published in IEEE 91CH3035-3 (1992) 704]. (6 pages, 550 kB)
UWFDM-866 The Importance of Using the Mixed Neutron Flux in Activation Analysis of D-3He Fueled Reactors; H.Y. Khater, M.E. Sawan, September 1991 [Presented at the 14th IEEE/NPSS Symposium on Fusion Engineering, 30 September - 3 October 1991, San Diego CA]. (7 pages, 645 kB)
UWFDM-885 Activation Analysis for the D-3He Reactor ARIES-III; H.Y. Khater and M.E. Sawan, March 1992 [Prepared for the 10th Topical Meeting on the Technology of Fusion Energy, 7-12 June 1992, Boston MA]. (8 pages, 625 kB)
UWFDM-888 The Impact of Reactor Operating Time on Activation Levels for Safety Analyses; H.Y. Khater and M.E. Sawan, March 1992 [Prepared for the 10th Topical Meeting on the Technology of Fusion Energy, 7-12 June 1992, Boston MA]. (8 pages, 590 kB)
UWFDM-889 Safety Analysis for ``SOMBRERO'': A KrF Laser Driven IFE Reactor; H.Y. Khater, M.E. Sawan, I.N. Sviatoslavsky, L.J. Wittenberg, March 1992 [Prepared for the 10th Topical Meeting on the Technology of Fusion Energy, 7-12 June 1992, Boston MA]. (9 pages, 553 kB)
UWFDM-890 Environmental and Safety Aspects of ``OSIRIS'': A Heavy Ion Beam Driven IFE Reactor; H.Y. Khater, M.E. Sawan, I.N. Sviatoslavsky, L.J. Wittenberg, W.R. Meier, March 1992 [Prepared for the 10th Topical Meeting on the Technology of Fusion Energy, 7-12 June 1992, Boston MA]. (10 pages, 570 kB) [more]
UWFDM-926 Environmental and Safety Assessment of the Inertially Confined Direct Drive Laser Fusion Power Reactor SIRIUS-P; H.Y. Khater, L.J. Wittenberg, M.E. Sawan, October 1993 [presented at 15th IEEE/NPSS Symposium on Fusion Engineering,. 11-14 October 1993, Hyannis MA]. (7 pages, 941 kB)
UWFDM-965 Radiological Dose Calculations for the Particle Beam Fusion Accelerator Upgrade (PBFA-U); H.Y. Khater and M.E. Sawan, 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]. (17 pages, 580 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-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-1112 Preliminary Radiological Assessment of the Fusion Ignition Research Experiment (FIRE); H.Y. Khater and M.E. Sawan, October 1999 [Presented at the 18th IEEE/NPSS Symposium on Fusion Engineering, Albuquerque NM, 25-29 October 1999]. (7 pages, 330 kB)
UWFDM-1135 Assessment of Personnel Accessibility in the X-1 Facility; H.Y. Khater, M.E. Sawan, R.R. Peterson, October 2000 [presented at the 14th Topical Meeting on the Technology of Fusion Energy, October 15-19, 2000, Park City UT]. (14 pages, 422 kB)
UWFDM-426 The INPORT Concept - An Improved Method to Protect ICF Reactor First Walls; G.L. Kulcinski, G.A. Moses, J. Sapp, M. Sawan, I.N. Sviatoslavsky, D.K. Sze, and W.F. Vogelsang, August 1981 [paper presented at Second Topical Mtg. on Fusion Reactor Materials, August 9-12, 1981, Seattle, WA; J. Nucl. Matls. 103 & 104, 103 (1981)]. (9 pages, 812 kB) [more]
UWFDM-427 TASKA, A Fusion Engineering Test Facility for the 1990's; G.L. Kulcinski, G.A. Emmert, C.W. Maynard, J.F. Santarius, M.E. Sawan, W. Heinz, P. Komarek, W. Maurer, A. Suppan, and E. Opperman, August 1981 [paper presented at Second Topical Mtg. on Fusion Reactor Materials, August 9-12, 1981, Seattle, WA; J. Nucl. Matls. 103 & 104, 67 (1982)]. (8 pages, 780 kB) [more]
UWFDM-607 Differences Between Neutron Damage in Inertial and Magnetic Confinement Fusion Materials Test Facilities; G.L. Kulcinski and M.E. Sawan, November 1984 [presented at the First International Conference on Fusion Reactor Materials, Tokyo, Japan, 3-6 December 1984]. (23 pages, 1.2 MB)
UWFDM-722 SOAR: Space Orbiting Advanced Fusion Power Reactor; G.L. Kulcinski, J.F. Santarius, H.M. Attaya, M.L. Corradini, L.A. El-Guebaly, G.A. Emmert, J.W. Johnson, T.E. Luzzi, C.W. Maynard, M.E. Sawan, I.N. Sviatoslavsky, W.F. Vogelsang, P.L. Walstrom, L.J. Wittenberg, September 1987. (57 pages, 4.0 MB) [more]
UWFDM-745 The Commercial Potential of D-He3 Fusion Reactors; G.L. Kulcinski, I.N. Sviatoslavsky, G.A. Emmert, H. Attaya, J.F. Santarius, M.E. Sawan, Z. Musicki, October 1987 [Presented at 12th Symposium on Fusion Engineering, Monterey, CA, 12-16 October 1987]. (5 pages, 634 kB)
UWFDM-780 Apollo - An Advanced Fuel Fusion Power Reactor for the 21st Century; G.L. Kulcinski, G.A. Emmert, J.P. Blanchard, L. El-Guebaly, H.Y. Khater, J.F. Santarius, M.E. Sawan, I.N. Sviatoslavsky, L.J. Wittenberg, R.J. Witt, October 1988 [presented at the 8th Topical Meeting on the Technology of Fusion Energy, 9-13 October 1988, Salt Lake City UT; published in Fusion Technology 15 (1989) 1233]. (14 pages, 1.4 MB)
UWFDM-830 Apollo-L3, An Advanced Fuel Fusion Power Reactor Utilizing Direct and Thermal Energy Conversion; G.L. Kulcinski, G.A. Emmert, J.P. Blanchard, L.A. El-Guebaly, H.Y. Khater, C.W. Maynard, E.A. Mogahed, J.F. Santarius, M.E. Sawan, I.N. Sviatoslavsky, L.J. Wittenberg, October 1990 [Presented at the 9th Topical Meeting on the Technology of Fusion Energy, 7-11 October 1990, Oak Brook IL; Fusion Technology 19 (1991) 791]. (13 pages, 753 kB)
UWFDM-857 LIBRA-LiTE: A 1000 MWe Reactor; G.L. Kulcinski, R.L. Engelstad, E.G. Lovell, J.J. MacFarlane, E.A. Mogahed, G.A. Moses, R.R. Peterson, S. Rutledge, M.E. Sawan, I.N. Sviatoslavsky, G. Sviatoslavsky, L.J. Wittenberg, June 1991 [published in J. Fusion Energy, Vol. 10, No. 4, 1991, pp. 339-344]. (13 pages, 1.1 MB)
UWFDM-884 Safety and Environmental Characteristics of Recent D-3He and DT Tokamak Power Reactors; G.L. Kulcinski, J.P. Blanchard, G.A. Emmert, L.A. El-Guebaly, H.Y. Khater, C.W. Maynard, E.A. Mogahed, J.F. Santarius, M.E. Sawan, I.N. Sviatoslavsky, L.J. Wittenberg, March 1992 [Prepared for the 10th Topical Meeting on the Technology of Fusion Energy, 7-12 June 1992, Boston MA; published in Fusion Technology, 21, 1779-1783 (May 1992)]. (8 pages, 546 kB)
UWFDM-896 Summary of Apollo, A D-3He Tokamak Reactor Design; G.L. Kulcinski, J.P. Blanchard, L.A. El-Guebaly, G.A. Emmert, H.Y. Khater, C.W. Maynard, E.A. Mogahed, J.F. Santarius, M.E. Sawan, I.N. Sviatoslavsky, L.J. Wittenberg, April 1992 [published in Fusion Technology 21 (1992) 1779]. (13 pages, 538 kB)
UWFDM-959 Evolution of Light Ion Driven Fusion Power Plants Leading to the LIBRA-SP Design; G.L. Kulcinski, R.R. Peterson, G.A. Moses, D. Bruggink, P. Cousseau, R.L. Engelstad, Y-M. Lee, H.Y. Khater, E.G. Lovell, J.J. MacFarlane, E.A. Mogahed, S. Rutledge, M.E. Sawan, I.N. Sviatoslavsky, P. Wang, L.J. Wittenberg, June 1994 [Prepared for the Eleventh Topical Meeting on the Technology of Fusion Energy, June 19-23, 1994, New Orleans LA]. (11 pages, 1.5 MB)
UWFDM-983 DRAFT: NOT FOR RELEASE - The Advantages of Using Pb-Li Alloys to Produce Tritium in the APT Project; G.L. Kulcinski, M.E. Sawan, I.N. Sviatoslavsky, H.Y. Khater, L.J. Wittenberg, E.A. Mogahed, R.T. Taussig, J.P. McDaniel, S. Ghose, August 1995 [Bechtel Proprietary Data-31 July 1995]. [more]
UWFDM-1026 LIBRA-SP, A Commercial Fusion Reactor Based on Near Term Technology; G.L. Kulcinski, P. Cousseau, R.L. Engelstad, H.Y. Khater, J.J. MacFarlane, E.A. Mogahed, R.R. Peterson, M.E. Sawan, I.N. Sviatoslavsky, P. Wang, June 1996 [Presented at the 12th Topical Meeting on the Technology of Fusion Power, 16-20 June 1996, Reno NV]. (8 pages, 634 kB)