Mahmoud Z. Youssef, Ph.D.
Senior Research Engineer and Instructor
Fusion Science and Technology Center
Mechanical and Aerospace Engineering Department
School of Engineering and Applied Science
University of California, Los Angeles
Tel: (310) 825-2879, Fax: (310) 825-2599, E-mail: youssef@fusion.ucla.edu

TEACHING:
MA192A Ordinary Differential Equations and Boundary Value Problem
MA191A Complex Variables and Integral Transform
MA192B Applied Partial Differential Equations and Boundary Value Problem
MA169A Mechanical Vibration

EDUCATION:
B.S. Nuclear Engineering, University of Alexandria, 1967.
M.S. Nuclear Engineering, University of Alexandria, 1973.
M.S. Nuclear Engineering, University of Wisconsin, 1976.
Ph.D. Nuclear Engineering, University of Wisconsin, 1980.

M.S. Thesis: "Evaluation of the Effective Cross Section of Fast and Epithermal Neutrons," University of Alexandria, 1973.
Ph.D. Thesis: "Fusion-Fission Systems Analysis and the Impact of Nuclear Data Uncertainties on Design,"University of Wisconsin, 1980.

PROFESSIONAL EXPERIENCE:
  • In charge of research in the area of nuclear performance and design for fusion/fission reactor blanket and shield, activation and safety operation of fusion devices.
  • Experience with the several computer codes, modules and neutron cross section libraries in use for nuclear analysis and design, among them: (a) Data Processing: AMPX I&II, NJOY, TRANSX-2, (b) Data bases: ENDF/B-I-VI, JENDL-3.2, FENFL1-2 (c) Deterministic transport codes: ANISN, 1-&2-&3-DANT, DOT , DORT , TORT, GRTUNCL, and TRISM (d) Monte Carlo codes: MCNP, (e) Cross-section sensitivity/uncertainty codes: SWANLAKE, SENSIT, SENSIT-2D, FORSS, UNCER, and (f) Radioactivity codes: REAC3, PULSAR)
    • >
  • Extensive cross-section sensitivity/uncertainty analysis pertaining to tritium fuel cycle due to uncertainties in design parameters and nuclear data.
  • Shared plans for long-term Inertial Fusion Energy (IFE) development. Comparison between Inertial Confinement Fusion (ICF) and Magnetic Confinement Fusion (MCF) reactor design and R&D issues.
  • Coordination and participation in the 10-year international research program of the USDOE/JAERI (Japan) Collaboration on Fusion Integral experiments utilizing the FNS 14 MeV neutron source to validate the predictive capabilities of neutron transport codes and nuclear data bases.
  • Execution of the Neutronics R&D Program of the International Thermonuclear Experimental Reactor (ITER). Predictive capabilities for the neutronics parameters of the blanket and shield components of ITER are verified using the 14 MeV facilities of FNS (JAERI), FNG (Frascati), and SNEG-13 (Russia).
  • Participation in the development of the Fusion Evaluated Nuclear Data Library (FENDL) led by the Nuclear Data Center (NDS) of the International Atomic Energy Agency (IAEA), Vienna, Austria.
  • Participation in executing the International Energy Agency (IEA) Implementing Agreement of the Co-operative Program on the Nuclear Technology of Fusion Reactors, Sub-Task “Neutronics”. This is an on-going activity with the objectives of improving nuclear data bases and computational tools based on integral experiments.
School of Engineering and Appied Science, University of California, Los Angeles
Research Engineer: May 1980 - Present

ACHIEVEMENTS:

  • Author/Co-author of ~113 manuscripts appeared in Scholarly Journals/Proceedings of technical meetings (mostly presented in oral/poster sessions of national/international conferences), ~60 technical reports, and ~128 presentations in workshops/research study meetings.
  • Development of statistical methodology to quantify design margin/safety factors based on observed discrepancies between measured and calculated integral design parameters (responses).
  • Development of methodology for propagating uncertainties in neutron secondary energy distribution (SED) and angular distribution (SAD) data to uncertainties in calculated integral responses.

SELECTED PUBLICATION (45 out 113)

  • 1. M.Z. Youssef, “Isotopic Tailoring To Improve The Breeding Capability Of The Sn-Li Eutectic In Thick Liquid FW Fusion Blanket Concept”, presented at the 15Th Topical Meeting on The Technology of Fusion Technology (TOFE), Nov,17-22, 2002, Washington D.C, to appear in Fusion Technology, 2003.
  • 2. M.Z. Youssef, M.E. Sawan, and D.-K. Sze “The Breeding Potential of "Flinabe" and "Flibe" in "CliFF" High Power Density Concept”, Fusion Engr. &Design, 61-62, (2002) 497-503.
  • 3. M.Z. Youssef and M.E. Sawan, “Component Lifetime Comparison and Waste Volume in CLiFF Sn/Flibe and Sn/LiPb Blankets”, Fusion Engr. &Design, 63-64, (2002) 277-283.
  • 4. M.Z. Youssef and M.E. Sawan, “Radwaste Volume In Lithium And Flibe Thick Liquid Wall And Comparison To Conventional SW Concepts”, Fusion Engr. &Design, 63-64, (2002) 263-269
  • 5. M.Z. Youssef, H. Khater, and M. Kotschenreuther, “Plasma Stabilization Conducting Shells and Their Impact on TBR and Activation in CLiFF Design, Fusion Technology Journal, 39, (2001) 839-845.
  • 6. M.Z. Youssef, N.B. Morley, and D-K Sze, “Nuclear Performance of the Thin-Liquid FW Concept of the CLiFF Design”, Fusion Technology Journal, 39, (2001) 804-809.
  • 7. M.Z. Youssef and M.A. Abdou, “Heat Deposition, Damage, and Tritium Breeding Characteristics in Thick Liquid Wall Blanket Concepts”, Fusion Eng. & Design, 49-50, (2000) 719-725
  • 8. M.Z. Youssef and C. Wong, “Neutronics Performance of High-Temperature Refractory Alloy Helium-Cooled Blankets for Fusion Application” Fusion Eng. & Design, 49-50, (2000) 727-734
  • 9. M. Abdou and the APEX Team, "Exploring Novel High Power Density Concepts for Attractive Fusion Systems", Fusion Eng. & Design, 45, No.1 (1999) 145-167.
  • 10. M.Z. Youssef, N. Morley, A. El-Azab, "X-Ray Surface and Volumetric Heat Deposition and Tritium Breeding Issues in Liquid-Protected FW in High Power Density Devices", Fusion Technology Journal, 34, (1998) 697-705.
  • 11. M.Z. Youssef, A. Kumar, M.A. Abdou, C. Konno, F. Maekawa, and Y. Ikeda,"Nuclear Analysis of Bulk Shielding Fusion Integral Experiments On Large SS316/Water Assembly With Simulated Super Conducting Magnet", Fusion Technology Journal, 34, (1998) 953-963.
  • 12. Kumar, Y. Ikeda, M.Z. Youssef, M.A. Abdou, and Y. Kasugai, “Validation of Induced Radioactivity Calculations for Candidate Fusion Materials Through Measurements in a Graphite-Centered Assembly,” Fusion Engr. &Design, 42, (1998) 319-327.
  • 13. Kumar, Y. Ikeda, M.Z. Youssef, M.A. Abdou, F. Maekawa, and Y. Kasugai, “Experimental Measurements of Nuclear Heating in a Graphite-Centered Assembly in Deuterium-Tritium Neutron Environment for Validation of Data and Calculation,” Fusion Engr. &Design, 42, (1998) 307-318.
  • 14. J.E. Eggleston, M.A. Abdou, and M.Z. Youssef, “The Use of MCNP for Neutronics Calculations within Large Buildings of Fusion Facilities Fusion Engr. &Design, 42, (1998) 281-288.
  • 15. M.Z. Youssef, A. Kumar, M. Abdou, H. Khater, M. Sawan, D. Henderson, “Assessment of Dose rate Profiles and Accessibility inside the Building of the International Experimental Fusion Reactor, ITER, During Operation and After Shutdown,” Fusion Engr. &Design, 42, (1998) 155-172.
  • 16. M.Z. Youssef, A. Kumar, M.A. Abdou, C. Konno, F. Maekawa, M. Wada, Y. Oyama, H. Maekawa, and Y. Ikeda, “Verification of ITER Shielding Capability and FENDL Data Benchmarking Through Analysis of Bulk Shielding Experiment on Large SS316/Water Assembly Bombarded with 14 MeV Neutrons,” Fusion Engr. &Design, 42, (1998) 235-245.
  • 17. M.Z. Youssef, A. Kumar, M.A. Abdou, C. Konno, F. Maekawa, M. Wada, Y. Oyama, H. Maekawa, and Y. Ikeda, “Benchmarking FENDL Libraries Through Analysis of Bulk Shielding Experiments on Large SS316 Assemblies for Verification of ITER Shielding Characteristics,” Fusion Technology Journal, 30, December, (1996) 1101-1112
  • 18. A.Kumar, Y. Ikeda, M.A. Abdou, M.Z. Youssef, C. Konno, K. Kosako, Y. Oyama, T. Nakamura, and H. Maekawa, "Decay Radioactivity Induced in Plasma Facing Component Materials by D-T Neutrons" Fusion Technology Journal, 28, No. 1, (1995) 99-155.
  • 19. M.Z. Youssef, A. Kumar, M.A. Abdou, Y. Oyama, C. Konno, F. Maekawa, Y. Ikeda, K. Kosako, M. Nakagawa, T. Mori, and H. Maekawa, "Fusion Integral Experiments and Analysis and The Determination of Design Safety Factors, Part II: Application to the Prediction Uncertainty of Tritium Production rate From The USDOE/JAERI Collaborative Program on Fusion Blanket Neutronics" Fusion Technology Journal, 28, No. 2, (1995) 388-432.
  • 20. M.Z. Youssef, A. Kumar, M.A. Abdou, Y. Oyama, and H. Maekawa, "Fusion Integral Experiments and Analysis and The Determination of Design Safety Factors, Part I: Methodology" Fusion Technology Journal, 28, No. 2, (1995) 366-387.
  • 21. M.Z. Youssef, M.A. Abdou, A. Kumar, K. Kosako, Y. Oyama, F. Maekawa, Y. Ikeda, C. Konno, and H. Maekawa, "The Nuclear Analysis of an Annular Li2O Blanket System Surrounding an Artificially Simulated 14 MeV Line Source and Comparison of Calculations to Measurements" Fusion Technology Journal, 28, No. 2, (1995) 320-346.
  • 22. M. Z. Youssef and A. Kumar, "Analytical Formulae for Estimating Damage Rate in the Final Mirrors of Laser Inertial Fusion Energy Reactors Based on the Uncollided Neutron Flux", Fusion Engr. & Design, 28, (1995) 648-657.
  • 23. M.Z. Youssef, A. Kumar, M.A. Abdou, Y. Oyama, C. Konno, F. Maekawa, Y. Ikeda, K. Kosako, M. Nakagawa, T. Mori, and H. Maekawa, "Quantification of Design Margins/Safety Factors Based on The Prediction Uncertainty in Tritium Production Rate From the Integral Experiments of The USDOE/JAERI Collaborative Program on Fusion Blanket Neutronics", Fusion Engr. & Design, 28, (1995) 457-478
  • 24. Song, P. M., Youssef, M. Z. and Abdou, M.,"A New Approach and Computational Algorithm for Sensitivity/Uncertainty Analysis for SED and SAD with Application to Integral Experiments", Nuclear Sc. & Engr., 113, 339-366, 1993.
  • 25. A. Kumar, M.A. Abdou, M.Z. Youssef, Y. Ikeda, C. Konno, Y. Oyama, K. Kosako, F. Maekawa, and H. Maekawa, "Measurements of Decay Radioactivity of Long-Lived Isotopes", Fusion Technology Journal, 21, 2180-2189,1992.
  • 26. Youssef, M.Z., Kumar, A., Abdou, M.A., Oyama Y., Kosako, K., and Nakamura, T., “Post-Analysis for the Line Source Phase IIIA Experiments of the USDOE/JAERI Collaborative Program on Fusion Neutronics,” Fusion Engineering & Design, 18, 265-274, 1991.
  • 27. Youssef, M.Z., and Watanabe, Y.,"Study on the accuracy of several beryllium data evaluations and comparison of measured and calculated data on reaction rates and tritium production distributions", Fusion Technology Journal, 19, No 3, 1967-1973, 1991.
  • 28. Youssef, M.Z., Watanabe, Y., Kumar, A., Oyama, Y., and Kosako, K.,"Analysis for the simulation of a line source by a 14 MeV moving point source and impact on blanket characteristics: USDOE/JAERI Collaborative Program on Fusion Neutronics", Fusion Technology Journal, 19, No 3, 1843-1852, 1991.
  • 29. Youssef, M., Kumar, A., Abdou, M., Nakagawa, M., Kosako, K., Oyama, Y., and Nakamura,, T., "Analysis for heterogeneous blankets and comparison to measurements: Phase IIC experiments of the USDOE/JAERI Collaborative Program on Fusion Neutronics," Fusion Technology Journal, 19, No 3, 1891-1899, 1991.
  • 30. Youssef, M.Z., and Abdou, M.A., "Neutronics Tests in a Fusion Engineering Facility," Fusion Engineering and Design, 10,95-102, 1989
  • 31. Youssef, M.Z. and Jun, I., "Comparison of PCA versus Tungsten in ITER In-board Shield and Impact of Nuclear Data Uncertainties on Machine Cost," Fusion Tech., 15, 2, Part 2B, 887-892, 1989.
  • 32. Youssef, M.Z., Watanabe, Y., Abdou, M.A., Nakagawa, M., Mori, T., Kosako, K., and Nakamura, T., "Comparative Analysis for Phase IIA and IIB Experiments of the U.S./JAERI Collaborative Program on Fusion Breeder Neutronics,"Fusion Tech., 15, 2, Part 2B, 1299-1308, 1989.
  • 33. Youssef, M.Z., Jung, J., Sawan, M., Nakagawa, M., Mori, T. and Kosako, T., "U.S./JAERI Calculational Benchmarks for Nuclear Data and Codes Intercomparison," Fusion Tech., 10, 1466-1476, 1986.
  • 34. Youssef, M.Z., Gung, C., Nakagawa, M., Mori, T., Kosako, K. and Nakamura, T., "Analysis and Intercomparison for Phase I Fusion Integral Experiments at the FNS Facility," Fusion Tech., 10, 549-563, 1986.
  • 35. Youssef, M.Z. and Abdou, M.A., "Uncertainties in Prediction of Tritium Breeding in Candidate Blanket Designs Due to Present Uncertainties in Nuclear Data Base," Fusion Tech., 9, 286-307, 1986.
  • 36. Deis, G.A., Miller, L.G. and Youssef, M.Z., "Utilization of Fission Reactors for Fusion Engineering Testing," Fusion Tech., 8, 1115-1123, 1985.
  • 37. Youssef, M.Z., "Status of Methods, Codes, and Application for Sensitivity and Uncertainty Analysis," Fusion Tech., 8, 1552-1570, 1985.
  • 38. Youssef, M.Z., "Instrumentation and Safety Controls for Tandem Mirror Fusion Reactors," Nucl. Tech./Fusion, 4, 1479-1485, 1983.
  • 39. Youssef, M.Z. and Conn, R.W., "On Isotopic Tailoring for Fusion Reactor Radioactivity Reduction," Nucl. Tech./Fusion, 4, 1177-1182, 1983.
  • 40. Youssef, M.Z. and Conn, R.W., "Induced Radioactivity and Influence of Materials Selection in DD and DT Systems," Nucl. Tech./Fusion, 3, 361-384, 1983.
  • 41. Conn, R.W., Dhir, V.K., Ghoniem, N.M., Goebel, D.M., Grotz, S.P., Kantrowitz, F., Kim, N.S., Mau, T.K., Shuy, G.W. and Youssef, M.Z., "Studies of the Physics and Engineering of D-D Barrier Tandem Mirror Reactors," Nucl. Tech./Fusion, 2, 563-589, 1982.
  • 42. Youssef, M.Z., Conn, R.W. and Maynard, C.W., "Impact of Cross-Section Uncertainties on the Nuclear Design of Hybrid Reactors," Nucl. Tech./Fusion, 2, 648-666, 1982.
  • 43. Conn, R.W., Abdel-Khalik, S.I., Moses, G.A., Kulcinski, G.L., Larsen, E., Maynard, C.W., Ragheb, M.M.H., Sviatoslavsky, I.N., Vogelsang, W.F., Wolfer, W.G., Ortman, M., Watson, R. and Youssef, M.Z., "Fusion-Fission Hybrid Design with Analysis of Direct Enrichment and Non-Proliferation Features (The SOLASE-H Study)," Nucl. Eng. and Design, 63, 357-374, 1981.
  • 44. Youssef, M.Z. and Conn, R.W., "Separation Method for the Transport Equation and Sensitivity Theory for Fusion-Fission Hybrid Analysis," Nucl. Sci. and Eng., 74, 130-139, 1980.
  • 45. Youssef, M.Z., Conn, R.W. and Vogelsang, W.F., "Tritium and Fissile Fuel Exchange Between Hybrids, Fission Power Reactors, and Tritium Production Reactors," Nucl. Tech., 47, 397-405, 1980. 
    Phone:    (310) 825-2879
e-mail:   youssef@fusion.ucla.edu
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