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: firstname.lastname@example.org
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
|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.
- 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 |
- 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)
-- Recent Publication --