Dr. Magdi Ragheb

Engineering at Illinois Engineering at Illinois

Dr. Magdi Ragheb

Dr. Magdi Ragheb

RESEARCH INTERESTS:

  • Computational methods
  • Reactor theory
  • Monte Carlo methods
  • Radiation protection and shielding
  • Probabilistic risk Assessment
  • Applied artificial intelligence
  • Supercomputing

EDUCATION:

  • B.Sc. Nuclear Engineering Univ. of Alexandria 1970
  • M.Sc. Nuclear Engineering Univ. of Alexandria, Undp-Unesco 1973 Science Centre for Postgraduate Studies
  • M.Sc. Nuclear Engineering Univ. of Wisconsin, Madison 1974
  • Ph.D. Nuclear Engineering Univ. of Wisconsin, Madison 1978 Computer Sciences

ACADEMIC POSITIONS HELD:

  • Assistant Professor, 1979-1986
  • Faculty Visitor, Interdisciplinary Research Center, National Center for Supercomputing Applications (NCSA), University of Illinois at Urbana-Champaign, 1985-1987
  • Associate Professor, 1986 - present

MAJOR CONSULTING ACTIVITIES

  • Idaho National Engineering Laboratory (INEL), Computer Application Division, Idaho Falls, Idaho
  • Inference Corp., Los Angeles, CA, University Advisory Committee, Joint Research on Artificial Intelligence Applications in Education and Research.
  • Applications Department, Cray Research Inc., Mendota Heights, Minnesota. Development of Artificial Intelligence Concepts on Supercomputers with application to the Safety Analysis of Nuclear Power plants. The first general-purpose Inference Engine using forward and backward chaining to be installed on a Cray Supercomputer was developed by M. Ragheb.
  • O'Donnell and Associates, Pittsburgh, Pennsylvania. Shielding Studies in Support of the SP-100 Space Power Reactor Program.
  • Illinois Department of Nuclear Safety, State of Illinois, Springfield, Illinois. Development of System for Emergency Response Analysis based on Artificial Intelligence Concepts.
  • Imagineering Ltd., Minnetonka, Minnesota. Particle Transport for High Resolution Industrial Neutron Tomography of Thick Structures.
  • Illinois Power Company, Clinton Power Plant, Clinton, Illinois. Development of Computerized Technical Specifications and Limiting Conditions System based on Artificial Intelligence Concepts.
  • Imagineering Ltd., Minnetonka, Minnesota. Measurement of Plasma Ion Density and or Temperature Profiles in Near Term Fusion Ignition Experiments.
  • Department of Nuclear Engineering, Brookhaven National Laboratory, Upton, New York. Three-dimensional neutronics and photonics studies of high-temperature fusion blankets for process heat and synthetic fuels production. Development of Monte Carlo calculational techniques.
  • Fusion Research Program, Univ. of Wisconsin, Madison. Joint work on blanket and shield design of contemplated fusion reactors designs.

OTHER (patents, designed and marketed software, magazine articles, etc.)

  • Ragheb, M., Associate Editor, "Deep Penetration: Problems and Methods of Solution," Preface, Special Section, Nucl. Technol./Fusion, 5, 69-137 (1984).
  • Ragheb, M., "HAL-1989, Version 2.0," Applications Software Librarian, Applications Dept., Cray Research Inc., 1333 Northland Drive, Mendota Heights, MN 55409.
  • Dr. M. Ragheb implemented the first Knowledge Engineering Analysis System on a Cray Supercomputer in 1985. "HAL-1985" is an analysis system (production system) based on the Rule-Based-System Paradigm. This problem-solving paradigm is the most popular one in Knowledge Engineering, the part of Artificial Intelligence specialized in building Expert Systems. The latest version HAL-1986 is listed in the Cray's software directory. Portable Standard Lisp (PSL) was implemented by M. Ragheb and W. Anderson from Los Alamos National Laboratory on the Univ. of Illinois Cray X-MP in Jan. of 1986.
  • This analysis system uses both Backward-Chaining and Forward Chaining. The Inference Engine uses a deduction-oriented antecedent-consequent logic. It is implemented on a Cray-X-MP advanced large-scale and high-speed multiprocessor system for Scientific Applications. The programming language used is PSL (Portable Standard LISP).
  • The Inference Engine is general and can accommodate general modifications and additions to the Knowledge Base.
  • The Knowledge Base: "SAFETY", currently includes a system for the diagnosis of abnormal situations in Nuclear Reactor Safety Analysis. The Knowledge Box uses a goal tree (AND/OR tree) for representation.

COLLEGE

  • College of Engineering Registration and Student Advisement Comm., 1990