Prof. Mohamed Abdou's Research Areas
- Developed theory and computational methods for nuclear heating.
- Performed integral experiments (in collaboration with Japan) on tritium breeding, nuclear heating, induced radioactivity, and decay heat. Made advances in: a) use of "point" neutron source in a "line source" arrangement, b) experimental techniques, and c) 3-D computational methods.
- Developed special methods for radiation transport in deep radiation penetration problems.
- Method development, nuclear analysis, and nuclear data assessments.
- Applications to blanket, shield, and fusion reactor designs
Tritium Behavior & Fuel Cycle
- Developed dynamic model of the complete tritium fuel cycle in fusion systems to predict tritium behavior, flow rates, and inventories in all components.
- Developed methodology to derive physics and technology conditions and parameters required to attain tritium fuel self-sufficiency. Applied methodology to identify R&D priorities for fusion physics and technology.
- Developed phenomenological and computational models for tritium release and transport in lithium ceramics and beryllium; benchmarked against experiments in fission reactors.
- Developed models and computational methods, and performed experiments for liquid metal MHD fluid flow and heat transfer (2-D core-flow approximation and 3-D full solution) in self-cooled (closed channel) blankets.
- Advanced models and performed experiments for understanding surface heat transfer and fluid flow behavior of free-surface flows with and without magnetic field. Applied results to investigating "liquid walls" in inertial and magnetic fusion systems.
- Experiments and models to predict the effective thermomechanical properties and interface heat conductance of ceramic blanket pebble beds.
- Modeling and analysis of the changes of the packed states through pebble/pebble and bed/clad interactions during blanket operation.
- Measurements of the interface heat conductance between non-conforming beryllium and metallic surfaces subject to non-uniform thermal deformations.
Innovative Designs and Engineering Testing
- Conceptual design and system analysis for magnetic and inertial fusion power reactors.
- Conceptual design and critical analysis of feasibility and attractiveness issues for self-cooled liquid metal blankets and ceramic breeder blankets.
- Conceptual design and system analysis of technology development facilities and volumetric neutron source (VNS; also called Component Development Facility, CTF)
- Development of technical approach and similarity parameters for fusion nuclear technology testing and development. Application to experiments in Testing Facilities such as ITER and VNS/CTF.
- Innovative designs and analysis for high power density plasma chamber technology including free-surface liquid walls and high-temperature refractory alloys.
- Examples of studies and projects for which a major leadership role and substantial technical contributions were provided:
- ITER US Test Blanket Module (TBM) Project (Blanket test module and ancillary equipment: design and engineering, R&D experiments and predictive capability, cost estimates, technical planning, testing strategy, and fabrication and prototype testing. Objective is to develop, deploy, and operate a series of US test blanket modules in ITER) (2003-Present)
- APEX (Advanced Power Extraction Study, 1997-2003)
- Test Program for ITER, the International Thermonuclear Experimental Reactor (Leader of the International Program, 1987-1989 and 1993-1995; Leader of the U.S. Program 1987-Present)
- IEA-HVPNS (International Energy Agency Study on High-Volume Plasma-Based Neutron Sources, 1994-1995)
- PROMETHEUS (Conceptual reactor design study for Inertial Fusion, 1991-1993)
- Technical Program Analysis (Leadership of Fusion Technology in the US Community studies, 1985-1987)
- FINESSE (The most comprehensive study to date of engineering scaling issues, phenomena, experiments and facilities for Fusion Nuclear Technology, 1983-1987)
- BCCS (Blanket Comparison and Selection Study, 1983-1984)
- DEMO (First Demonstration Power Plant study in the world, 1980-1983)
- INTOR (International Tokamak Reactor, US, Japan, Europe, and Russia; led the U. S. Fusion Nuclear Technology Research and Design Effort, 1980-1983)
- STARFIRE (Comprehensive reactor conceptual design, 1979-1982)