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THERMAL TEST. Expert has 38 years experience in the thermal hydraulic testing of simulated nuclear fuel and reactor recirculation systems. The range of these tests included steady state and transient critical power, assembly pressure drop, two-phase stability, subchannel flow and enthalpy measurements, flow-induced vibration, debris control, counter current flow limiting, as well as many different reactor system safety experiments. Geometries investigated ranged from simple round tubes to 12x12 rod bundles. Many of these experiments were "first of a kind," and formed the basis for several new fuel designs and resulted in many technical society papers.

BOILING-WATER NUCLEAR REACTOR. Expert is an expert in the thermal hydraulic and geometric design, development, and testing of boiling-water reactor nuclear fuel, recirculation, and safety systems. Expert is a holder of 40 US Patents on fuel and components usable in boiling-water reactors.

TWO-PHASE FLOW; TWO-PHASE HEAT TRANSFER. Expert was responsible for several hundred, often "first of a kind", two-phase flow and/or heat transfer experiments. These tests were used to verify two-phase flow theory and to develop new correlations as well as to develop new reactor core designs.

EXPERIMENTAL MATERIALS AND TECHNIQUES. In order to perform efficient, safe, and reliable experiments described above, Expert found it necessary to develop new technology for high-temperature, high-pressure steam-water systems operating at fluid conditions as high as 2300 psi and 650¦F. Some of these items were high-pressure, high-temperature seals of several types, electrical insulating schemes capable of surviving in high-pressure, high-temperature steam-water mixtures and low-temperature melting point alloys used to conduct electric current flows up to 100,000 amps. He provided new concept designs for many different experimental simulations, such as hydrodynamic stability, internal flow measurement, countercurrent flow limiting, loss of coolant accident, turbine trip with and without bypass transients, and flow-induced vibration. Also, Expert was responsible for the design of several experimental high-pressure, high-temperature systems capable of studying various aspects of nuclear core performance.

ELECTRICAL RESISTANCE HEATING ELEMENTS. Expert is experienced with the design, fabrication, and operation of electrical resistance heaters of the types needed to simulate different reactor core states. Some of the heater capabilities included the simulation of radial and axial heat flux conditions and a system for changing during a transient test both total power and the element axial flux shape simultaneously.


In one morning, Expert solved a flow measurement problem that threatened to shutdown the Perry Nuclear Power Station. He participated personally in technology transfer operations in Canada, Japan, Germany, England, Italy, and Sweden.