Lead coolant test facility systems design, thermal hydraulic analysis and cost estimate

The Idaho National Laboratory prepared a preliminary technical and functional requirements (T&FR), thermal hydraulic design and cost estimate for a lead coolant test facility. The purpose of this small scale facility is to simulate lead coolant fast reactor (LFR) coolant flow in an open lattice geometry core using seven electrical rods and liquid lead or lead–bismuth eutectic coolant. Based on review of current world lead or lead–bismuth test facilities and research needs listed in the Generation IV Roadmap, five broad areas of requirements were identified as listed below:•Develop and demonstrate feasibility of submerged heat exchanger.•Develop and demonstrate open-lattice flow in electrically heated core.•Develop and demonstrate chemistry control.•Demonstrate safe operation.•Provision for future testing.This paper discusses the preliminary design of systems, thermal hydraulic analysis, and simplified cost estimated. The facility thermal hydraulic design is based on the maximum simulated core power using seven electrical heater rods of 420 kW; average linear heat generation rate of 300 W/cm. The core inlet temperature for liquid lead or Pb/Bi eutectic is 4200 °C. The design includes approximately seventy-five data measurements such as pressure, temperature, and flow rates. The preliminary estimated cost of construction of the facility is $3.7M (in 2006 $). It is also estimated that the facility will require two years to be constructed and ready for operation.