The U.S. Department of Energy’s (DOE) Office of Nuclear Energy is actively pursuing design research related to Generation IV nuclear reactors for near term deployment as commercial nuclear facilities. High-temperature reactors are expected to provide collateral process heat for industrial applications that require high-temperatures during manufacturing processes. For the DOE to complete its research and development goals, all related components, instrumentation, and materials require assessment in high-temperature environments. The High-Temperature Helium Facility (HTHF) located in the Thermal Hydraulics Laboratory at The Ohio State University was designed to provide a laboratory environment that will be integral to completion of research in these areas. Intended to complement research and development projects that will help the industry reach the objectives set forth by the Generation IV International Forum for the development of next generation, high-temperature gas cooled reactors, construction of the HTHF has been completed.
This document briefly reviews the HTHF’s layout and operational characteristics. Specifically, a detailed list of the facility’s instrumentation and an uncertainty analysis for each component is presented along with a description of the procedures developed to calibrate the thermocouples monitoring the HTHF and their application in the test environment. Calibration results are presented in conjunction with a brief review of thermocouple design and functionality. The calibration results clearly prove that the K-type thermocouples are within their specified tolerances. Calibration, application, and uncertainties of three Venturi meters are detailed herein. It has been observed that one of the three Venturi meters is not functioning according to its calibration. Heat losses related to the heaters, piping, test sections, and instrumentation ports are fully documented and do not show significant deviation from the losses specified in the facility’s design documentation and analyses. Pressure drop across the facility corresponds to known correlations and is nominally between 10 and 20 psi (0.07 and 0.14 MPa).
To date the facility’s performance includes a maximum temperature, pressure and mass flow rate of 640 °C, 400 psig (2.8 MPa), and 50 kg/hr, respectively, using helium as the cooling agent. Following additional testing and possible minor modifications, the facility is expected to provide a testing environment that achieves 800 °C at 435 psig (3 MPa) and 40 kg/hr, which more closely approximates the temperature requirements for high-temperature gas cooled reactors. The HTHF is currently operational with the ability to accommodate various components for testing in a high-temperature environment.