Thermal Hydraulic Analysis of the Annular Flow Helium Heater Design

摘要

Oak Ridge National Laboratory has conducted Core Support Performance Test (CSPT) by use of an existing facility, Component Flow Test Loop (CFTL), as part of the High Temperature Gas-Cooled Reactor (HTGR) application program. A major objective of the CSPT is to study accelerated corrosion of the core graphite support structure in helium at reactor conditions. Concentration of impurities will be adjusted so that a 6-month test represents the 30-year reactor life. Thermal hydraulic and structural integrity of the graphite specimen, among other things, will be studied at high pressure of 7.24 MPa (1050 psi) and high temperature of 1000 exp 0 C (1832 exp 0 F) in a test vessel. To achieve the required high temperature at the test section, a heater bundle has to be specially designed and properly manufactured. This report presents performance characteristics of the heater that were determined from an analysis based on this design. (ERA citation 07:043409)