17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017
Abstract
The characteristics of an electromagnetic pump which is used for the circulation of sodium coolant in the Prototype Generation IV Sodium-cooled Fast Reactor (PGSFR) is analyzed. The Intermediate Heat Exchanger (IHX) of the PGSFR is counter-current flow type heat exchanger which transports heat from the sodium coolant of Primary Heat Transport System (PHTS) to that of Intermediate Heat Transport System (IHTS). Because IHX has dominant impact to the performance of heat transport system of PGSFR, the performance of components of the sodium thermohydraulic test system must be verified in the environment of sodium flow. An electromagnetic pump is considered for the generation of sodium flow satisfying easy control of the flow rate. The electromagnetic pump with simple structure has good safety and maintenance property as it is operated without rotating part like an impellor directly-contacting with chemically reacting sodium. The electromagnetic pump with the mass flow rate of 20 kg/s and developed pressure of 4 bar is designed for the sodium thermohydraulic experiment at the Sodium Test Loop for Safety Simulation and Assessment-Phase 1 (STELLA-1) which is constructed in Korea Atomic Energy Research Institute (KAERI). In this study, as one of steps to estimate the characteristic of the electromagnetic pump, narrow annular channel in which sodium flows is numerically analyzed based on magnetohydrodynamics. As results, the relationship between distribution of developed pressure and magnetic field is verified.
Publisher
The Chinese Nuclear Society (CNS) and Xi’an Jiaotong University (XJTU)