Numerical analysis of the temperature distribution of the EM pump for the sodium thermo-hydraulic test loop of the GenⅣ PGSFR
Creators
- 1. Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)
Description
The temperature distribution of an electromagnetic pump was analyzed with a flow rate of 1380 L/min and a pressure of 4 bar designed for the sodium thermo-hydraulic test in the Sodium Test Loop for Safety Simulation and Assessment-Phase 1 (STELLA-1). The electromagnetic pump was used for the circulation of the liquid sodium coolant in the Intermediate Heat Transport System (IHTS) of the Prototype Gen-Ⅳ Sodium-cooled Fast Reactor (PGSFR) with an electric power of 150 MWe. The temperature distribution of the components of the electromagnetic pump was numerically analyzed to prevent functional degradation in the high temperature environment during pump operation. The heat transfer was numerically calculated using ANSYS Fluent for prediction of the temperature distribution in the excited coils, the electromagnet core, and the liquid sodium flow channel of the electromagnetic pump. The temperature distribution of operating electromagnetic pump was compared with cooling of natural and forced air circulation. The temperature in the coil, the core and the flow gap in the two conditions, natural circulation and forced circulation, were compared. The electromagnetic pump with cooling of forced circulation had better efficiency than natural circulation even considering consumption of the input power for the air blower. Accordingly, this study judged that forced cooling is good for both maintenance and efficiency of the electromagnetic pump
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Technology
- Journal Volume
- 53
- Journal Issue
- 5
- Series
- 16 refs, 12 figs, 2 tabs
- Journal Page Range
- p. 1429-1435
- ISSN
- 1738-5733
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 53091309
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- A CODES; COMPARATIVE EVALUATIONS; COOLING; DESIGN; ELECTROMAGNETIC PUMPS; HEAT TRANSFER; LIQUID FLOW; LIQUID METALS; MAGNET COILS; NATURAL CONVECTION; NUMERICAL ANALYSIS; SODIUM; SODIUM COOLED REACTORS; TEMPERATURE DISTRIBUTION
- Descriptors DEC
- ALKALI METALS; COMPUTER CODES; CONVECTION; ELECTRIC COILS; ELECTRICAL EQUIPMENT; ELEMENTS; ENERGY TRANSFER; EQUIPMENT; EVALUATION; FLUID FLOW; FLUIDS; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; LIQUIDS; MASS TRANSFER; MATHEMATICS; METALS; PUMPS; REACTORS