Design Development of a High-Temperature Sodium Compatibility Testing Facility

摘要

The use of advanced alloys within sodium-cooled fast reactors (SFRs) has been identified as a means of increasing plant efficiency and reducing construction costs. In particular, alloys such as NF-616, NF-709 and HT-UPS are promising because they exhibit greater strength than traditional structural materials such as 316-SS. However, almost nothing is known about the sodium compatibility of these new alloys. Therefore, research taking place at the University of Wisconsin-Madison is focused on studying the effects of sodium corrosion on these materials under prototypic SFR operating conditions (600 [°C], V_(Na)=10 [m/s], C_(o～1) [wppm]). This paper focuses on the design and construction of the testing facility with an emphasis on moving magnet pumps (MMPs). Corrosion data from a preliminary 500 [hr] natural convection test will also be presented.