Scientific design of a large-scale sodium thermal–hydraulic test facility for KALIMER—Part II: Validation of reactor pool design using CFD analyses

• A passive decay heat removal system for the KALIMER-600 fast reactor.
• A 1/5th scale sodium thermal–hydraulic test facility design for the KALIMER-600.
• CFD analysis for validation of the 1/5th scale-down test facility.
• The scale-down model for the reactor pool appeared to be appropriate.

A one-fifth scale test loop for a sodium cooled fast reactor (SFR), KALIMER-600, is designed based on scaling analyses. The coolant flow and temperature distribution inside the prototype reactor pool and 1/5 scale model are numerically analyzed using a CFD package. In order to perform the numerical analyses, numerical models are created for the reactor core and heat exchangers. The analyses results are compared with each other in terms of normalized pressure, velocity magnitude, and temperature distributions. These comparisons demonstrate that the scaling analyses for the reactor pool described in Part I are appropriate and that the one-fifth scale thermal hydraulic test facility provides appropriate simulation of the KALIMER-600 prototype.