[2A01-04] Thermal Hydraulics of Fast Reactors

[2A02] Numerical Analysis of Decay Heat Removal Experiments using Dipped-type Direct Heat Exchanger in sodium test facility PLANDTL-2 for Sodium-cooled Fast Reactor Development

*Toshiki Ezure¹, Yasuhiro Miyake², Erina Hamase¹, Masaaki Tanaka¹ (1. JAEA, 2. NDD)

Keywords:Sodium-cooled fast reactor, decay heat removal, Dipped direct heat exchanger, Numerical analysis

As a part of the safety enhancement of sodium-cooled fast reactors, development of numerical analysis method using CFD code has been conducted to evaluate core coolability by decay heat removal system using a dipped-type direct heat exchanger (D-DHX) installed in the upper plenum of the reactor vessel by using the sodium experimental data obtained in sodium test facility PLANDTL-2. Temperature distributions of experiments both in the core and the upper plenum was well traced by the numerical results. On the while, the importance of further modification of the models for D-DHX and inter wrapper gaps was indicated.