[2J17-19] Fast Reactor Thermal Hydraulics

[2J19] PLANDTL-2 Experiment for Evaluation of Decay Heat Removal in Sodium-cooled Fast Reactors

Effect of Inter-subassembly Gap Flow under Interruption of Flow through Fuel Assemblies

*Toshiki Ezure¹, Yuta Akimot¹, Mitsuyo Tsuji¹, Akikazu Kurihara¹, Masaaki Tanaka¹ (1. JAEA)

Keywords:sodium-cooled fast reactor, decay heat removal, dipped-direct heat exchanger, inter-subassembly gap flow

Sodium experiments using PLANDTL-2 test facility, which have multiple rows of simulated core, have been carried out to clarify the decay heat removal characteristics inside a reactor. In this study, decay heat removal experiments were carried out using a dipped-direct heat exchanger under no primary flow rate conditions and interrupting the flow through the assemblies by a plugging system of fuel assemblies. As the results, the influence of inter-subassembly gap flow on the cooling characteristics of simulated core was clarified.