[2H17-19] Fast Reactor Safety Evaluation

[2H18] Study on In-Vessel Coolability by Decay Heat Removal Systems in Sodium-cooled Fast Reactors

(2) Conceptual Design of Components in A Sodium Test Apparatus with In-Vessel Direct Heat Exchangers

*Masaaki Tanaka¹, Toshiki Ezure¹, Nobuyuki Ishikawa¹, Kunihiko Nabeshima¹, Kazuhiro Oyama², Hironori Nakamura², Takashi Ichihara² (1. JAEA, 2. MFBR)

Keywords:Sodium-cooled Fast Reactor, Decay Heat Removal System, Sodium Test, In-vessel Coolability

Conceptual design of a sodium experiment facility named AtheNa-RV/DHRS has been conducted for feasibility study of the diverse systems in decay heat removal under various operating conditions. Conceptual design of the major components of the core and the cooling device has been made in accordance with the requirements for significant core thermal-hydraulic problems.