Abstract
Japan sodium-cooled fast reactor is going to adopt an advanced fuel handling system. As for ex-vessel spent fuel handling, a transfer pot with two fuel subassembly positions has been developed so as to shorten refueling period increasing plant availability. The pot is required to provide sufficient cooling capability in case of transportation malfunction. To evaluate cooling capacity of the transfer pot, a mockup pot has been fabricated and heat transfer experiments have been conducted on the mockup pot.
Acknowledgements
The present study includes the results of “Development of Fuel Handling System” entrusted to the Japan Atomic Power Company (JAPC) by the Ministry of Education, Culture, Sports, Science and Technology of JAPAN (MEXT).