3:30 PM - 3:45 PM
[1D11] Study on reactor vessel coolability of sodium-cooled fast reactor under severe accident condition
(3)Design study of large scale sodium test facility AtheNa-RV
Keywords:sodium-cooled fast reactor, decay heat removal system, natural circulation, core thermal hydraulic, sodium test
AtheNa-SA project in JAEA is planned to evaluate the availability of cooling system in the reactor vessel under the severe accident of loop-type or pool-type sodium-cooled fast reactor. This report describes the design study of large scale sodium test facility AtheNa-RV, which could simulate natural circulation decay heat removal system in normal or damaged core.