Author/Authors :
Vitkovsky، نويسنده , , I.V and Golovanov، نويسنده , , M.M and Divavin، نويسنده , , V.A. and Kirillov، نويسنده , , I.R and Lipko، نويسنده , , A.V and Malkov، نويسنده , , A.A and Kartashev، نويسنده , , I.A and Komarov، نويسنده , , V.M and Ogorodnikov، نويسنده , , A.P and Schipakin، نويسنده , , O.L، نويسنده ,
Abstract :
The RF Home Team lithium-cooled test blanket module (TBM) is one of the TBMs to be tested in international thermonuclear experimental reactor (ITER). To satisfy ITER safety demands, the TBM is enclosed in helium-cooled shell. So, it simulates DEMO reactor by having comparable radial dimensions and by using all the materials of DEMO reactor, but does not simulate first wall (FW) conditions. To achieve the last task, it is planned to modify this module slightly and test it at ITER extended performance phase with Li-cooled FW. Some results of neutronic, thermal–hydraulic and stress analysis are presented here for TBM with He-cooled FW.
Keywords :
ITER , vanadium , Test blanket module , Lithium self-cooled
