Author/Authors :
Sviridenko، نويسنده , , M.N. and Leshukov، نويسنده , , A.Yu. and Razmerov، نويسنده , , A.V. and Tomilov، نويسنده , , S.N. and Danilov، نويسنده , , I.V. and Strebkov، نويسنده , , Yu.S. and Mazul، نويسنده , , I.V. and Labusov، نويسنده , , A. and Gervash، نويسنده , , A.A. and Belov، نويسنده , , A.V. and Semichev، نويسنده , , D.، نويسنده ,
Abstract :
According to Procurement Arrangement (PA) Russian Federation will procure 40% of enhanced heat flux first wall (FW) panels. The signing of PA is scheduled on November 2013. In framework of PA preparation the RF specialists perform EHF FW design optimization in order to provide the ability to operation of EHF FW panel under ITER conditions.
rticle contains the design description of EHF FW 14 developed by RF and following analysis have been performed:•
lic analysis;
ent thermal analysis;
ural analysis.
es results show that new design of FW panel with two straight welds for finger fixation on FW beam developed by RF specialists can be used as a reference design for ITER blanket EHF FW panel loaded by 5 MW/m2 peak heat flux.
Keywords :
Plasma facing component , EHF first wall , Blanket system , Blanket module , Hydraulic analysis , Thermal analysis , FW beam , FW fingers
