Title of article :
Design update, thermal and fluid dynamic analyses of the EU-HCPB TBM in vertical arrangement
Author/Authors :
Cismondi، نويسنده , , F. and Kecskés، نويسنده , , S. and Ilic، نويسنده , , M. and Légrلdi، نويسنده , , G. and Kiss، نويسنده , , B. and Bitz، نويسنده , , O. and Dolensky، نويسنده , , B. and Neuberger، نويسنده , , Francis H. and Boccaccini، نويسنده , , L.V. and Ihli، نويسنده , , T.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2009
Abstract :
In the frame of the activities of the EU Breeder Blanket Programme and of the Test Blanket Working Group of ITER, the Helium Cooled Pebble Bed Test Blanket Module (HCPB TBM) is developed in Forschungszentrum Karlsruhe (FZK) to investigate DEMO relevant concepts for blanket modules.
ree main functions of a blanket module (removing heat, breeding tritium and shielding sensitive components from radiation) will be tested in ITER using a series of four TBMs, which are irradiated successively during different test campaigns. Each HCPB TBM will be installed, with a vertical orientation, into the vacuum vessel connected to one equatorial port. As the studies performed up to 2006 in FZK concerned a horizontal orientation of the HCPB TBM, a global review of the design is necessary to match with the new ITER specifications.
iminary version of the new vertical design is proposed extrapolating the neutronic analysis performed for the horizontal HCPB TBM. An overview of the new HCPB TBM vertical designs, as well as the preliminary thermal and fluid dynamic analyses performed for the validation of the design, are presented in this paper. A critical review of the results obtained allows us, in the conclusion, to prepare a plan for the future detailed analyses of the vertical HCPB TBM.
Keywords :
Helium cooled pebble bed , Test blanket module , Finite elements
Journal title :
Fusion Engineering and Design
Journal title :
Fusion Engineering and Design