Karlsruher Institut für Technologie


Manufacturing and testing of a mock-up for experimental investigation of heat transfer in the first wall of helium Cooled Test Blanket Module. Comparison with numerical modelling

Donnerstag, 26. Januar 2012, 14:00-16:00
KIT Campus Nord, INR, Bau 521, 2. OG, Raum 302
Abstract: The Helium-Cooled-Pebble-Bed Test Blanket Module (HCPB TBM) is one of two blanket concepts chosen in the Frame of the European Blanket Programme as a DEMO relevant blanket. This blanket module has as outer boundary a Helium cooled steel structure named the First Wall (FW). The heat removal from the FW is a peculiar case of heat transfer due to an extreme asymmetry of heat loads – heat flux on the plasma facing FW side is 4.5 times (in an excess case even 9 times) stronger than the one on FW inner side which faces breeding units. Preliminary 3D CFD results have shown that under such conditions the cooling of the first wall is significantly less effective than predicted by common heat transfer approaches. As a reliable heat removal from the first wall is of crucial importance for HCPB TBM design, an experimental verification of the aforementioned CFD results had been mandatory. For that purpose a test section named HETRA (HEat TRAnsfer) has been developed at the Institute for Neutron Physics and Reactor Technique. The HETRA test section involves one U-pass of the cooling channel in the first wall of HCPB TBM Version 1.1. The experimental tests are performed for TBM relevant conditions – test channel made of Eurofer steel, Helium coolant at pressure of 80bar and inlet temperature of 3000C and heat flux of 270kW/m2 at the channel side representing plasma facing side of the first wall. Test channels with hydraulically smooth and with hydraulically rough walls have been considered. In total 6 measuring series have been performed in which temperature of Eurofer channel walls has been measured at ~60 positions. For each measuring series 3D CFD analyses have been done using computer code STAR-CD. This presentation gives an overview of main activities performed within the HETRA framework: from the CAD design, manufacturing and assembling issues up to the operational details of conducted experimental runs. The results of investigations will be presented through the comparison of measured and computed data and an analysis of main heat transfer parameters.
Frau Dr. Milica Iliæ

Karlsruher Institut für Technologie, Campus Nord
Institut für Neutronenphysik und Reaktortechnik
Institut für Neutronenphysik und Reaktortechnik
Karlsruher Institut für Technologie (KIT) - Campus Nord
Hermann-von-Helmholtz-Platz 1
76344 Eggenstein-Leopoldshafen
E-Mail:ingeborg schwartzRez3∂kit edu