Design and Development of Swiral Tube for Critical Heat Flux Applications

Abstract

In a plasma reactor, plasma facing components (PFC) will be subjected to critical heat flux (CHF). Therefore, the protection of these components is a very important issues for the design of SST-1 or ITER especially the divertor plates which will be subject to high heat loads.

Heat transfer enhancement techniques increase heat transfer coefficient which help to increase in heat load capacity, decrease temperature difference, decrease pumping power with a same size of heat area. Only drawbacks are: it increases pressure drop & cost.

There are many enhancement techniques available. For high heat flux in PFC, hypervapotron and swirl tube are compared. After comparing, the optimum option for cooling of PFC is swirl tube. Its design depends upon parameters like twist ratio, tape thickness, tape width etc.

Design for CHF = 0.3 MW/m2, the analytical data obtained are compared with those obtained from ANSYS result data. A comparison was based on equal CHF, flow velocity and inlet fluid temperature. There are increase in heat transfer coefficient and pressure drop 168% and 519% respectively comparing with swirl tube and smooth tube. It could be used in different area of plasma reactor.