Design and Analysis of First Wall High Heat Flux Component in Fusion Reactor

Abstract

First wall (FW) is the component of fusion reactor that faces the high energy neutron (14.1 MeV) that is emitted from the D-T reaction taking place in plasma. This high energy neutrons pass through the rst wall resulting in high Flux on the Fi rst wall as well can cause nuclear damage. Hence while designing rst wall one should take care of high energy neutron compatibility and proper cooling to remove heat deposition by neutrons. Here in the scope of this thesis, is to nd the best design of the rst wall that performs good heat transfer to remove the heat deposited by neutrons so that the rst wall does not get damaged for the life of the reactor. The main aim of this work is to nd the best out of available design of the cooling channel which gives the maximum heat transfer coe cient and minimum pumping power, used in rst wall of blanket module. To nd the best design, analysis is carried out with the di erent velocities of coolant and di erent area of cooling channel, and then optimisation is carried out with the Taguchi method. To get maximum heat removal rate helium is used as a coolant and helium passes across the First Wall cooling channels. Based on the surface heat ux and neutronics heat generation on FW, thermal hydraulic analyses have been carried out. After doing various analysis of rst wall cooling channel, and from the optimisation method it is cleared that with channel dimension of 15 + 15mm with velocity of 58 m/s satisfy the objective of achieving maximum heat transfer coe cient with minimum pumping power. Where theoretical value is 4533.46 W=m2:K and simulation result of HTC is 4091 W=m2:K , pumping power is 0.261 kW. While designing First wall one should take care of high energy neutron compatibility and proper cooling to remove heat deposition by neutrons. Thus have to design cooling channels that can sustain high heat Flux on First wall.