Thermal Analysis Of ITER Central Thermal Shield Joints


Completed orders:

ITER Team (Garching, Germany) - International Thermonuclear Experimental Reactor


The main objective of the presented analysis is to evaluate an impact of the joint design on the TS shielding insulation performance. For this purpose the parametric analysis has been performed to study impact of the emissivity of the joint area (bare or silver coated) and the pitch between bolts on:
the VVTS and CTS joints area temperature state;
the maximal and average heat influx on to TFC via joint area.

The parametric analysis performed to study impact of the joint area design features of VVTS/TTS and CTS on their thermal insulation performance revealed that:

- a decrease of the bolt emissivity from 0.35 to 0.05 would cause a reduction of the local heat influx by ~ 1.5 times. An average heat flux is expected to be less affected.

- a decrease of the bolt pitch from 400 mm to 200 mm leads to reduction of the local heat influx to TFC in 1.35 times (from 0.42 to 0.31 W/m2) at the bolt emissivity of 0.05, in the same time an average heat flux to the TFC reduces negligibly.

- good thermal contact between the bush and the splice plate decreases drastically the temperature of the splice plate as well as a local influx to the TFC.

- local heat influxes to the TFC for all the studied options are below the stated limit of 40 W/m2.

- an average heat load on the TFC near the joints is up to 3.5 times higher than the "background" level (thermal radiation to the TFC from the TS panel at 80 К). However, this is below 1 W/m2 limit specified for all options.



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