Thermal Analysis of the Blanket and Shield for the U.S. ITER Design
Fusion Science and Technology / Volume 19 / Number 3P2B / May 1991 / Pages 1546-1551
ITER / Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) / dx.doi.org/10.13182/FST91-A29561
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Thermal analyses for the U.S. inboard and outboard shield and first wall of ITER have been performed utilizing the nuclear heating results obtained from the neutronics calculations. Several radial build configurations of the shield have been thermally analyzed. Different routes for the coolant are investigated to reduce the maximum temperature in shielding material which in turn reduces thermal expansion effects during ITER operation. The maximum thermal stresses are within the prescribed limits for the shield material at the maximum operating temperatures.
