Advanced Inboard Shielding Design for Tokamak Fusion Reactors
Fusion Science and Technology / Volume 8 / Number 1P2A / July 1985 / Pages 1037-1042
Shielding Neutronic / Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) / dx.doi.org/10.13182/FST85-A40170
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The recent physics and technology advances in the field of high power density compact tokamak reactors have established the need for advanced inboard shielding design. This work presents the design of an optimal inboard shield and assesses the limits on the radiation effects in the magnets of a high wall loading (10 MW/m2) tokamak design. A new material, boron hydride, was identified as a potential shielding material and more optimum combinations of TiH2, B4C, and W were identified as well.
