Neutronics and Photonics Calculations for the Tokamak Experimental Power Reactor

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Abstract
One-dimensional neutronic and photonic calculations have been carried out using the discrete-ordinates code ANISN to compare the nuclear performance of blanket and shield designs proposed for use in the Tokamak Experimental Power Reactor. The radiation transport was accomplished using cross-section data from the DLC-37 library (ENDF/B-IV). Nuclear heating and radiation damage rates were estimated using the latest available nuclear response functions. The nuclear analysis was performed for both nonbreeding and tritium-breeding blanket modules to compare the spatial variations of the radiation flux and energy distributions, nuclear heating, radiation damage, and tritium breeding. The nonbreeding blanket modules that utilize potassium plus Type 316 stainless steel or potassium only as the neutron and gamma-ray energy absorbing medium, and breeding blanket modules that use natural lithium as the fertile material were also evaluated as a function of the first wall cooling scheme.

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