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Preliminary Design Studies of a Cylindrical Experimental Hybrid Blanket with Deuterium-Tritium Driver

Sümer Şahin, Tawfik A. Al-Kusayer, Muhammad Abdul Raoof

Fusion Science and Technology / Volume 10 / Number 1 / Pages 84-99

July 1986

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The AYMAN research project has been initiated to formulate the main structure of a prototypical experimental fusion and fusion-fission (hybrid) reactor blanket in cylindrical geometry. This geometry is consistent with most of the current fusion and hybrid reactor design concepts in respect to neutronic considerations. In this project, the fusion chamber is simulated by a cavity with a diameter of ∼1.6 m inside a cylindrical blanket. Fusion neutrons of 14 MeV are produced by a movable target along the axis of the cylinder. The movable neutron source allows simulation of a line source for integral experiments, which is a result of the linear nature of the Boltzmann transport equation. The calculations have shown that a blanket with a 13-cm-thick natural UO2 fuel zone and a 17-cm-thick Li2O zone has a self-sustaining tritium breeding for the fusion driver. By an appropriate dispersion of the Li2O zone inside the graphite reflector, it became possible to decrease the neutron leakage out of the reflector by a factor of 2 to 3 in favor of tritium breeding performance.

 
 
 
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