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Neutronics Analysis for the First Wall and Shield of the D-3He Reactor ARIES-III

M. E. Sawan, L. A. El-Guebaly

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2069-2074

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30026

An efficient organic cooled low activation ferritic steel first wall and shield has been designed for the D-3He power reactor ARIES-III. The inboard shield is 65 cm thick and provides adequate magnet protection. The steel structure has a peak end-of-life damage of only 63 dpa and is expected to last for the whole reactor life. The total absorbed dose rate in the organic coolant is 1026 eV/s resulting in a radiolytic decomposition rate of 171 kg/hr. Tritium production leads to a release rate of 33.5 Ci/d and an acceptable off-site effluent dose < 1.3 mrem/yr.