@article{article_97020, title={FISSILE FUEL BREEDING IN THE ARIES-ST FUSION REACTOR BY USING MOLTEN SALT WITH UF4}, journal={Gazi University Journal of Science}, volume={16}, pages={387–394}, year={2010}, author={Übeyli, Mustafa}, keywords={ARIES-ST fusion reactor, molten salt, fissile fuel breeding.}, abstract={<p class="MsoNormal" style="margin: 0cm 0cm 0pt; text-align: justify;"> <span style="font-size: small; font-family: Times New Roman;">ABSTRACT </span> </p> <p class="MsoNormal" style="margin: 0cm 0cm 0pt; text-align: justify;"> <span style="font-size: small; font-family: Times New Roman;">Fissile fuel breeding in the ARIES-ST of the 1000 MW <sub>el </sub> power plant is investigated by using molten salt containing UF <sub>4 </sub> Calculations are done with the aid of one-dimensional code of SCALE4.3. In this hybrid model, a substantial amount of fissile fuel can be produced with a fissile fuel breeding ratio of <sup>239 </sup> Pu = 0.115 per incident neutron at start-up conditions, that corresponds to 3558 kg <sup>239 </sup> Pu/year by a full fusion power of 2740 MW. Tritium breeding ratio is found as 1.14 so that tritium self-sufficiency is maintained for DT fusion driver. </span> </p> <p class="MsoNormal" style="margin: 0cm 0cm 0pt; text-align: justify;"> <span style="font-size: small; font-family: Times New Roman;">  </span> </p> <p class="MsoNormal" style="margin: 0cm 0cm 0pt; text-align: justify;"> <span style="font-size: small; font-family: Times New Roman;">Key Words: ARIES-ST fusion reactor, molten salt, fissile fuel breeding. </span> </p>}, number={2}, publisher={Gazi University}