Neutronic investigation of the ARIES-ST fusion reactor by using molten salt with $ThF_4$

$ThF_4$ içeren eriyik tuz kullanarak 1000 $MW_el$ gücündeki ARIES-ST reaktörünün hibrid modellenmesi incelenmiştir. Hesaplamalar tek boyutlu SCALE4.3 kodu kullanılarak yapılmıştır. Trityum üretim oranı l .05'den büyüktür ve bundan dolayı DT füzyon kaynağı için trityumun kendi kendine yeterli olması sağlanmaktadır. Bu hibrid modelde, önemli miktarda fisil yakıt üretilebilecektir. Başlangıç şartlarındaki nötron başına fısil yakıt üretim oranı 233U = 0.123'tür ve bu da 2740 MW'lık tam füzyon gücü altında 3742 kg 233U/yıl demektir.

$ThF_4$ içeren eriyik tuz kullanılarak ARIES-ST füzyon reaktörünün nötronik olarak incelenmesi

A hybrid modeling of ARIES-ST of the 1000 $MW_el$ power plant is investigated by using molten salt containing $ThF_4$. Calculations are done by using one-dimensional code of SCALE4.3. Tritium breeding ratio is greater than 1.05 so that tritium self-sufficiency is maintained for DT fusion driver. In this hybrid model, a significant amount of fissile fuel can be produced with a fissile fuel breeding ratio of 233U = 0.123 per incident neutron at start-up conditions, which corresponds to 3742 kg 233U/year by a full fusion power of 2740 MW.

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