Fissile fuel breeding in the ARIES-ST fusion reactor by using molten salt with UF4

$UF_4$ içeren eriyik tuz kullanarak 1000 $MW_{el}$ gücündeki ARIES-ST reaktöründe fisil yakıt üretimi incelenmiştir. Hesaplamalar tek boyutlu SCALE4.3 kodu yardımıyla yapılmıştır. Bu hibrid modelde, önemli miktarda fisil yakıt üretilebilecektir. Başlangıç şartlarındaki nötron başına fisil yakıt üretim oranı $^{239}Pu$=0.115'tir ve bu da 2740 MW'lik tam füzyon gücü altında 3558 kg $^{239}Pu$/yıl demektir. Trityum üretim oranı 1.14 olarak bulunmuştur ve bundan dolayı DT füzyon kaynağı için trityumun kendi kendine yeterli olması sağlanmaktadır.

UF4 içeren eriyik tuz kullanarak ARIES-ST füzyon reaktöründe fisil yakıt üretimi

Fissile fuel breeding in the ARIES-ST of the 1000 $MW_{el}$ power plant is investigated by using molten salt containing $UF_4$. 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 $^{239}Pu$ = 0.115 per incident neutron at start-up conditions, that corresponds to 3558 kg $^{239}Pu$/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.

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