CANDU reaktörlerinde $ThO_2$ ve $^{233}UO_2$ yakıt karışımı kullanımının incelenmesi

Bu çalışmada; $(Th+^{233}U)O_2$ yakıt karışımının CANDU reaktörlerinde kullanılabilirliği ve reaktör başarımına etkisi araştırılmıştır. Bunun için yakıt olarak %98 $ThO_2$ + %2 $^{233}UO_2$ yakıt karışımı kullanılmıştır. Nötronik veriler, tek boyutlu SCALE 4.4a nükleer hesaplama kodu yardımıyla elde edilmiştir. Reaktör kritiklik ve yanma derecesi değerleri tam güçte 20 yıl için hesaplanmıştır. Yapılan hesaplamalar sonucunda, reaktör kritikliğinin $k_{infty}$=~1,3 le başladığı ve 2. yıl sonundan itibaren 20 yıl boyunca $k_{infty}$=1,06 sınır değerinin üzerinde olduğu görülmüştür. Yanma derecesi 2. yıl sonunda 45.216 MW.D/MT ve 20. yılın sonunda 558.061 MW.D/MT gibi çok yüksek bir değer elde edilmiştir. Bu çalışma, toryumun çok düşük oranda (%2) fisil izotop karışımlarıyla CANDU reaktörlerinde yakıt olarak kullanılabileceğini göstermektedir.

Investigation utilization of $ThO_2$ and $^{233}UO_2$ fuel mixture in CANDU reactors

In this study, applicability of mixed $(Th+^{233}U)O_2$ fuel in the CANDU reactors and influence on the reactor performance was investigated. In order to achieve this purpose, mixed 98 % $ThO_2$ + 2 % $^{233}UO_2$ fuel was used. Neutronic data were calculated by using the aid of one dimensional computer system code of SCALE 4.4a. The criticality and the burn-up values of the reactor were been calculated by full power operation for a period of 20 years. The results showed that the during criticality started by $k_{infty}$=~1,3 and after the second year it remained above $k_{infty}$=1,06 for 20 years. Burn-up grades were calculated as 45.216 MW.D/MT after the second year and as 558.061 MW.D/MT after the twentieth year. This study showed that a few percent (2%) fissile izotopes mixed with thorium would make it possible to run the CANDU reactor.

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