Publication: Analysis of neutronic parameters of the VVER-1200, PWR and TRIGA Mark II reactor
Abstract
Çalışmanın ilk kısmında PWR ve VVER-1200 yakıt demetlerini MCNP 6.1 kodunu kullanarak modelleyip kontrol çubuklarının yokluğunda aynı şartlar altında, farklı senaryolar ve yakıt demeti sıcaklıkları için simüle ederek elde ettiğimiz nötronik parametreleri karşılaştırdık. Bu çalışmayı oluşturan ikinci kısımda ise İstanbul Teknik Üniversitesi'nde bulunan TRIGA Mark II araştırma reaktörünün yakıt elemanını MCNP 6.1 kodunu kullanarak modelleyip reaktör seyir defterinden elde ettiğimiz bilgilere göre simüle ederek yakıt elemanındaki kritik kütlenin ortalama yanma değerini elde ettik.
In the first part of this study, we modeled PWR and VVER-1200 fuel assemblies using the MCNP 6.1 code and compared the neutronic parameters we obtained by simulating them for different scenarios and fuel assembly temperatures under the same conditions in the absence of control rods. In the second part of this study, we modeled the fuel element of the TRIGA Mark II research reactor at Istanbul Technical University using the MCNP 6.1 code and simulated it according to the information we obtained from the reactor logbook, and determined the average burnup value of the critical mass in the fuel element.
In the first part of this study, we modeled PWR and VVER-1200 fuel assemblies using the MCNP 6.1 code and compared the neutronic parameters we obtained by simulating them for different scenarios and fuel assembly temperatures under the same conditions in the absence of control rods. In the second part of this study, we modeled the fuel element of the TRIGA Mark II research reactor at Istanbul Technical University using the MCNP 6.1 code and simulated it according to the information we obtained from the reactor logbook, and determined the average burnup value of the critical mass in the fuel element.