The effect of different fuels and clads on neutronic calculations in a boiling water reactor using the Monte Carlo method
Küçük Resim Yok
Tarih
2020
Yazarlar
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
Nature Portfolio
Erişim Hakkı
info:eu-repo/semantics/openAccess
Özet
In this study, a Boiling Water Reactor (BWR) modeling was done for the reactor core divided into square lattice 8x8 type using the Monte Carlo Method. Each of the square lattices in the reactor core was divided into small square lattices 7x7 type in groups of four. In the BWR designed in this study, modeling was made on fuel assemblies at pin-by-pin level by using neptunium mixed fuels as fuel rod, Zr-2 and SiC as fuel cladding, H2O as coolant. In fuel rods were used NpO2 and NpF4 fuels at the rate of 0.2%-1% as neptunium mixed fuels. In this study, the effect on the neutronic calculations as k(eff), neutron flux, fission energy, heating of NpO2 and NpF4 fuels in 0.2%-1% rates, and Zr-2 and SiC clads were investigated in the designed BWR system. The three-dimensional (3-D) modelling of the reactor core and fuel assembly into the designed BWR system was performed by using MCNPX-2.7.0 Monte Carlo method and the ENDF/B-VII.0 nuclear data library.
Açıklama
Anahtar Kelimeler
Intranuclear-Cascade Calculation, Zircaloy-2, Operation, Fluids, Alloy
Kaynak
Scientific Reports
WoS Q Değeri
Q1
Scopus Q Değeri
Q1
Cilt
10
Sayı
1
