Neutronic Calculations for Certain Americium Mixed Fuels and Clads in a Boiling Water Reactor
Küçük Resim Yok
Tarih
2021
Yazarlar
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
Frontiers Media Sa
Erişim Hakkı
info:eu-repo/semantics/openAccess
Özet
In this study, a Boiling Water Reactor (BWR) design was made using the Monte Carlo (MCNPX) method. The reactor core in the designed BWR system was divided into an 8 x 8 square lattice with a constant pitch of 30.48 cm. In this study, americium (Am), which is found in the minor actinidine (MA) of spent nuclear fuel known as nuclear waste from existing reactors, was used as fuel with the addition of oxygen and fluorine. In this study, AmO2 and AmF3 fuels at the rate of 0.02-0.1 % were used as Americium Mixed Fuels, and Zircaloy-2 (Zr-2), SiC, and VC were used as clad. Neutronic calculations for certain Americium Mixed Fuels and clads were compared in the designed BWR system. In the BWR system designed in the study; k(eff) , neutron flux, fission energy, heating, and depleted Am were calculated. The three-dimensional (3-D) modeling of 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
boiling water reactor, keff, neutron flux, fission energy, heating, MCNPX-2.7.0
Kaynak
Frontiers in Energy Research
WoS Q Değeri
Q3
Scopus Q Değeri
Q2
Cilt
9
