DSpace Repository

Neutronic Calculations for Certain Americium Mixed Fuels and Clads in a Boiling Water Reactor

Show simple item record

dc.contributor.author Düz, M.
dc.date.accessioned 2022-10-06T12:49:54Z
dc.date.available 2022-10-06T12:49:54Z
dc.date.issued 2021
dc.identifier.issn 2296598X (ISSN)
dc.identifier.uri http://hdl.handle.net/11616/71571
dc.description.abstract 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 × 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; keff, 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. © Copyright © 2021 Düz.
dc.source Frontiers in Energy Research
dc.title Neutronic Calculations for Certain Americium Mixed Fuels and Clads in a Boiling Water Reactor


Files in this item

Files Size Format View

There are no files associated with this item.

This item appears in the following Collection(s)

Show simple item record