A study on the feasibility of using Uranium Nitride (UN) fuel in Pressurized water reactors (PWR)

A study on the feasibility of using Uranium Nitride (UN) fuel in Pressurized water reactors (PWR)

MCNPX computer code is used to design a three-dimensional model for a typical Pressurized Water reactor (PWR) core. Uranium Nitride fuel (UN) was tested for the reactor and the results were compared with a typical UO2 fuel. Neutron spectrum, power distributions, plutonium isotopes productions, and k...

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Bibliographic Details
Main Author: Moustafa Aziz
Format: Article
Language:English
Published: Elsevier 2023-04-01
Series:Alexandria Engineering Journal
Subjects:
Nitride fuel (UN)
PWR reactor
MCNPX code
Monte Carlo method
Zirconium oxide (ZrO2)
Online Access:http://www.sciencedirect.com/science/article/pii/S1110016823000662

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