Abstract
In fission reactors, neutron radiation is the main reason for the displacement of atoms in the crystalline lattice of the material. In this study, this damage is investigated on the fuel clad of the Bushehr reactor, which is Zr + 1%Nb. The MCNPX code is used to simulate the core of the reactor and find the highest neutron flux in the core of the reactor. Both the SRIM and SPECTER codes are used to study the neutron interaction with matter. The damage rate of the SRIM code is calculated in full cascade and quick damage modes, calculated as 2.05E−06 (dpa/s) and 1.06E−06 (dpa/s), respectively. Also, the damage rate in the SPECTER code is 1.0193E−06 (dpa/s), and the result has been compared with the SRIM code results. Using the calculated displacement per atom (dpa), the yield stress of the material, which is the resistance to the stresses, and the electrical resistivity of the material are calculated for 3 years of reactor operation. Both factors have increased over time, and the fuel clad lost its original function.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
