The MOX Fuel Performance Analysis of ALFRED Core Using MCNPX Transport Code

Document Type : Original Article

Authors

1 Department of Basic & Medical Sciences, Faculty of Dentistry, Al Ryada University for Science & Technology

2 Department of Mathematics and Eng. Physics - Faculty of Engineering - Fayoum University

Abstract

The (300 MWth) pool type Advanced Lead-cooled Fast Reactor European De-monstrator (ALFRED) is an essential step in the evolution of the LFR technology developed to demonstrate the viability of the European Lead Fast Reactor (ELFR) of Generation-IV for use in the future commercial power plant. The ALFRED core consists of two radial zones, inner zone (IZ) and outer zone (OZ), with closed hexagonal Fuel Assemblies (FAs). The fuel is composed of MOX pel-lets with different fissile plutonium enrichment for inner and outer zones. Using MCNPX transport code, 3D model of ALFRED core has been designed to study the MOX fuel performance analysis of the ALFRED core and to simulate its oper-ation during a fuel cycle of a duration of 1825 effective full power days. The ob-tained results show good agreement with previous studies and confirm the ca-pability of the reactor ALFRED to achieve sustainability.

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Fayoum University Journal of Engineering
Volume 7, Issue 2
Special Issue, Selected papers from the Third International Conference on Advanced Engineering Technologies for Sustainable Development ICAETSD, held on 21-22 November 2023
2024
Pages 272-277

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