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344952

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

Article

Last updated: 24 Dec 2024

Subjects

-

Tags

Physics

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.

DOI

10.21608/fuje.2024.344952

Keywords

ALFRED, MCNP, MOX

Authors

First Name

Mohammed

Last Name

El-Alem

MiddleName

Ibrahim

Affiliation

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

Email

mohamed.elalem@rst.edu.eg

City

-

Orcid

-

First Name

Ahmed

Last Name

Abdel-Latif

MiddleName

M.

Affiliation

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

Email

-

City

-

Orcid

-

Volume

7

Article Issue

2

Related Issue

46380

Issue Date

2024-03-01

Receive Date

2024-03-08

Publish Date

2024-03-01

Page Start

272

Page End

277

Print ISSN

2537-0626

Online ISSN

2537-0634

Link

https://fuje.journals.ekb.eg/article_344952.html

Detail API

https://fuje.journals.ekb.eg/service?article_code=344952

Order

344,952

Type

Original Article

Type Code

651

Publication Type

Journal

Publication Title

Fayoum University Journal of Engineering

Publication Link

https://fuje.journals.ekb.eg/

MainTitle

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

Details

Type

Article

Created At

24 Dec 2024