Analysis of Fuel Burn-up Calculations of 3600 MWth Sodium cooled Fast Reactor Core
- 5 May 2021
- journal article
- research article
- Published by Egypts Presidential Specialized Council for Education and Scientific Research in Arab Journal of Nuclear Sciences and Applications
- Vol. 54 (3), 1-7
- https://doi.org/10.21608/ajnsa.2021.58175.1434
Abstract
Fast spectrum reactors are essential for the future of nuclear energy. Therefore, there is a need for continuous research and development of the design and safety of current and future nuclear fast reactors. The aim of this work is to analyze the process of fuel burnup in a large scale (3600 MWth) Sodium cooled Fast Reactor (SFR) core. This design is called European Sodium Fast Reactor (ESFR). It is proposed in the 7th Framework Programme within the Euratom Framework. A new version (version 2.7) of Monte Carlo neutron transport code (MCNPX) was used to design a 3D model of the ESFR core to evaluate and analyze a number of burnup-relevant characteristics. These include the flux and power distributions across the ESFR core as well as the reactivity changes and fuel transmutation during burnup to take into account the changes in fuel composition during burnup. Obtained results can serve as up to date evaluation for the design and well allow for a detailed assessments of the fuel performance inside the ESFR core.Keywords
This publication has 5 references indexed in Scilit:
- Detailed neutronic study of the power evolution for the European Sodium Fast Reactor during a positive insertion of reactivityNuclear Engineering and Design, 2017
- Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarkingNuclear Engineering and Design, 2014
- Pre-conceptual thermal–hydraulics and neutronics studies on sodium-cooled oxide and carbide coresAnnals of Nuclear Energy, 2013
- Methods for Processing ENDF/B-VII with NJOYNuclear Data Sheets, 2010
- The design of the Prototype Fast Breeder ReactorNuclear Engineering and Design, 2006