Core Design and Neutronic Analysis of the European Sodium Fast Reactor With Metallic Fuel
Abstract The current ESFR (European Sodium Fast Reactor) design was proposed and in-depth evaluated in the frame of the past ESFR-SMART project. As a follow-up project, the ESFR-SIMPLE has been launched with the aim of challenging the current commercial-size ESFR design in terms of safety features and economic performance. Among the new safety measures to be developed and assessed in ESFR-SIMPLE, the current oxide fuel ESFR design will be challenged by a modified version of the core with metallic fuel. This intends to conclude on what types of benefits can be obtained with high-density fuel, under similar safety and design constraints. In this paper, the designing approach for enabling the use of metallic fuel in the current ESFR core is described and a preliminary neutronic evaluation is carried out. The optimal configuration is established through the optimization of key neutronic parameters aiming at the potential reduction of the plutonium inventory. The resulting core configuration serves as a basis for further safety assessment analyses, which will provide insight into the advantages and drawbacks of the two types of fuels.
Authors
- Antonio Jiménez-Carrascosa (ORCID: https://orcid.org/0000-0001-6155-2034)
- Nicolas Stauff (ORCID: https://orcid.org/0000-0001-6167-9326)
- E. Fridman
- Konstantin Mikityuk
- Alexander Ponomarev
- Aydın Karahan
Institutions
- Argonne National Laboratory (US)
- Helmholtz-Zentrum Dresden-Rossendorf (DE)
- Paul Scherrer Institute (CH)
Publication Details
- Published
- 2024-08-04
- DOI
- https://doi.org/10.1115/icone31-133069
- Primary Topic
- Nuclear reactor physics and engineering
- Type
- article
- Field-Weighted Citation Impact
- 0.00