Recent research in advanced fast reactors and fuel cycle strategies in Spain

F Álvarez-Velarde, Ó Cabellos, H Galán… - … Engineering and Design, 2024 - Elsevier
One of the main drawbacks of current nuclear energy is the generation of high-level
radioactive waste. On the other hand, the composition of the used nuclear fuel would still …

[HTML][HTML] Analysis of sodium boiling initiated by unprotected loss of flow in European sodium fast reactor core with different subassembly designs

J Bodi, A Ponomarev, K Mikityuk - Nuclear Engineering and Design, 2022 - Elsevier
In this paper, an Unprotected Loss of Flow (ULOF) assessment has been performed on the
European Sodium Fast Reactor developed in the ESFR-SMART EU project. To conduct the …

Impact of thermal-hydraulic feedback and differential thermal expansion on European sodium-cooled fast reactor core power distribution

B Lindley, F Álvarez Velarde… - Journal of …, 2023 - asmedigitalcollection.asme.org
The objective of this paper is to quantify the coupling effect on the power distribution of
sodium-cooled fast reactors (SFRs), specifically the European SFR. Calculations are …

[PDF][PDF] Spatial interdependence of safety related effects in ESFR-SMART core

J Krepel, A Ponomarev… - … of International Conference …, 2022 - conferences.iaea.org
ESFR-SMART belongs to the family of Gen-IV sodium cooled reactors. For the
demonstration of its safety performance the detailed knowledge of selected safety related …

Methodologies for enhancing the neutronic assessment of Sodium-cooled Fast Reactors: from nuclear data to transient analysis

A Jiménez Carrascosa - 2023 - oa.upm.es
Resumen Sodium-cooled Fast Reactors (SFR) have been identifed as the most promising
technology among the Generation-IV nuclear systems. The European Sustainable Nuclear …

Measurement of the Reactivity Coefficients and Neutron Flux of the SLOWPOKE-2 Reactor Using OpenMC.

A El Mtili, O El Hajjaji, T El Bardouni… - International …, 2023 - search.ebscohost.com
This article aims to calculate and analyze the reactivity coefficients of a SLOWPOKE-2
reactor under different temperature conditions using the OpenMC code and two cross …

[PDF][PDF] CAPACIDADES DEL SISTEMA DE CÓDIGOS SCALE PARA EL ANÁLISIS DE REACTORES RÁPIDOS AVANZADOS

El sistema de códigos SCALE, desarrollado por Oak Ridge National Laboratory (ORNL), se
presenta como una potente herramienta para el estudio de la física de reactores gracias a …