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Recent research in advanced fast reactors and fuel cycle strategies in Spain
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 …
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 …
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
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 …
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 …
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 …
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.
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 …
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
A JIMÉNEZ-CARRASCOSA, N GARCÍA-HERRANZ… - revistanuclear.es
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 …
presenta como una potente herramienta para el estudio de la física de reactores gracias a …