ABOUT ESFR-SMART

To improve the public acceptance of nuclear power and secure its future role in Europe, the significantly higher safety of new reactors compared to traditional reactors has to be demonstrated. The 4-year ESFR-SMART project (European Sodium Fast Reactor Safety Measures Assessment and Research Tools), launched in September 2017 aims to enhance the safety of Generation-IV Sodium Fast Reactors (SFR), in particular the commercial-size European Sodium Fast Reactor (ESFR).

THE PROJECT IN VIDEO

The projects aims to achieve 5 specific objectives.

Produce new experimental data in order to support calibration and validation of the computational tools for each defence-in-depth level

Test and qualify new instrumentations to support their utilisation in the reactor protection system

Perform further calibration and validation of the computational tools for each defence-in-depth level to support safety assessments of Generation-IV SFRs, using the data produced in the project as well as selected legacy data

Select, implement and assess new safety measures for the commercial-size ESFR using the GIF methodologies, the FP7 CP-ESFR project legacy, the calibrated and validated codes, and being in accordance with the update of the European and international safety frameworks taking into account the Fukushima accident

Strengthen and link new networks, in particular the networks of European sodium facilities and of European students working on SFR technology

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Concept

The project will take the large-power (1500 MWe / 3600 MWt) sodium cooled fast reactor concept a step further, using the outputs of the SPX2, EFR and CP-ESFR projects and using the Generation-IV International Forum objectives as a target.

Compared to the traditional LWRs and SFRs, the new reactor should be able to reprocess its own and legacy waste, exclude fuel enrichment, be more reliable in operation, more environmentally-friendly, more affordable, and better protected against proliferation. Last but not least: the new reactor should be safer than traditional LWRs and SFRs. The implementation of this new safety level in the ESFR reactor concept is one of the main challenges that will tackled in the project.

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Background

ESNII, the European Sustainable Nuclear Industrial Initiative of SNETP, gives Fast Neutron Reactors (FNR) a high priority for the production of sustainable nuclear energy in Europe. Taking into account the significant European and international operational experience, the ESNII roadmap identified the Sodium Fast Reactor as the most mature technology to be implemented and considers the Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID) to be an SFR prototype. ASTRID is the Generation-IV system that is being developed in France as part of European and international industrial and R&D cooperation programmes, including ASTRID Research and Development Cooperation (ARDECo). Two alternative FNR technologies to be explored in the longer term are the Lead cooled Fast Reactor (LFR) and the Gas cooled Fast Reactor (GFR).

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NEWS & EVENTS

Ten new PhDs earned within the ESFR-SMART project

The European workshop on Magneto-hydrodynamics in liquid metal systems (MHD)

Happening soon – the European workshop on Magneto-hydrodynamics in liquid metal systems (MHD)!

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The European workshop on Magneto-hydrodynamics in liquid metal systems (MHD)

Happening soon – the European workshop on Magneto-hydrodynamics in liquid metal systems (MHD)!

Presentations from the Spring School are now available for download!

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RESOURCES

PUBLICATIONS

Use of similarity indexes to identify spatial correlations of sodium void reactivity coefficients, A. Jiménez-Carrascosa & N. García-Herranz
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Mapping of sodium void effect and Doppler constant in ESFR-SMART core with Monte Carlo code SERPENT and deterministic code ERANOS, J. Krepel & V. Raffuzzi
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ESFR SMART project Conceptual design of in-vessel core catcher, J. Guidez, A. Gerschenfeld, K. Mikityuk, J. Bodi, F. Alvarez-Velarde, P. Romojaro, U. Diaz-Chiron
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Diagnosis of the unresolved domain treatment in Monte Carlo transport calculations through the identification and modelling of criticality safety experiments, N. Garcia-Herranz, J. Rodriguez, A. Jimenez-Carrascosa, O. Cabellos
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Using active learning in hybrid learning environments, C. Demazière
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Evaluation of the ESFR end of cycle state and detailed analysis of spatial distributions of reactivity coefficients, U. Davies, M. Margulis, E. Shwageraus, E. Fridman, N. Garcia-Herranz, A. Jimenez-Carrascosa, O. Cabellos, R. Gregg
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Fast reactor multiphysics and uncertainty propagation within WIMS, B. Lindley, B. Tollit, P. Smith, A. Charles, R. Mason, T. Ware, R. Perry, J. Lavarenne, U. Davies, R. Gregg
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Using active learning in hybrid learning environments, C. Demazière
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Ablation of ice bloc by a hot water jet – Application to SFR safety, A. Lecoanet, N. Rimbert, M. Gradeck, F. Payot
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Modelling of batch-wise operation of European Sodium Fast Reactor and Breed&Burn Molten Salt Reactor, V. Raffuzzi – Thesis supervisors: K. Mikityuk & J. Krepel
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A 2-D correlation to evaluate fuel-cladding gap thermal conductance in mixed oxide fuel elements for sodium-cooled fast reactors, J. Lavarenne, E. Bubelis, S. Gicquel, J. Krepel, M. Lainet, B. Lindley, K. Mikityuk, C. Murphy, B. Perrin, W. Pfrang, A. Ponomarev, A. Schubert, E. Shwageraus, P. Van Uffelen
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Whole-core validation of the Superphénix reactor using WIMS11 and an investigation into a hybrid RZ-HEX SP3 calculation route, U. Davies, B. Lindley, B. Tollit, E. Shwageraus
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New measurements on (U,Pu)O2 properties within European projects: ESNII+ and ESFR-SMART, N. Chauvin, D. Staicu, D. Manara, P. Raison, Ph. M. Martin
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3D Modelling of a Superphénix Benchmark with SERPENT and PARCS for coupled simulation with PARCS/ATHLET code, R. Henry, A. Seubert
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Etude de l’ablation d’une paroi solide par un jet liquide, A. Lecoanet; N. Rimbert; F. Payot; M. Gradeck
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Generazione di griglie computazionali per la progettazione di componenti di reattori nucleari di IV generazione refrigerati a sodio, L. Spitilli
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ESFR-SMART core burnup calculation on radially infinite lattice with Monte-Carlo code, G. Tomic and J. Krepel
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About the impact of the Unresolved Resonance Region in Monte Carlo simulations of Sodium Fast Reactors, A. Jiménez-Carrascosa; E. Fridman; N. García-Herranz; F. Alvarez-Velarde; P. Romojaro; F. Bostelmann
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Analytical and Experimental Study of Condensation and Collapse of Steam Bubbles at high Jakob number, S. Mambelli; A. Ponomarev; Y. Sato; K. Mikityuk
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Benchmarking ATHLET against TRACE as applied to Superphenix start-up tests, V. A. Di Nora; E. Fridman; K. Mikityuk
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Hybrid stochastic-deterministic method of one-group cross-section generation applied to Sodium Fast Reactor, J. Bodi; A. Ponomarev; K. Mikityuk
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Status of new safety measures considered for European Sodium Fast Reactor in the ESFR-SMART project, J. Guidez; A. Rineiski; E. Girardi; K. Mikityuk; J. Bodi
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European Sodium Fast Reactor: innovative design of reactor pit aiming at suppression of safety vessel, J. Guidez; A. Gerschenfeld; E. Girardi; K. Mikityuk; J. Bodi; A. Grah
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Development of a thermomechanical analysis method as part of the ESFR-SMART EU project for the quantification of SFR core reactivity change due to core distortion, J. Bodi; A. Ponomarev; K. Mikityuk
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Horizon-2020 ESFR-SMART project on Sodium Fast Reactor Safety: status after 18 months, K. Mikityuk; F. Álvarez Velarde; L. Bankhead; E. Bubelis; N. Bukasa Kampata; L. Buligins; B. Carluec; N. Chauvin; C. Demaziere; E. Fridman; N. García Herranz; G. Gerbeth; E. Girardi; N. Girault; M. Gradeck; J. Guidez; W. Hering; J. Krepel; C. Latge; B. Lindley; C. Lombardo; F. Payot; A.Rineiski; E. Schwageraus; A. Seubert; H. Tsige-Tamirat
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Analysis of hypothetical unprotected loss of flow in Superphénix start-up core: sensitivity to modeling details, A. Ponomarev and K. Mikityuk
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Horizon-2020 ESFR-SMART project on SFR safety: status after first 15 months, K. Mikityuk; E. Girardi; J. Krepel; E. Bubelis; E. Fridman; A. Rineiski; N. Girault; F. Payot; L. Buligins; G. Gerbeth; N. Chauvin; C. Latge; J. Guidez
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Teaching Fast Reactors within the frame of European Union Projects, C. Latge; A. Vasile; K. Mikityuk; R. Garbil
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Assessment of SCALE capabilities for full core Monte Carlo burnup calculations of Sodium Fast Reactors, Carrascosa, Antonio Jiménez; García Herranz, Nuria (Thesis supervisor)
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Minor actinide balance reduction in ESFR-SMART, Marchetti, Marco; Rineiski, Andrei
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New safety measures proposed for European Sodium Fast Reactor in Horizon-2020 ESFR-SMART project, Guidez, Joel; Bodi, Janos; Mikityuk, Konstantin; Rineiski, Andrei; Girardi, Enrico
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Use of CAD models in ESFR-SMART EU project, Bodi, Janos; Mikityuk, Konstantin; Ponomarev, Alexander; Guidez, Joel
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A simplified numerical benchmark for pool-type Sodium Fast Reactors, Radman, Stefan; Fiorina, Carlo; Mikityuk, Konstantin; Putz, Andreas
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Numerical investigation of corium coolability in core catcher: sensitivity to modeling parameters, Guo, Liancheng; Rineiski, Andrei
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Creation of an OpenFOAM fuel performance class based on FRED and integration into the GeN-Foam multi-physics code, Fiorina, Carlo; Pautz, Andreas; Mikityuk, Konstantin
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Analytical and experimental study of chugging boiling instability: the CHUG project, MS Thesis by Mambelli, Simone
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Etude de l’ablation d’une surface solide par un jet chaud, Conference paper by Zacharie, Célien; Rimbert, Nicolas; Hadj Achour, Miloud; Payot, Frédéric; Lecoanet, Alexandre; Gradeck, Michel
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A new experimental R&D program associated with the corium jet impingement on the ASTRID core catcher sacrificial material, Conference paper by Payot, Frederic; Journeau, Christophe; Suteau, Christophe; Serre, Frederic; Gradeck, Michel; Rimbert, Nicolas; Lecoanet, Alexandre; Miassoedov, Alexei
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Core safety measures in ESFR-SMART, Conference paper by Rineiski, Andrei; Meriot, Clement; Marchetti, Marco; Krepel, Jiri
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New sodium fast reactor neutronics benchmark, Conference paper by Ponomarev, Alexander; Bednarova, Alzbeta; Mikityuk, Konstantin
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Proposal of new safety measures for European Sodium Fast Reactor to be evaluated in framework of Horizon-2020 ESFR-SMART project, Conference paper by Guidez, Joel; Rineiski, Andrei; Prêle, Gérard; Girardi, Enrico; Bodi, Janos; Mikityuk, Konstantin
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Development of a CAD model for the European Sodium Fast Reactor in view of using the thermal hydraulics code TRACE, MS Thesis by Bodi, Janos
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Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow, Conference paper by Mambelli, Simone; Mikityuk, Konstantin; Panadero, Anne-Laurene
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ESFR-SMART: new Horizon-2020 project on SFR safety, Conference paper by Mikityuk, Konstantin; Girardi, Enrico; Krepel, Jiri; Bubelis, Evaldas; Fridman, Emil; Rineiski, Andrei; Girault, Nathalie; Payot, Frederic; Buligins, Leonids; Gerbeth, Gunter; Chauvin, Nathalie; Latge, Christian; Garnier, Jean-Claude
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