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 projects aims to achieve 5 specific objectives.
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Produce new experimental data in order to support calibration and validation of the computational tools for each defence-in-depth level

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

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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

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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

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


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.


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).


2nd Project Meeting in Riga

The second ESFR-SMART project meeting took place in Riga (Latvia), from September 11 to 13 2018. After one year of work, it was a great opportunity for partners to meet and…

Safety measures WP1
WP1.1 set up the basis for safety measures

One of the key objectives of the ESFR-SMART project is to define new safety measures for the European Sodium Fast Reactor (ESFR) core and system in order to improve the reliability and…


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, JanosMikityuk, KonstantinRineiski, AndreiGirardi, Enrico
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Use of CAD models in ESFR-SMART EU project, Bodi, JanosMikityuk, KonstantinPonomarev, AlexanderGuidez, Joel
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A simplified numerical benchmark for pool-type Sodium Fast Reactors, Radman, StefanFiorina, CarloMikityuk, KonstantinPutz, Andreas
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Numerical investigation of corium coolability in core catcher: sensitivity to modeling parameters, Guo, LianchengRineiski, 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, CarloPautz, AndreasMikityuk, 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, CélienRimbert, NicolasHadj Achour, MiloudPayot, FrédéricLecoanet, AlexandreGradeck, 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, FredericJourneau, ChristopheSuteau, ChristopheSerre, FredericGradeck, MichelRimbert, NicolasLecoanet, AlexandreMiassoedov, 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, AlexanderBednarova, AlzbetaMikityuk, 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, JoelRineiski, AndreiPrêle, GérardGirardi, EnricoBodi, JanosMikityuk, 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, SimoneMikityuk, KonstantinPanadero, Anne-Laurene
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ESFR-SMART: new Horizon-2020 project on SFR safety, Conference paper by Mikityuk, KonstantinGirardi, EnricoKrepel, JiriBubelis, EvaldasFridman, EmilRineiski, AndreiGirault, NathaliePayot, FredericBuligins, LeonidsGerbeth, GunterChauvin, NathalieLatge, ChristianGarnier, Jean-Claude
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ESFR-SMART Project video

  • Scientific posters:



D3.1.6 Communication action plan

D1.1.1 Definition of safety requirements

D1.1.2 Specification of the new core safety measures

D2.3.1 Design guidelines for sodium loops

D2.3.2 Standard procedures for Na loop operation and measurements treatment methodologies

D3.1.1 New pedagogical approach to teaching about Generation-IV fast reactors

D3.1.2 Improvement of educational tools

D2.3.3 Review of sodium technologies and dedicated roadmap for R&D studies and synergies and communalities with other liquid metal systems

D3.1.7 Report on content and Delivery of Video

D2.3.4 Support to the students mobility program

D3.1.3 Synthesis of 6 Topical Workshops and Summer School

D3.1.4 Synthesis of research activities performed through MS and PhD studies


19 partners from 9 European countries will enhance the sodium cooled fast reactor concept during 48 months.

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