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.
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).
NEWS & EVENTS
Assessment of SCALE capabilities for full core Monte Carlo burnup calculations of Sodium Fast Reactors, Carrascosa, Antonio Jiménez; García Herranz, Nuria (Thesis supervisor)
Minor actinide balance reduction in ESFR-SMART, Marchetti, Marco; Rineiski, Andrei
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
Use of CAD models in ESFR-SMART EU project, Bodi, Janos; Mikityuk, Konstantin; Ponomarev, Alexander; Guidez, Joel
A simplified numerical benchmark for pool-type Sodium Fast Reactors, Radman, Stefan; Fiorina, Carlo; Mikityuk, Konstantin; Putz, Andreas
Numerical investigation of corium coolability in core catcher: sensitivity to modeling parameters, Guo, Liancheng; Rineiski, Andrei
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
Analytical and experimental study of chugging boiling instability: the CHUG project, MS Thesis by Mambelli, Simone
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
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
Core safety measures in ESFR-SMART, Conference paper by Rineiski, Andrei; Meriot, Clement; Marchetti, Marco; Krepel, Jiri
New sodium fast reactor neutronics benchmark, Conference paper by Ponomarev, Alexander; Bednarova, Alzbeta; Mikityuk, Konstantin
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
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
Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow, Conference paper by Mambelli, Simone; Mikityuk, Konstantin; Panadero, Anne-Laurene
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
D1.1.1 Definition of safety requirements
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