European Sodium Fast Reactor Safety Measures Assessment and Research Tools

Risultati finali

D2.3.4. Support to the students mobility program

The deliverable will report on the main results of the students mobility program and review the different sodium fire extinguishing means as described in Task 234

D1.1.2. Specification of the new core safety measures

The deliverable will present the main steps of the optimization procedure and provide the new core specification as described in Task 1.1.2.

D1.1.1. Definition of safety requirements

As described in Task 1.1.1, the deliverable 1) describes the application of the GIF ISAM tool to the pre-conceptual and conceptual design phases of the ESFR, i.e., QSR and OPT; 2) defines the ESFR safety architecture; 3) defines the associated safety requirements in accordance with the European and international safety framework; 4) analyses the three main safety functions; 5) proposes the list of accidents to be analysed in WP1.2 -- 1.5.

D3.1.7. Report on content and Delivery of Video

The deliverable will report on the content of the video to promote the project and highlight its goals as described in Task 3.1.7.

D3.1.2. Improvement of educational tools

The deliverable will describe the outcome of the work on improvement of the educational tools related to the sodium systems as described in Task 312

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

The deliverable will summarize the main findings of the PhD and MS theses performed in frame of the project as described in Task 314

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

The deliverable will describe main outcome of the work on review, systematization and recommendations for the Generation-IV related education as described in Task 3.1.1.

D3.1.6. Communication action plan

A detailed communication action plan will described the activities as listed in Task 3.1.7.

D3.1.3. Synthesis of 6 Topical Workshops and Summer School

The deliverable will summarize the main conclusions and statistics of the workshops and summer school organized in frame of the project as described in Task 313

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

The deliverable will review and analyze selected elements of sodium technology as described in Task 2.3.2.

D2.3.1. Design guidelines for sodium loops

The deliverable will report on the rules to design sodium loops, on the safety related design options and recommendations as described in Task 2.3.1.

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

The deliverable will review existing technologies used in sodium experimental facilities and set priorities and actions to raise the TRL of these technologies as described in Task 2.3.3.

D3.1.5. Project website

The public website of the project will be maintained and updated during the whole project duration as described in Task 3.1.7.

Pubblicazioni

Experiment and codes to support safety assessments for sodium fast reactors (KASOLA, SOLTEC and KARIFA)

Autori: W. Hering, J. Fuchs, A. Onea, S. Perez-Martin, Th. Schaub
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 8(1), 2022, ISSN 2332-8975
Editore: ASME
DOI: 10.1115/1.4052642

Safety Method for the Preconceptual Phase of Sodium‐cooled Fast Reactors

Autori: S. Ehster, L. Ammirabile, E. Bubelis, B. Carluec, J.B. Droin, E. Girardi
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 8(1), 2022, ISSN 2332-8975
Editore: ASME
DOI: 10.1115/1.4050766

CFD analysis of the ESFR reactor pit cooling system in case of sodium leakage

Autori: A. Grah, H. Tsige-Tamirat, J. Guidez, A. Gerschenfeld, K. Mikityuk, J. Bodi, E. Girardi
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 23328983, 2022, ISSN 2332-8983
Editore: The American Society of Mechanical Engineers (ASME)
DOI: 10.1115/1.4051292

New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Autori: J. Guidez, J. Bodi, K. Mikityuk, E. Girardi, J. Bittan, A. Grah, H. Tsige-Tamirat, P. Romojaro, F. Álvarez-Velarde, B. Carluec
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 23328983, 2022, ISSN 2332-8983
Editore: The American Society of Mechanical Engineers (ASME)
DOI: 10.1115/1.4051723

Neutronic Analysis of the European Sodium Fast Reactor: Part II—Burnup Results

Autori: E. Fridman, F. Álvarez Velarde, P. Romojaro Otero, H. Tsige -Tamirat, A. Jiménez Carrascosa, N. García Herranz, F. Bernard, R. Gregg, U. Davies, J. Krepel, B. Lindley, S. Massara, S. Poumerouly, E. Girardi, K. Mikityuk
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 23328983, 2022, ISSN 2332-8983
Editore: The American Society of Mechanical Engineers (ASME)
DOI: 10.1115/1.4048765

A Review of Models for the Sodium Boiling Phenomena in Sodium-Cooled Fast Reactor Subassemblies

Autori: H. Tsige-Tamirat, S. Perez-Martin, W. Pfrang, M. Anderhuber, A. Gerschenfeld, L. Laborde, K. Mikityuk, C. Peniguel, S. Mimouni
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 8(1), 2022, ISSN 2332-8975
Editore: ASME
DOI: 10.1115/1.4051066

Autori: Antonio Jiménez-Carrascosa, Nuria García-Herranz
Pubblicato in: Nuclear Engineering and Technology, Numero 52/11, 2020, Pagina/e 2442-2451, ISSN 1738-5733
Editore: Korean Nuclear Society
DOI: 10.1016/j.net.2020.04.021

Reassessment of Computational Tools for the Modeling of Heat Transfer in a Molten UO2 Pool in Natural Convection

Autori: Jamond, C., Lopez, E. M., Chen, X.-N.,Girault, N., Gubernatis, P., Rineiski, A.
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 8(1), 2022, ISSN 2332-8975
Editore: ASME
DOI: 10.1115/1.4052489

Evaluation of the Passive Reactor Shutdown System Performance in European Sodium Fast Reactor

Autori: E. Bubelis, M. Schikorr, K. Mikityuk
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 8(1), 2022, ISSN 2332-8975
Editore: ASME
DOI: 10.1115/1.4050563

Evaluation of sodium boiling models using KNS-37 LOF experiments

Autori: S. Perez-Martin, M. Anderhuber, L. Laborde, N. Girault, C. Lombardo, L. Ammirabile, K. Mikityuk, S. Mimouni, C. Peniguel, W. Pfrang
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 8(1), 2022, ISSN 2332-8975
Editore: ASME
DOI: 10.1115/1.4050769

Evaluation of the ESFR End of Equilibrium Cycle State: Spatial Distributions of Reactivity Coefficients

Autori: Baker, U., Margulis, M., Shwageraus, E., Fridman, E., Jiménez-Carrascosa, A., García-Herranz, N., Cabellos, O., Gregg, R., Krepel J.
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 23328983, 2022, Pagina/e 11, ISSN 2332-8983
Editore: The American Society of Mechanical Engineers(ASME)
DOI: 10.1115/1.4052121

Analysis of ESFR decay heat removal systems in Protected Station Blackout

Autori: J. Bodi, A. Ponomarev, E. Bubelis, K. Mikityuk
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 8(1), 2022, ISSN 2332-8975
Editore: ASME
DOI: 10.1115/1.4052190

On the importance of target accuracy assessments and data assimilation for the co-development of nuclear data and fast reactors: MYRRHA and ESFR

Autori: Romojaro, P., Álvarez-Velarde, F., Cabellos, O., García-Herranz, N., Jiménez-Carrascosa, A.
Pubblicato in: Annals of Nuclear Energy, Numero 03064549, 2021, Pagina/e 13, ISSN 0306-4549
Editore: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2021.108416

Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project

Autori: J. Guidez, J. Bodi, K. Mikityuk, E. Girardi
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 23328983, 2022, ISSN 2332-8983
Editore: The American Society of Mechanical Engineers (ASME)
DOI: 10.1115/1.4052589

Decay heat characterization for the European Sodium Fast Reactor

Autori: Jiménez-Carrascosa, A., García-Herranz, N., Krepel, J., Margulis, M., Baker U., Shwageraus E., Fridman E., Gregg R.
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 23328983, 2022, Pagina/e 9, ISSN 2332-8983
Editore: The American Society of Mechanical Engineers (ASME)
DOI: 10.1115/1.4051798

Superphénix Benchmark Part I: Results of Static Neutronics

Autori: Ponomarev A., K. Mikityuk, L. Zhang, E. Nikitin, E. Fridman, F. Álvarez-Velarde, P. Romojaro, A. Jiménez-Carrascosa, N. García-Herranz, B. Lindley, U. Baker, A. Seubert, R. Henry
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 23328983, 2022, Pagina/e 25, ISSN 2332-8983
Editore: ASME
DOI: 10.1115/1.4051449

Forced and mixed convection experiments in a confined vertical backward facing step at low-Prandtl number

Autori: Th. Schaub, F. Arbeiter, W. Hering, R. Stieglitz
Pubblicato in: Experiments in Fluids, Numero 63:19, 2022, ISSN 1432-1114
Editore: Springer-Verlag GmbH Germany
DOI: 10.1007/s00348-021-03363-9

Superphénix Benchmark Part II: Transient Results

Autori: A. Ponomarev, K. Mikityuk, E. Fridman, V. A. Di Nora, E. Bubelis, M. Schikorr
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 23328975, 2022, ISSN 2332-8975
Editore: ASME
DOI: 10.1115/1.4051877

Ablation d’un bloc de glace transparente par un jet d’eau chaude – Application à la sûreté des RNR-Na

Autori: Alexandre Lecoanet, Nicolas Rimbert, Michel Gradeck, Frédéric Payot
Pubblicato in: Entropie : thermodynamique – énergie – environnement – économie, Numero 1/4, 2020, ISSN 2634-1476
Editore: ISTE OpenScience
DOI: 10.21494/iste.op.2020.0519

New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design

Autori: J. Guidez, J. Bodi, K. Mikityuk, E. Girardi, B. Carluec
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 23328983, 2022, ISSN 2332-8983
Editore: The American Society of Mechanical Engineers (ASME)
DOI: 10.1115/1.4051364

Burn-up Dependent Modelling of Fuel-to-clad Gap Conductance and Temperature Predictions for Mixed-oxide Fuel in the ESFR-SMART Core

Autori: J. Lavarenne, E. Bubelis, U. Davies, S. Gianfelici, S. Gicquel, J. Krepel, M. Lainet, B. Lindley, K. Mikityuk, C. Murphy, B. Perrin, W. Pfrang, A. Ponomarev, A. Schubert, E. Shwageraus, P.V. Uffelen
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 8(1), 2022, ISSN 2332-8975
Editore: ASME
DOI: 10.1115/1.4050479

Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results

Autori: E. Fridman, F. Álvarez Velarde, P. Romojaro Otero, H. Tsige-Tamirat, A. Jiménez Carrascosa, N. García Herranz, F. Bernard, R. Gregg, U. Davies, J. Krepel, S. Massara, S. Poumerouly, E. Girardi, K. Mikityuk
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 23328983, 2022, ISSN 2332-8983
Editore: The American Society of Mechanical Engineers (ASME)
DOI: 10.1115/1.4048905

ESFR-SMART Core Safety Measures and Their Preliminary Assessment

Autori: Rineiski, A., Mériot, C., Marchetti, M., Krepel, J., Coquelet-Pascal, Ch., Tsige-Tamirat, H., Álvarez-Velarde, F., Girardi, E., Mikityuk, K.
Pubblicato in: Journal of Nuclear Engineering and Radiation Science, Numero 8(1), 2022, ISSN 2332-8975
Editore: ASME
DOI: 10.1115/1.4052588

ESFR SMART project conceptual design of in-vessel core catcher

Autori: Guidez, Joel; Gerschenfeld, Antoine; Bodi, Janos; Mikityuk, Konstantin; Alvarez-Velarde, Francisco; Romojaro, Pablo; Diaz-Chiron, U.
Pubblicato in: Internationcal Conference on Physics of Reactor, PHYSOR 2020, March 29 -- April 2, 2020, University of Cambridge, UK, Numero 1, 2020
Editore: PHYSOR
DOI: 10.5281/zenodo.4260874

Analytical and Experimental Study of Condensation and Collapse of Steam Bubbles at High Jakob Number

Autori: Mambelli, Simone; Ponomarev, Alexander; Sato, Yohei; Mikityuk, Konstantin
Pubblicato in: ICAPP 19, Numero 2, 2019
Editore: ICAPP 19
DOI: 10.5281/zenodo.3324409

Sensitivity analyses of advanced reactors in the EC projects ESNIIplus and ESFR-SMART

Autori: N. García-Herranz, A. Jiménez-Carrascosa
Pubblicato in: OECD/NEA WPEC SG-46 meeting, 2022
Editore: OECD/NEA

Étude de l'ablation d'une paroi solide par un jet liquide

Autori: Lecoanet, Alexandre; Rimbert, Nicolas; Payot, Frederic; Gradeck, Michel
Pubblicato in: 24ème Congrès Français de Mécanique, Numero 2, 2019
Editore: CFM2019
DOI: 10.5281/zenodo.3537702

Mapping of sodium void effect and Doppler constant in ESFR-SMART core with Monte Carlo code SERPENT and deterministic code ERANOS

Autori: Krepel, Jiri; Raffuzzi, Valeria
Pubblicato in: Internationcal Conference on Physics of Reactor, PHYSOR 2020, March 29 -- April 2, 2020, University of Cambridge, UK, Numero 1, 2020
Editore: PHYSOR
DOI: 10.5281/zenodo.4260938

ANALYSIS OF HYPOTHETICAL UNPROTECTED LOSS OF FLOW IN SUPERPHÉNIX START-UP CORE: SENSITIVITY TO MODELING DETAILS

Autori: Alexander Ponomarev; Konstantin Mikityuk
Pubblicato in: ICONE27, Numero 1, 2019
Editore: ICONE27
DOI: 10.5281/zenodo.3262074

Using active learning in hybrid learning environments

Autori: C. Demazière
Pubblicato in: Conference on Teaching and Learning (Konferens om Undervisning och Lärande – KUL2020), Chalmers University of Technology, Gothenburg, Sweden, January 10, 2020 (2020)., 2020
Editore: KUL
DOI: 10.5281/zenodo.3607660

Horizon-2020 ESFR-SMART project on Sodium Fast Reactor Safety: status after 18 months

Autori: Mikityuk, Konstantin; Alvarez Velarde, Francisco; Bankhead, Lucy; Bubelis, Evaldas; Bukasa Kampata, Niclette; Buligins, Leonids; Carluec, Bernard; Chauvin, Nathalie; Demaziere, Christophe; Fridman, Emil; García Herranz, Nuria; Gerbeth, Gunter; Girardi, Enrico; Girault, Nathalie; Gradeck, Michel; Guidez, Joel; Hering, Wolfgang; Krepel, Jiri; Latge, Christian; Lindley, Ben; Lombardo, Calogera; Payo
Pubblicato in: 9th European Commission Conference on Euratom Research and Training in Safety of Reactor Systems, Numero 2, 2017
Editore: FISA
DOI: 10.5281/zenodo.3322925

Evaluation of the ESFR end of cycle state and detailed analysis of spatial distributions of reactivity coefficients

Autori: Davies, Una; Margulis, Marat; Shwageraus, Eugene; Fridman, Emil; Garcia-Herranz, Nuria; Jimenez-Carrascosa, Antonio; Cabellos, Oscar; Gregg, Robbie; Krepel, Jiri
Pubblicato in: Internationcal Conference on Physics of Reactor, PHYSOR 2020, March 29 -- April 2, 2020, University of Cambridge, UK, Numero 1, 2020
Editore: PHYSOR
DOI: 10.5281/zenodo.4260497

3-D Modelling of a Superphénix Benchmark with SERPENT and PARCS for coupled simulation with PARCS/ATHLET code

Autori: R. Henry, A. Seubert
Pubblicato in: International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering (M&C 2019), Portland Marriott Downtown Waterfront, Portland, Oregon USA, August 25-29, 2019, 2019
Editore: M&C2019
DOI: 10.5281/zenodo.3541503

Whole-core validation of the Superphénix reactor using WIMS11 and an investigation into a hybrid RZ-HEX SP3 calculation route

Autori: Davies, Una; Lindley, Ben; Tollit, Brendan; Shwageraus, Eugene
Pubblicato in: International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering (M&C 2019, Numero 1, 2019
Editore: M&C 2019
DOI: 10.5281/zenodo.3541540

Status of new safety measures considered for European Sodium Fast Reactor in the ESFR-SMART project

Autori: Guidez, Joel; Bodi, Janos; Mikityuk, Konstantin; Rineiski, Andrei; Girardi, Enrico
Pubblicato in: International Congress on Advances in Nuclear Power Plants (ICAP 2019), Numero 1, 2019
Editore: International Congress on Advances in Nuclear Power Plants (ICAP 2019)
DOI: 10.5281/zenodo.3323957

Using active learning in hybrid learning environments

Autori: Demazière, Christophe
Pubblicato in: Internationcal Conference on Physics of Reactor, PHYSOR 2020, March 29 -- April 2, 2020, University of Cambridge, UK, Numero 1, 2020
Editore: PHYSOR
DOI: 10.5281/zenodo.4260607

Diagnosis of the unresolved domain treatment in Monte Carlo transport calculations through the identification and modelling of criticality safety experiments

Autori: Garcia-Herranz, Nuria; Rodríguez, J.; Jiménez-Carrascosa, Antonio; Cabellos, Oscar
Pubblicato in: Internationcal Conference on Physics of Reactor, PHYSOR 2020, March 29 -- April 2, 2020, University of Cambridge, UK, Numero 1, 2020
Editore: PHYSOR
DOI: 10.5281/zenodo.4260651

Joint UPM and CIEMAT contribution: Progress on European Sodium Fast Reactor (ESFR)

Autori: A. Jiménez-Carrascosa, N. García-Herranz, O. Cabellos, F. Alvarez-Velarde, P. Romojaro
Pubblicato in: OECD/NEA WPEC SG-46 meeting, 2020
Editore: OECD/NEA

New measurements on (U,Pu)O2 properties within European projects: ESNII+ and ESFR-SMART

Autori: Chauvin, Nathalie; Staicu, Dragos; Manara, Dario; Raison, Philippe; Martin, Philippe
Pubblicato in: International Nuclear Fuel Cycle Conference, Numero 2, 2019
Editore: GLOBAL
DOI: 10.5281/zenodo.3541551

A new experimental R&D program associated with the corium jet impingement on the ASTRID core catcher sacrificial material

Autori: Payot, Frederic; Journeau, Christophe; Suteau, Christophe; Serre, Frederic; Gradeck, Michel; Rimbert, Nicolas; Lecoanet, Alexandre; Miassoedov, Alexei
Pubblicato in: International Congress on Advances in Nuclear Power Plants (ICAPP 18), Numero 1, 2018
Editore: International Congress on Advances in Nuclear Power Plants (ICAPP 18)
DOI: 10.5281/zenodo.1309374

A simplified numerical benchmark for pool-type Sodium Fast Reactors

Autori: Radman Stefan; Fiorina Carlo; Mikityuk Konstantin; Putz Andreas
Pubblicato in: ICONE 26 International Conference on Nuclear Engineering (ICONE), Numero 1, 2018
Editore: ICONE 26 International Conference on Nuclear Engineering (ICONE)
DOI: 10.5281/zenodo.1435697

New safety measures proposed for European Sodium Fast Reactor in Horizon-2020 ESFR-SMART project

Autori: Guidez, Joel; Bodi, Janos; Mikityuk, Konstantin; Rineiski, Andrei; Girardi, Enrico
Pubblicato in: Generation-IV International Forum Symposium, UIC, Numero 1, 2018
Editore: Generation-IV International Forum Symposium, UIC
DOI: 10.5281/zenodo.1479043

Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow

Autori: Mambelli, Simone; Mikityuk, Konstantin; Panadero, Anne-Laurene
Pubblicato in: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development, Numero 1, 2017
Editore: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
DOI: 10.5281/zenodo.1309195

Core safety measures in ESFR-SMART

Autori: Rineiski, Andrei; Meriot, Clement; Marchetti, Marco; Krepel, Jiri
Pubblicato in: International Conference: Reactor Physics paving the way towards more efficient systems, Numero 1, 2018
Editore: International Conference: Reactor Physics paving the way towards more efficient systems
DOI: 10.5281/zenodo.1313993

Proposal of new safety measures for European Sodium Fast Reactor to be evaluated in framework of Horizon-2020 ESFR-SMART project

Autori: Guidez, Joel; Rineiski, Andrei; Prêle, Gérard; Girardi, Enrico; Bodi, Janos; Mikityuk, Konstantin
Pubblicato in: International Congress on Advances in Nuclear Power Plants (ICAPP 18), Numero 1, 2018
Editore: International Congress on Advances in Nuclear Power Plants (ICAPP 18)
DOI: 10.5281/zenodo.1309316

Minor actinide balance reduction in ESFR-SMART

Autori: Marchetti, M.; Rineiski, A.
Pubblicato in: International Conference for young scientists, specialists and post-graduates on Nuclear Reactor Physics 2018 (ICNRP-2018) ISSN: 1742-6588, 1742-6596, Numero 1, 2018
Editore: International Conference for young scientists, specialists and post-graduates on Nuclear Reactor Physics 2018 (ICNRP-2018)
DOI: 10.5281/zenodo.1479056

ESFR-SMART: new Horizon-2020 project on SFR safety

Autori: 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
Pubblicato in: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development (FR17), Numero 1, 2017
Editore: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development (FR17)
DOI: 10.5281/zenodo.1309193

Use of CAD models in ESFR-SMART EU project

Autori: Bodi, Janos; Mikityuk, Konstantin; Ponomarev, Alexander; Guidez, Joel
Pubblicato in: Generation-IV International Forum Symposium, Numero 1, 2018
Editore: Generation-IV International Forum Symposium
DOI: 10.5281/zenodo.1479029

New sodium fast reactor neutronics benchmark

Autori: Ponomarev, Alexander; Bednarova, Alzbeta; Mikityuk, Konstantin
Pubblicato in: International Conference: Reactor Physics Paving The Way Towards More Efficient Systems (PHYSOR 2018), Numero 1, 2018
Editore: International Conference: Reactor Physics Paving The Way Towards More Efficient Systems (PHYSOR 2018)
DOI: 10.5281/zenodo.1309384

Etude de l'ablation d'une surface solide par un jet chaud

Autori: Zacharie, Célien; Rimbert, Nicolas; Hadj Achour, Miloud; Payot, Frédéric; Lecoanet, Alexandre; Gradeck, Michel
Pubblicato in: Congrès de la société française de thermique (SFT), Numero 1, 2018
Editore: Congrès de la société française de thermique (SFT)
DOI: 10.5281/zenodo.1312721

Numerical investigation of corium coolability in core catcher: sensitivity to modeling parameters

Autori: Guo Liancheng; Rineiski Andrei
Pubblicato in: ICONE 26 International Conference on Nuclear Engineering (ICONE), Numero 1, 2018
Editore: ICONE 26 International Conference on Nuclear Engineering (ICONE)
DOI: 10.5281/zenodo.1435703

Creation of an OpenFOAM fuel performance class based on FRED and integration into the GeN-Foam multi-physics code

Autori: Fiorina Carlo; Pautz Andreas; Mikityuk Konstantin
Pubblicato in: ICONE 26 International Conference on Nuclear Engineering (ICONE), Numero 1, 2018
Editore: ICONE 26 International Conference on Nuclear Engineering (ICONE)
DOI: 10.5281/zenodo.1435696

Teaching Fast Reactors within the frame of European Union Projects

Autori: Latge, Christian; Vasile, Alfredo; Mikityuk, Konstantin; Garbil, Roger
Pubblicato in: Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2019), Numero 1, 2019
Editore: Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2019)
DOI: 10.5281/zenodo.2658892

A 2-D correlation to evaluate fuel-cladding gap thermal conductance in mixed oxide fuel elements for sodium-cooled fast reactors

Autori: 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
Pubblicato in: International Nuclear Fuel Cycle Conference GLOBAL, Seattle, WA, USA, September 22-26, 2019, 2019
Editore: GLOBAL
DOI: 10.5281/zenodo.3541656

Benchmarking ATHLET against TRACE as applied to Superphénix start-up tests

Autori: Di Nora, Vincenzo Anthony; Fridman, Emil; Mikityuk, Konstantin
Pubblicato in: International Congress on Advances in Nuclear Power Plants - ICAPP2019, 12.-15.05.2019, Juan-les-Pins, France, Numero 1, 2019
Editore: ICAPP2019
DOI: 10.5281/zenodo.3324320

Development of an Artificial Neural Network for predicting spatial interdependencies of reactivity effects in Sodium Fast Reactors

Autori: A. Jiménez-Carrascosa, J. Krepel, A. Ponomarev, K. Mikityuk, N. García-Herranz
Pubblicato in: International Conference on Fast Reactors and Related Fuel Cycles FR22: Sustainable Clean Energy for the Future, 2022
Editore: IAEA

Fast Reactor Multiphysics and Uncertainty Propagation within WIMS

Autori: Lindley, Ben; Tollit, Brendan; Smith, Peter; Charles, Alan; Mason, Robert; Ware, Tim; Perry, Ray; Lavarenne, Jean; Davies, Una; Gregg, Robert
Pubblicato in: Internationcal Conference on Physics of Reactor, PHYSOR 2020, March 29 -- April 2, 2020, University of Cambridge, UK, Numero 6, 2020
Editore: PHYSOR
DOI: 10.5281/zenodo.4260387

How I use SCALE for my Work? (SCALE Open Mic)

Autori: A. Jiménez-Carrascosa, N. García-Herranz
Pubblicato in: 5th SCALE Users’ Group Workshop, 2021
Editore: Oak Ridge National laboratory

About the impact of the Unresolved Resonance Region in Monte Carlo simulations of Sodium Fast Reactors

Autori: Jiménez-Carrascosa, Antonio; Fridman, Emil; García-Herranz, Nuria; Alvarez-Velarde, Francisco; Romojaro, Pablo; Bostelmann, Frederike
Pubblicato in: ICAPP 2019 – International Congress on Advances in Nuclear Power Plants, 12.-15.05.2019, Juan-les-pins, France<br/>Proceedings of ICAPP 2019, Numero 1, 2019
Editore: ICAPP 19
DOI: 10.5281/zenodo.3324476

European Sodium Fast Reactor: innovative design of reactor pit aiming at suppression of safety vessel

Autori: Guidez, Joel; Gerschenfeld, Antoine; Grah, Aleksander; Tsige-Tamirat, Haileyesus; Mikityuk, Konstantin; Bodi, Janos; Girardi, Enrico
Pubblicato in: ICAPP 19, Numero 1, 2019
Editore: ICAPP 19
DOI: 10.5281/zenodo.3324074

Capacidades del sistema de códigos SCALE para el análisis de reactores rápidos avanzados

Autori: A. Jiménez Carrascosa, N. García-Herranz, O. Cabellos
Pubblicato in: Revista Nuclear España, Numero 11372885, 2021, Pagina/e 6, ISSN 1137-2885
Editore: Grupo SENDA

Modelling of batch-wise operation of European Sodium Fast Reactor and Breed&Burn Molten Salt Reactor

Autori: Raffuzzi, Valeria
Pubblicato in: ETH Zürich, Numero 1, 2019
Editore: ETH Zürich
DOI: 10.5281/zenodo.3561314

Assessment of SCALE capabilities for full core Monte Carlo burnup calculations of Sodium Fast Reactors

Autori: Carrascosa, Antonio Jiménez
Pubblicato in: Universidad Politécnica de Madrid, Numero 1, 2018
Editore: Universidad Politécnica de Madrid
DOI: 10.5281/zenodo.1691212

Analytical and experimental study of chugging boiling instability: the CHUG project

Autori: Mambelli, Simone
Pubblicato in: Eidgenossische Technische Hochschule Zurich, Numero 1, 2018
Editore: Eidgenossische Technische Hochschule Zurich
DOI: 10.5281/zenodo.1311464

Development of a CAD model for the European Sodium Fast Reactor in view of using the thermal hydraulics code TRACE

Autori: Bodi, Janos
Pubblicato in: University of Birmingham, Numero 1, 2017
Editore: University of Birmingham
DOI: 10.5281/zenodo.1309203

Generazione di griglie computazionali per la progettazione di componenti di reattori nucleari di IV generazione refrigerati a sodio

Autori: Spitilli, Ludovico
Pubblicato in: UNIVERSITÀ DI BOLOGNA, Numero 2, 2019
Editore: UNIVERSITÀ DI BOLOGNA
DOI: 10.5281/zenodo.3480028

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