European Sodium Fast Reactor Safety Measures Assessment and Research Tools

Resultado final

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.

Publicaciones

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

Autores: W. Hering, J. Fuchs, A. Onea, S. Perez-Martin, Th. Schaub
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 8(1), 2022, ISSN 2332-8975
Editor: ASME
DOI: 10.1115/1.4052642

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

Autores: S. Ehster, L. Ammirabile, E. Bubelis, B. Carluec, J.B. Droin, E. Girardi
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 8(1), 2022, ISSN 2332-8975
Editor: ASME
DOI: 10.1115/1.4050766

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

Autores: A. Grah, H. Tsige-Tamirat, J. Guidez, A. Gerschenfeld, K. Mikityuk, J. Bodi, E. Girardi
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 23328983, 2022, ISSN 2332-8983
Editor: 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

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

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

Autores: 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
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 23328983, 2022, ISSN 2332-8983
Editor: 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

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

Autores: Antonio Jiménez-Carrascosa, Nuria García-Herranz
Publicado en: Nuclear Engineering and Technology, Edición 52/11, 2020, Página(s) 2442-2451, ISSN 1738-5733
Editor: 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

Autores: Jamond, C., Lopez, E. M., Chen, X.-N.,Girault, N., Gubernatis, P., Rineiski, A.
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 8(1), 2022, ISSN 2332-8975
Editor: ASME
DOI: 10.1115/1.4052489

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

Autores: E. Bubelis, M. Schikorr, K. Mikityuk
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 8(1), 2022, ISSN 2332-8975
Editor: ASME
DOI: 10.1115/1.4050563

Evaluation of sodium boiling models using KNS-37 LOF experiments

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

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

Autores: Baker, U., Margulis, M., Shwageraus, E., Fridman, E., Jiménez-Carrascosa, A., García-Herranz, N., Cabellos, O., Gregg, R., Krepel J.
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 23328983, 2022, Página(s) 11, ISSN 2332-8983
Editor: The American Society of Mechanical Engineers(ASME)
DOI: 10.1115/1.4052121

Analysis of ESFR decay heat removal systems in Protected Station Blackout

Autores: J. Bodi, A. Ponomarev, E. Bubelis, K. Mikityuk
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 8(1), 2022, ISSN 2332-8975
Editor: 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

Autores: Romojaro, P., Álvarez-Velarde, F., Cabellos, O., García-Herranz, N., Jiménez-Carrascosa, A.
Publicado en: Annals of Nuclear Energy, Edición 03064549, 2021, Página(s) 13, ISSN 0306-4549
Editor: 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

Autores: J. Guidez, J. Bodi, K. Mikityuk, E. Girardi
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 23328983, 2022, ISSN 2332-8983
Editor: The American Society of Mechanical Engineers (ASME)
DOI: 10.1115/1.4052589

Decay heat characterization for the European Sodium Fast Reactor

Autores: Jiménez-Carrascosa, A., García-Herranz, N., Krepel, J., Margulis, M., Baker U., Shwageraus E., Fridman E., Gregg R.
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 23328983, 2022, Página(s) 9, ISSN 2332-8983
Editor: The American Society of Mechanical Engineers (ASME)
DOI: 10.1115/1.4051798

Superphénix Benchmark Part I: Results of Static Neutronics

Autores: 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
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 23328983, 2022, Página(s) 25, ISSN 2332-8983
Editor: ASME
DOI: 10.1115/1.4051449

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

Autores: Th. Schaub, F. Arbeiter, W. Hering, R. Stieglitz
Publicado en: Experiments in Fluids, Edición 63:19, 2022, ISSN 1432-1114
Editor: Springer-Verlag GmbH Germany
DOI: 10.1007/s00348-021-03363-9

Superphénix Benchmark Part II: Transient Results

Autores: A. Ponomarev, K. Mikityuk, E. Fridman, V. A. Di Nora, E. Bubelis, M. Schikorr
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 23328975, 2022, ISSN 2332-8975
Editor: 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

Autores: Alexandre Lecoanet, Nicolas Rimbert, Michel Gradeck, Frédéric Payot
Publicado en: Entropie : thermodynamique – énergie – environnement – économie, Edición 1/4, 2020, ISSN 2634-1476
Editor: ISTE OpenScience
DOI: 10.21494/iste.op.2020.0519

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

Autores: J. Guidez, J. Bodi, K. Mikityuk, E. Girardi, B. Carluec
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 23328983, 2022, ISSN 2332-8983
Editor: 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

Autores: 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
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 8(1), 2022, ISSN 2332-8975
Editor: ASME
DOI: 10.1115/1.4050479

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

Autores: 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
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 23328983, 2022, ISSN 2332-8983
Editor: The American Society of Mechanical Engineers (ASME)
DOI: 10.1115/1.4048905

ESFR-SMART Core Safety Measures and Their Preliminary Assessment

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

ESFR SMART project conceptual design of in-vessel core catcher

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

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

Autores: Mambelli, Simone; Ponomarev, Alexander; Sato, Yohei; Mikityuk, Konstantin
Publicado en: ICAPP 19, Edición 2, 2019
Editor: ICAPP 19
DOI: 10.5281/zenodo.3324409

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

Autores: N. García-Herranz, A. Jiménez-Carrascosa
Publicado en: OECD/NEA WPEC SG-46 meeting, 2022
Editor: OECD/NEA

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

Autores: Lecoanet, Alexandre; Rimbert, Nicolas; Payot, Frederic; Gradeck, Michel
Publicado en: 24ème Congrès Français de Mécanique, Edición 2, 2019
Editor: 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

Autores: Krepel, Jiri; Raffuzzi, Valeria
Publicado en: Internationcal Conference on Physics of Reactor, PHYSOR 2020, March 29 -- April 2, 2020, University of Cambridge, UK, Edición 1, 2020
Editor: PHYSOR
DOI: 10.5281/zenodo.4260938

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

Autores: Alexander Ponomarev; Konstantin Mikityuk
Publicado en: ICONE27, Edición 1, 2019
Editor: ICONE27
DOI: 10.5281/zenodo.3262074

Using active learning in hybrid learning environments

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

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

Autores: 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
Publicado en: 9th European Commission Conference on Euratom Research and Training in Safety of Reactor Systems, Edición 2, 2017
Editor: FISA
DOI: 10.5281/zenodo.3322925

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

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

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

Autores: R. Henry, A. Seubert
Publicado en: 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
Editor: 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

Autores: Davies, Una; Lindley, Ben; Tollit, Brendan; Shwageraus, Eugene
Publicado en: International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering (M&C 2019, Edición 1, 2019
Editor: M&C 2019
DOI: 10.5281/zenodo.3541540

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

Autores: Guidez, Joel; Bodi, Janos; Mikityuk, Konstantin; Rineiski, Andrei; Girardi, Enrico
Publicado en: International Congress on Advances in Nuclear Power Plants (ICAP 2019), Edición 1, 2019
Editor: International Congress on Advances in Nuclear Power Plants (ICAP 2019)
DOI: 10.5281/zenodo.3323957

Using active learning in hybrid learning environments

Autores: Demazière, Christophe
Publicado en: Internationcal Conference on Physics of Reactor, PHYSOR 2020, March 29 -- April 2, 2020, University of Cambridge, UK, Edición 1, 2020
Editor: 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

Autores: Garcia-Herranz, Nuria; Rodríguez, J.; Jiménez-Carrascosa, Antonio; Cabellos, Oscar
Publicado en: Internationcal Conference on Physics of Reactor, PHYSOR 2020, March 29 -- April 2, 2020, University of Cambridge, UK, Edición 1, 2020
Editor: PHYSOR
DOI: 10.5281/zenodo.4260651

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

Autores: A. Jiménez-Carrascosa, N. García-Herranz, O. Cabellos, F. Alvarez-Velarde, P. Romojaro
Publicado en: OECD/NEA WPEC SG-46 meeting, 2020
Editor: OECD/NEA

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

Autores: Chauvin, Nathalie; Staicu, Dragos; Manara, Dario; Raison, Philippe; Martin, Philippe
Publicado en: International Nuclear Fuel Cycle Conference, Edición 2, 2019
Editor: 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

Autores: Payot, Frederic; Journeau, Christophe; Suteau, Christophe; Serre, Frederic; Gradeck, Michel; Rimbert, Nicolas; Lecoanet, Alexandre; Miassoedov, Alexei
Publicado en: International Congress on Advances in Nuclear Power Plants (ICAPP 18), Edición 1, 2018
Editor: 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

Autores: Radman Stefan; Fiorina Carlo; Mikityuk Konstantin; Putz Andreas
Publicado en: ICONE 26 International Conference on Nuclear Engineering (ICONE), Edición 1, 2018
Editor: 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

Autores: Guidez, Joel; Bodi, Janos; Mikityuk, Konstantin; Rineiski, Andrei; Girardi, Enrico
Publicado en: Generation-IV International Forum Symposium, UIC, Edición 1, 2018
Editor: 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

Autores: Mambelli, Simone; Mikityuk, Konstantin; Panadero, Anne-Laurene
Publicado en: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development, Edición 1, 2017
Editor: 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

Autores: Rineiski, Andrei; Meriot, Clement; Marchetti, Marco; Krepel, Jiri
Publicado en: International Conference: Reactor Physics paving the way towards more efficient systems, Edición 1, 2018
Editor: 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

Autores: Guidez, Joel; Rineiski, Andrei; Prêle, Gérard; Girardi, Enrico; Bodi, Janos; Mikityuk, Konstantin
Publicado en: International Congress on Advances in Nuclear Power Plants (ICAPP 18), Edición 1, 2018
Editor: International Congress on Advances in Nuclear Power Plants (ICAPP 18)
DOI: 10.5281/zenodo.1309316

Minor actinide balance reduction in ESFR-SMART

Autores: Marchetti, M.; Rineiski, A.
Publicado en: International Conference for young scientists, specialists and post-graduates on Nuclear Reactor Physics 2018 (ICNRP-2018) ISSN: 1742-6588, 1742-6596, Edición 1, 2018
Editor: 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

Autores: 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
Publicado en: International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable, Development (FR17), Edición 1, 2017
Editor: 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

Autores: Bodi, Janos; Mikityuk, Konstantin; Ponomarev, Alexander; Guidez, Joel
Publicado en: Generation-IV International Forum Symposium, Edición 1, 2018
Editor: Generation-IV International Forum Symposium
DOI: 10.5281/zenodo.1479029

New sodium fast reactor neutronics benchmark

Autores: Ponomarev, Alexander; Bednarova, Alzbeta; Mikityuk, Konstantin
Publicado en: International Conference: Reactor Physics Paving The Way Towards More Efficient Systems (PHYSOR 2018), Edición 1, 2018
Editor: 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

Autores: Zacharie, Célien; Rimbert, Nicolas; Hadj Achour, Miloud; Payot, Frédéric; Lecoanet, Alexandre; Gradeck, Michel
Publicado en: Congrès de la société française de thermique (SFT), Edición 1, 2018
Editor: 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

Autores: Guo Liancheng; Rineiski Andrei
Publicado en: ICONE 26 International Conference on Nuclear Engineering (ICONE), Edición 1, 2018
Editor: 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

Autores: Fiorina Carlo; Pautz Andreas; Mikityuk Konstantin
Publicado en: ICONE 26 International Conference on Nuclear Engineering (ICONE), Edición 1, 2018
Editor: ICONE 26 International Conference on Nuclear Engineering (ICONE)
DOI: 10.5281/zenodo.1435696

Teaching Fast Reactors within the frame of European Union Projects

Autores: Latge, Christian; Vasile, Alfredo; Mikityuk, Konstantin; Garbil, Roger
Publicado en: Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2019), Edición 1, 2019
Editor: 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

Autores: 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
Publicado en: International Nuclear Fuel Cycle Conference GLOBAL, Seattle, WA, USA, September 22-26, 2019, 2019
Editor: GLOBAL
DOI: 10.5281/zenodo.3541656

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

Autores: Di Nora, Vincenzo Anthony; Fridman, Emil; Mikityuk, Konstantin
Publicado en: International Congress on Advances in Nuclear Power Plants - ICAPP2019, 12.-15.05.2019, Juan-les-Pins, France, Edición 1, 2019
Editor: ICAPP2019
DOI: 10.5281/zenodo.3324320

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

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

Fast Reactor Multiphysics and Uncertainty Propagation within WIMS

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

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

Autores: A. Jiménez-Carrascosa, N. García-Herranz
Publicado en: 5th SCALE Users’ Group Workshop, 2021
Editor: Oak Ridge National laboratory

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

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

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

Autores: Guidez, Joel; Gerschenfeld, Antoine; Grah, Aleksander; Tsige-Tamirat, Haileyesus; Mikityuk, Konstantin; Bodi, Janos; Girardi, Enrico
Publicado en: ICAPP 19, Edición 1, 2019
Editor: ICAPP 19
DOI: 10.5281/zenodo.3324074

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

Autores: A. Jiménez Carrascosa, N. García-Herranz, O. Cabellos
Publicado en: Revista Nuclear España, Edición 11372885, 2021, Página(s) 6, ISSN 1137-2885
Editor: Grupo SENDA

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

Autores: Raffuzzi, Valeria
Publicado en: ETH Zürich, Edición 1, 2019
Editor: ETH Zürich
DOI: 10.5281/zenodo.3561314

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

Autores: Carrascosa, Antonio Jiménez
Publicado en: Universidad Politécnica de Madrid, Edición 1, 2018
Editor: Universidad Politécnica de Madrid
DOI: 10.5281/zenodo.1691212

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

Autores: Mambelli, Simone
Publicado en: Eidgenossische Technische Hochschule Zurich, Edición 1, 2018
Editor: 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

Autores: Bodi, Janos
Publicado en: University of Birmingham, Edición 1, 2017
Editor: 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

Autores: Spitilli, Ludovico
Publicado en: UNIVERSITÀ DI BOLOGNA, Edición 2, 2019
Editor: UNIVERSITÀ DI BOLOGNA
DOI: 10.5281/zenodo.3480028

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