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Oriol COSTA Garrido

Research Associate

Jožef Stefan Institute
Jamova cesta 39
SI-1000 Ljubljana
Slovenia

Phone: +386 1 5885 290
Fax: +386 1 5885 377
E-mail: oriol.costa@ijs.si

 

 

 

 

 

 

 

Research Interests

  • Probabilistic fracture mechanics, structural mechanics, integrity assessment, fatigue life prediction
  • Thermal fatigue, pressurized thermal shock, leak-before-break, active damage mechanisms
  • Nuclear engineering and safety
  • Heat transfer, thermal energy
  • Refrigeration systems

Education

Awards

Co-authored Awards

Professional Experience

  • 2019-now : Research associate at the Reactor Engineering Division, Jožef Stefan Institute, Ljubljana, Slovenia.
  • 2018-2019: Postdoctoral fellow at the Laboratory for Nuclear Materials, Paul Scherrer Institut, Villigen, Switzerland. Research in the field of probabilistic fracture mechanics applied to reactor pressure vessel and primary piping integrity under pressurized thermal shock and active damage mechanisms.
  • 2009-2018: Research assistant at the Reactor Engineering Division, Jožef Stefan Institute, Ljubljana, Slovenia. Research in the fields of structural mechanics and thermal fatigue related to nuclear safety. Involved in international and domestic projects related to research and consultancy in the nuclear safety and engineering fields.
  • 2006-2009: Chief engineer at Taller de Fred, S.L., Barcelona, Spain. Directing the technical office, coordinating projects and workshop. Supervising two engineers and eleven co-workers divided in three departments: industrial refrigeration, catering-trade refrigeration and air conditioning.
  • 2001-2005: Technical organizer at Taller de Fred, S.L., Barcelona, Spain. Managing maintenance schedules of installations. Responsible of the workshop for the assembly of cooling stations and condensing units.

Selected Publications

The full list of publications is maintained by COBISS. Links to publications use the Digital Object Identifier System DOI.

Scopus Author ID: 56122449100.
ORCID: 0000-0001-7616-4405.

Articles in SCI Journals

J09 Costa Garrido, Oriol, Končar, Boštjan, Brown, Richard, Bachmann, Christian. Pre-conceptual design of DEMO upper port duct bellows. Fus. Eng. Des. 2018, vol. 136, pp. 1130-1134.
doi: 10.1016/j.fusengdes.2018.04.088. [COBISS.SI-ID 31359527]
J08 Costa Garrido, Oriol, El Shawish, Samir, Cizelj, Leon. Assessment of thermal fatigue predictions of pipes with spectral methods. ASME J. of Nuclear Rad. Sci. 2017, vol. 3, pp. 041001.
doi: 10.1115/1.4036736. [COBISS.SI-ID 30660903]
J07 Costa Garrido, Oriol, El Shawish, Samir, Cizelj, Leon. Comments on “Study of the quantitative assessment method for high-cycle thermal fatigue of a T-pipe under turbulent fluid mixing based on the coupled CFD-FEM method and the rainflow counting method” [Y. Zhang, T. Lu, Nucl. Eng. Des. 309 (2016) 175–196. doi:10.1016/j.nucengdes.2016.09.021]. Nucl. Eng. Des. 2017, vol. 318C, pp. 274-275.
doi: 10.1016/j.nucengdes.2016.11.017. [COBISS.SI-ID 30056487]
J06 Costa Garrido, Oriol, El Shawish, Samir, Cizelj, Leon. Uncertainties in the thermal fatigue assessment of pipes under turbulent fluid mixing using an improved spectral loading approach. Int. J. of Fatigue. 2015, vol. 82, pp. 550-560.
doi: 10.1016/j.ijfatigue.2015.09.010. [COBISS.SI-ID 28868903].
J05 Costa Garrido, Oriol, El Shawish, Samir, Cizelj, Leon. Stress assessment in piping under synthetic thermal loads emulating turbulent fluid mixing. Nucl. Eng. Des. 2015, vol. 283, pp. 114-130.
doi: 10.1016/j.nucengdes.2014.10.016. [COBISS.SI-ID 28134183].
J04 Costa Garrido, Oriol, El Shawish, Samir, Cizelj, Leon. A novel approach to generate random surface thermal loads in piping. Nucl. Eng. Des. 2014, vol. 273, pp. 98-109.
doi: 10.1016/j.nucengdes.2014.02.027. [COBISS.SI-ID 27652903].
J03 Costa Garrido, Oriol, Cizelj, Leon, El Shawish, Samir. The role of the axial heat fluxes in the thermal fatigue assessment of piping. Nucl. Eng. Des. 2013, vol. 261, pp. 382-393.
doi: 10.1016/j.nucengdes.2013.01.024. [COBISS.SI-ID 26591527].
J02 Costa Garrido, Oriol, Tiselj, Iztok, Cizelj, Leon. Depressurization of vertical pipe with temperature gradient modeled with WAHA code. Sci. Technol. Nucl. Install. 2012, vol. 2012, pp. 951923-1-951923-9.
doi: 10.1155/2012/951923. [COBISS.SI-ID 26147367].
J01 Costa Garrido, Oriol, Cizelj, Leon, Simonovski, Igor. Modular 3-D solid finite element model for fatigue analyses of a PWR coolant system. Nucl. Eng. Des. 2012, vol. 246, pp. 115-122.
doi: 10.1016/j.nucengdes.2011.06.038. [COBISS.SI-ID 24910631].

Scientific Conference Contributions

C17
Costa Garrido, Oriol, Kromar, Nejc, El Shawish, Samir, Cizelj, Leon. Development of a T-junction Structural Model in Abaqus for Efficient Thermo-Mechanical Analyses Using Detailed CFD Data. In: 29th International Conference Nuclear Energy for New Europe 2020, Portorož, Slovenia, September 7-10. Conference proceedings.
[COBISS.SI-ID 47111683]. (Direct Link)
C16 Costa Garrido, Oriol, Niffenegger, Markus, Mora, Diego F., Mukin, Roman. Probabilistic Fracture Mechanics Analyses for Structural Integrity Assessment of Nuclear Components. In: 28th International Conference Nuclear Energy for New Europe 2019, Portorož, Slovenia, September 9-12. Conference proceedings.
[COBISS.SI-ID 33177639]. (Link to Proceedings)
C15 Costa Garrido, Oriol, El Shawish, Samir, Cizelj, Leon. Thermal fatigue assessment of nuclear piping under random loading. In: Third International Conference on Multiscale Computational Methods for Solids and Fluids, September 20-22, 2017, Faculty of Civil and Geodetic Engineering, Ljubljana, Slovenia. Proceedings: Multiscale Computational Methods for Solids and Fluids, Ibrahimbegovic, Adnan, Brank, Boštjan, Kozar, Ivica, pp. 134-137.
[COBISS.SI-ID 30791207]. (Link to Proceedings)
C14 Costa Garrido, Oriol, Končar, Boštjan, Brown, Richard, Bachmann, Christian. Effect of DEMO Load Cases on Rectangular Bellows Design. In: 26th International Conference Nuclear Energy for New Europe 2017, Bled, Slovenia, September 11-14. Conference proceedings.
[COBISS.SI-ID 31099175]. (Direct Link)
C13 Costa Garrido, Oriol, El Shawish, Samir, Cizelj, Leon. Effect of Power Spectral Density Profile on Fatigue Predictions of Pipes under Turbulent Fluid Mixing. In: 26th International Conference Nuclear Energy for New Europe 2017, Bled, Slovenia, September 11-14. Conference proceedings.
[COBISS.SI-ID 31096103]. (Direct Link)
C12 Costa Garrido, Oriol, Timperi, Antti, El Shawish, Samir, Cizelj, Leon. Comparison of Spectral Methods with CFD Simulation of Turbulent Fluid Mixing. In: Transactions of SMiRT-24, Structural Mechanics in Reactor Technology Conference 2017, BEXCO, Busan, South Korea, August 20-25.
[COBISS.SI-ID 30770471]. (Direct Link)
C11 Costa Garrido, Oriol, Cizelj, Leon. Life-time predictions accuracy of thermally fatigued pipes under turbulently mixing fluids. In: European Nuclear Conference - ENC2016, Warsaw, Poland, October 9-13, 2016. Conference proceedings.
[COBISS.SI-ID 29905959]. (Link to Ext.Abstracts)
C10 Costa Garrido, Oriol, El Shawish, Samir, Cizelj, Leon. Crack growth assessment in pipes under turbulent fluid mixing using an improved spectral loading approach and linear elastic fracture mechanics. In: 25th International Conference Nuclear Energy for New Europe 2016, Portorož, Slovenia, September 5-8. Conference proceedings.
[COBISS.SI-ID 30220839]. (Direct Link)
C09 Costa Garrido, Oriol, Cizelj, Leon. Probabilistic prediction of fatigue life of pipes under turbulent fluid mixing. In: The 24th International Conference of Nuclear Engineering (ICONE24), Charlotte, NC, USA, June 26-30, 2016. Conference proceedings.
[COBISS.SI-ID 29621543]. (Direct Link)
C08 Costa Garrido, Oriol, Končar, Boštjan, Košmrlj, Samo, Bachmann, Christian, Meszaros, Botond. Global thermal analysis of DEMO Tokamak. In: 24th International Conference Nuclear Energy for New Europe 2015, Portorož, Slovenia, September 14-17. Conference proceedings.
[COBISS.SI-ID 29173543]. (Direct Link)
C07 Costa Garrido, Oriol, El Shawish, Samir, Cizelj, Leon. Uncertainties in fatigue life assessment of pipes due to random thermal loads. In: 23rd International Conference Nuclear Energy for New Europe 2014, Portorož, Slovenia, September 8-11. Conference proceedings.
[COBISS.SI-ID 28324647]. (Direct Link)
C06 Costa Garrido, Oriol, El Shawish, Samir, Cizelj, Leon. Thermal stresses in pipes caused by randomly generated two-dimensional temperature fluctuations. In: 22nd International Conference Nuclear Energy for New Europe 2013, Bled, Slovenia, September 9-12. Conference proceedings.
[COBISS.SI-ID 27354407]. (Direct Link)
C05 Costa Garrido, Oriol, Tiselj, Iztok. Two-phase subcooled decompression under temperature gradient modeled with WAHA code. In: 21st International Conference Nuclear Energy for New Europe 2012, Ljubljana, Slovenia, September 5-7. Conference proceedings.
[COBISS.SI-ID 26393639]. (Direct Link)
C04 Costa Garrido, Oriol, Cizelj, Leon. Thermal fatigue assessment: a two-dimensional approach. In: 20th International Conference Nuclear Energy for New Europe 2011, Bovec, Slovenia, September 12-15. Conference proceedings.
[COBISS.SI-ID 25478951]. (Direct Link)
C03 Costa Garrido, Oriol, Cizelj, Leon, Simonovski, Igor. Modular 3-D solid finite element model for fatigue analyses of a PWR reactor coolant system. In: International Conference Nuclear Energy for New Europe 2010, Portorož, Slovenia, September 6-9. Conference proceedings.
[COBISS.SI-ID 24341543]. (Direct Link)
C02 Costa Garrido, Oriol, ŠTUMBERGER, Gorazd, VORŠIČ, Jože. Optimizing production of electric energy from renewable sources by differential evolution. In: International conference on renewable energies and power quality (ICREPQ'07), Sevilla, Spain, March 28-30 2007.
[COBISS.SI-ID 11239446]. (Direct Link)
C01 Costa Garrido, Oriol, ŠTUMBERGER, Gorazd, VORŠIČ, Jože. Optimizing operational diagrams of electric energy production units based on renewable energy sources. In: 15th International Expert Meeting Power Engineering, Maribor, Slovenia, May 9-11 2006.
[COBISS.SI-ID 10413590].

Co-authored Articles in SCI Journals

JC07 Benavides, Julio, Costa Garrido, Oriol, Jimenez, Gonzalo, Cizelj, Leon. Thermo-mechanical analysis of a nuclear spent fuel dry cask using CFD results in a FE code. Nucl. Eng. Des. 2021, vol. 384, pp. 111481.
doi: 10.1016/j.nucengdes.2021.111481. [COBISS.SI-ID 79905027].
JC06 Končar, Boštjan, Ovtar, Domen, Costa Garrido, Oriol, Angostinetti, Piero. Calorimeter conceptual design for Neutral Beam Injector of DTT - CFD optimisation and thermal stress analysis. Fus. Eng. Des. 2021, vol. 170, pp. 112469.
doi: 10.1016/j.fusengdes.2021.112469. [COBISS.SI-ID 56957443].
JC05 Končar, Boštjan, Costa Garrido, Oriol, Draksler, Martin, Herrmann, A., Kovačič, J., Ionita, C., Schrittwieser, R.. Analysis of thermal and structural responses of a new diagnostic probe to repeated exposure in ASDEX upgrade tokamak. Fus. Eng. Des. 2020, vol. 161, pp. 112047.
doi: 10.1016/j.fusengdes.2020.112047. [COBISS.SI-ID 35267331].
JC04
Mora, Diego F., Costa Garrido, Oriol, Mukin, Roman, Niffenegger, Markus. Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach. Eng. Frac. Mech. 2020, vol. 238, pp. 107258.
doi: 10.1016/j.engfracmech.2020.107258. [COBISS.SI-ID 26034435].
JC03 Končar, Boštjan, Costa Garrido, Oriol, Draksler, Martin, Brown, Richard, Coleman, Matti. Initial optimization of DEMO fusion reactor thermal shields by thermal analysis of its integrated systems. Fus. Eng. Des. 2017, vol. 125, pp. 38-49.
doi: 10.1016/j.fusengdes.2017.10.017. [COBISS.SI-ID 30903847].
JC02 Končar, Boštjan, Draksler, Martin, Costa Garrido, Oriol, Meszaros, Botond. Thermal radiation analysis of DEMO tokamak. Fus. Eng. Des. 2017, vol. 124, pp. 567-571.
doi: 10.1016/j.fusengdes.2017.03.134. [COBISS.SI-ID 30401575].
JC01 Simonovski, Igor, Cizelj, Leon, Costa Garrido, Oriol. The influence of the grain boundary strength on the macroscopic properties of a polycrystalline aggregate. Nucl. Eng. Des. 2013, vol. 261, pp. 362-370.
doi: 10.1016/j.nucengdes.2012.12.007. [COBISS.SI-ID 26488103].

Co-authored Scientific Conference Contributions

CC11 Benavides, Julio, Costa Garrido, Oriol, Jimenez, Gonzalo, Cizelj, Leon. Analisis Termomecanico de un Contenedor de Combustible Nuclear Gastado. In: Sociedad Nuclear Espanola (SNE) virtual meeting 2020, November 16-19.
[COBISS.SI-ID 41955075].
CC10 Benavides, Julio, Costa Garrido, Oriol, Jimenez, Gonzalo, Cizelj, Leon. Thermo-Mechanical Analysis of a Dry Storage System. In: 29th International Conference Nuclear Energy for New Europe 2020, Portorož, Slovenia, September 7-10. Conference proceedings.
[COBISS.SI-ID 47109891]. (Direct Link)
CC09 Končar, Boštjan, Ovtar, Domen, Costa Garrido, Oriol, Draksler, Martin, Agostinetti, Piero. Calorimeter design for Neutral Beam Injector of DTT – Thermo-hydraulic analysis. In: 29th International Conference Nuclear Energy for New Europe 2020, Portorož, Slovenia, September 7-10. Conference proceedings.
[COBISS.SI-ID 46906627]. (Direct Link)
CC08 Mora, Diego F., Costa Garrido, Oriol, Mukin, Roman, Niffenegger, Markus. Fracture Mechanics Analyses of Reactor Pressure Vessel under Pressurized Thermal Shock with TRACE Input Loads. In: 28th International Conference Nuclear Energy for New Europe 2019, Portorož, Slovenia, September 9-12. Conference proceedings.
[COBISS.SI-ID 33177895]. (Link to Proceedings)
CC07 Mukin, Roman, Clifford, Ivan, Costa Garrido, Oriol, Mora, Diego F., Niffenegger, Markus, Niceno, Bojan, Ferroukhi, H. Screening Analysis for Pressurized Thermal Shork (PTS) Transient Scenarios. In: Proceedings of the NURETH 18, Portland, OR, USA, August 18-22, 2019.
[COBISS.SI-ID 32591655]
CC06 Niffenegger, Markus, Costa Garrido, Oriol, Mora, Diego F., Qian, Guian, Mukin, Roman, Sharabi, M. Niceno, Bojan. Uncertainties in Pressurized Thermal Shock Analyses. In: Proceedings of the ASME 2019, Pressure Vessels and Piping Conference, Sant Antonio, TX, USA, July 14-19 (PVP2019-94076).
[COBISS.SI-ID 32592167]. (Direct Link)
CC05 Mora, Diego F., Mukin, Roman, Costa Garrido, Oriol, Niffenegger, Markus. Fracture Mechanics Analysis of a PWR Under PTS Using XFEM and Input from TRACE. In: Proceedings of the ASME 2019, Pressure Vessels and Piping Conference, Sant Antonio, TX, USA, July 14-19 (PVP2019-94019).
[COBISS.SI-ID 32592423]. (Direct Link)
CC04 Končar, Boštjan, Costa Garrido, Oriol, Draksler, Martin, Brown, Richard, Bachmann, Christian. Development of DEMO Thermal Shield Concept: Design Requirements and Expected Thermal Loads. In: 26th International Conference Nuclear Energy for New Europe 2017, Bled, Slovenia, September 11-14. Conference proceedings.
[COBISS.SI-ID 31099431]. (Direct Link)
CC03 Vavtar, Ingrid, Draksler, Martin, Končar, Boštjan, Costa Garrido, Oriol. The effect of multilayer insulation on thermal loading in DEMO Systems. In: 25th International Conference Nuclear Energy for New Europe 2016, Portorož, Slovenia, September 5-8.
[COBISS.SI-ID 30223911]. (Direct Link)
CC02 Simonovski, Igor, Oliver, Martin, Bourgeois, Myriam, Aït-Bachir, Malik, Szabolcs, Svávai, Beleznai, Robert, Costa Garrido, Oriol, Cizelj, Leon, Blasset, Sébastien, Jourden, Erwan, Cueto-Felgueroso García, Carlos, Lopez Quesada, Guillermo. J-Integral fracture toughness assessment of specimens containing dissimilar metal welds. In: Transactions of SMiRT-23, Structural Mechanics in Reactor Technology Conference 2015, Manchester, United Kingdom, August 10-14. Conference proceedings.
[COBISS.SI-ID 29198631]. (Direct Link)
CC01 Simonovski, Igor, Cizelj, Leon, Costa Garrido, Oriol. The influence of the grain boundary strength on the macroscopic properties of a polycrystalline aggregate. In: 20th International Conference Nuclear Energy for New Europe 2011, Bovec, Slovenia, September 12-15. Conference proceedings.
[COBISS.SI-ID 25478439]. (Direct Link)

 

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