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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
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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
- Winner prize for the best presentation of relevant research in nuclear fields at the 10th ENEN PhD Event&Prize 2016, within the European Nuclear Conference-ENC2016, Warsaw, Poland, October 9-13, 2016. Contribution: Costa Garrido, Oriol, Cizelj, Leon. "Life-time predictions accuracy of thermally fatigued pipes under turbulently mixing fluids".
- Best poster in the student paper competition at the 24th International Conference of Nuclear Engineering (ICONE24), Charlotte, NC, USA, June 26-30, 2016. Contribution: Costa Garrido, Oriol, Cizelj, Leon. "Probabilistic Prediction of Fatigue Life of Pipes Under Turbulent Fluid Mixing".
Co-authored Awards
- Best poster at the International Conference Nuclear Energy for New Europe 2020, Portorož, Slovenia, September 7-10, 2020. Contribution: Benavides Rodriguez, Julio, Costa Garrido, Oriol, Jimenez, Gonzalo, Cizelj, Leon. "Thermo-mechanical analysis of a dry storage system".
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
| C20 |
O. Costa Garrido, N. Kromar, A. Prošek, L. Cizelj. Development of a 3D-RPV Finite Element Model
for Pressurized Thermal Shock Analyses. In: 31st International Conference Nuclear Energy for New Europe 2022, Portorož, Slovenia, September 12-15.
[COBISS.SI-ID 135014403]. (Direct Link) |
C19
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Costa Garrido, Oriol, Prošek, Andrej, Cizelj, Leon. Pressurized thermal shock preliminary analyses of a 2-loop pressurized water reactor under loss-of-coolant accident scenarios. In: 30th International Conference Nuclear Energy for New Europe 2021, Bled, Slovenia, September 6-9.
[COBISS.SI-ID 91490051]. (Direct Link) |
C18
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Costa Garrido, Oriol, Kromar, Nejc, El Shawish, Samir, Cizelj, Leon. Development of a T-junction Structural Model with cracks in Abaqus for Efficient Fracture Mechanics Analyses Using Detailed CFD Data. In: 30th International Conference Nuclear Energy for New Europe 2021, Bled, Slovenia, September 6-9.
[COBISS.SI-ID 91493635]. (Direct Link) |
C17
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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.
[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.
[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.
[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.
[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.
[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.
[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.
doi: 10.1115/ICONE24-60194. [COBISS.SI-ID 29621543] |
| 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.
[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.
[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.
[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.
[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.
[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.
[COBISS.SI-ID 24341543]. (Direct Link) |
| C02 |
Costa Garrido, Oriol, ŠTUMBERGER, Gorazd, VORŠIÄŒ, 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, VORŠIÄŒ, 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
| JC08 |
M. Zhou, O. Costa Garrido, S. Ma, N. Zhang. Numerical investigation of turbulent thermal stratification at a horizontally oriented 90° pipe-elbow with varied elbow radiuses. Int. J. Th. Sci. 2023, vol. 185, pp. 108092.
doi: 10.1016/j.ijthermalsci.2022.108092. [COBISS.SI-ID 134337027]. |
| 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
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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
| CC14 |
P. Tarfila, B. Koncar, O. Costa Garrido, G. Dose, F. Giorgetti, S. Roccella. Development Of A Thermohydraulic Model For DTT PFU. In: 31st International Conference Nuclear Energy for New Europe 2022, Portorož, Slovenia, September 12-15.
[COBISS.SI-ID 135022083]. (Direct Link) |
| CC13 |
Zarazovskii M., Costa Garrido O., et al., "State-of-the-art of WPS in RPV PTS analysis", Pressure Vessels & Piping Conference (PVP2022-83699), Las Vegas, Nevada, USA, 2022.
doi: 10.1115/PVP2022-83699. [COBISS.SI-ID 137307907]. |
| CC12 |
R. Tregoning, J. Wallace, A. Bouydo, O. Costa-Garrido, P. Dillström, X. Duan, K. Heckmann, Y-J. Oh, Y-B. Kim, Y. Kim, J. Kuutti, A. Mano, M. Niffenegger, P. Samohyl, P.K. Singh, E. Kurth-Twombly, S. Yang. "CSNI Leak-Before-Break Benchmark – Summary of Phase 1", 26th International Conference on Structural Mechanics in Reactor Technology (SMiRT 26), Division IX, Berlin/Potsdam, Germany, July 10-15, 2022.
[COBISS.SI-ID 144182531]. (Direct Link) |
| 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.
[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.
[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.
[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).
doi: 10.1115/PVP2019-94076. [COBISS.SI-ID 32592167] |
| 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).
doi: 10.1115/PVP2019-94019. [COBISS.SI-ID 32592423] |
| 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.
[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.
[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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Dr. Mohit Sharma ter sodelavci na Odseku za reaktorsko tehniko so opravili eksperiment turbulentnega prenosa... | | A single grain boundary parameter to characterize normal stress fluctuations in materials with elastic cubic grains | | Dr. Samir El Shawish in dr. Timon Mede z Odseka za reaktorsko tehniko na Institutu »Jožef Stefan« sta v sodelovanju z dr. Jeremyjem Hurom z Université Paris-Saclay, CEA (Francija) objavila znanstven... | | Modelling of premixed layer formation in stratified fuel-coolant configuration | | Janez Kokalj, dr. Mitja Uršič ter dr. Matjaž Leskovar, sodelavci Odseka za reaktorsko tehniko na Institutu »Jožef Stefan«, so objavil znanstveni članek »... | | Validation of a morphology adaptive multi-field two-fluid model considering counter-current stratified flow with interfacial turbulence damping | | Dr. Matej Tekavčič, sodelavec Odseka za reaktorsko tehniko na Institutu »Jožef Stefan«, je v sodelovanju z raziskovalci iz Inštituta za dinamiko tekočin, Helmholtz-Zentrum Dresden-Rossendorf (Nemčija) objavil zn... | |
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