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Oriol COSTA Garrido

Research Assistant

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

  • Thermal fatigue
  • Structural mechanics
  • Nuclear safety
  • Thermal energy
  • Refrigeration systems

Education

Awards

Professional Experience

  • Current 2009-: Research assistant at the Reactor Engineering Division, Jožef Stefan Institute, Slovenia.
  • 2006-2009: Chief Engineer in 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, cathering-trade refrigeration and air conditioning.
  • 2001-2005: Technical organizer in 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

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

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].
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].
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].
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]
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].
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].
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].
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].
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].
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].
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].
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].
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].
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]
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

JC3 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].
JC2 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].
JC1 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

CC4 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].
CC3 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].
CC2 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].
CC1 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].

 

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