Ta stran uporablja piškotke (za prikaz videoposnetkov, zemljevidov in enostavno deljenje vsebine z drugimi).
Z nadaljevanjem ogleda te strani se strinjate z njihovo uporabo.
Z uporabo piškotkov se strinjam / želim več informacij / ne strinjam

 
logo logo JavnostPartnerjiMediji

Username: Password:

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].

 

NOVICE
Nov raziskovalni program
Na javnem razpisu Agencije za raziskovalno dejavnost RS (ARRS) je bil sprejet nov raziskovalni program »Fuzijske tehnologije«. Raziskave, ki jih izvajajo raziskovalci, združeni v ...
ENEN in OECD/NEA sta podpisala sporazum o sodelovanju pri spodbujanju izobraževanja in usposabljanja za jedrske tehnologije
31. oktobra 2018 sta Evropska mreža za jedrsko izobraževanje (ENEN, www.enen.eu) in Agencija za jedrsko energijo (NEA, www.oecd-nea.org) pri Organiz...
NEA Steering Commitee Policy Debate on Knowledge Management in the Context of an Ageing Workforce, Pariz, Francija, 31.10.2018
Steering Committee je najvišji odbor, ki svetuje generalnemu direktorju OECD/NEA (nuclear Energy Agency). Sestavljajo ga visoki predstavniki vlad držav članic OECD/NEA, dostik...
Ad-hoc sestanek EURATOM programme committee fission configuration, Bruselj, Belgija, 9.10.2018
Programski odbor EURATOM sestavljajo predstavniki vseh držav članic Evropske skupnosti. Odbor svetuje in usmerja strokovne službe Evropske komisije pri pripravi in izvedbi razpisov raziskovalnih projektov na področju je...
Sestanek CROSSING projekta, Dresden, Nemčija, 25.10.-26.10., 2018
Združenje 18 nemških raziskovalnih centrov »Helmholtz Association« si prizadeva za krepitev skupnih raziskav v Evropi - zlasti v vzhodni, osrednji in južni Evropi - prek svojega novega programa financiranja "Helmholtz European Part...
Konferenca International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS)
  Konferenca International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS) redno poteka že več kot 20 let, in to doslej vedno v državah severo-vzhodne Azije: LR Kitajska ...
Sestanek ekspertov glede predloga OECD/NEA projekta ROSAU
Sestanek ekspertov glede predloga OECD/NEA projekta ROSAU, OECD/NEA, Pariz, Francija, 20.-21. 9. 2018 Organizacija za gospodarsko sodelovanje in razvoj - OECD (Organisation for Economic Co-operation...
Konferenca »2018 International Severe Accident Management Conference«, CNSC/CNL, Ottawa, Kanada, 15.-18. 10. 2018
Kanadska uprava za jedrsko varnost - CNSC (Canadian Nuclear Safety Commission) in Kanadski jedrski laboratoriji – CNL (Canadian Nuclear Laboratories) so skupaj organizirali mednarodno konferenco o obvladovanju težkih...
Mednarodna konferenca IAEA za pooblaščene izvedence za jedrsko varnost (TSO)
Mednarodna konferenca IAEA za pooblaščene izvedence za jedrsko varnost (TSO), Bruselj, Belgija, 15.-18. 10. 2018 Mednarodna konferenca za pooblaščene izvedence za jedrs...
Začetni sestanek projekta ASCOM in 8. sestanek ASTEC Users Club
Začetni sestanek projekta ASCOM in 8. sestanek ASTEC Users Club ASTEC je sistemski računalniški program, ki omogoča simulacijo vseh faz potencialne težke nesreče v lahkovodni jedrski elektrarni, od nastopa izlivne nezgode, preko d...
3. sestanek generalne skupščine projekta SOTERIA
3. sestanek generalne skupščine projekta SOTERIA, Helsinki, Finska, 9-10.10.2018 Projekt SOTERIA (»Safe long term operation of light water reactors based on improved understanding of r...
8. delovni sestanek projekta SESAME, TUD, Delft, Nizozemska
8. delovni sestanek projekta SESAME, TUD, Delft, Nizozemska Projekt SESAME je projekt, ki poteka v okviru evropskega projekta Horizon 2020. Glavni trije cilji projekta ...
Projektni sestanek NARSIS
Projektni sestanek NARSIS Karlsruhe, Nemčija, 18-20.9.2018 NARSIS (New Approach to Reactor Safety ImprovementS) je štiriletni evropski projekt okvirnega programa Obzorje 2020, katerega glavna cil...
Poletna delavnica sekcije JSP združenja ETSON
Poletna delavnica sekcije JSP združenja ETSON V okviru združenja pooblaščenih izvedencev za jedrsko varnost (ETSON) deluje tudi sekcija, ki je namenjena mlajšim sodelavcem članic z...
CFD4NRS - Computational Fluid Dynamics for Nuclear Reactor Safety
Računska dinamika tekočin zavarnost jedrskih reaktorjev - "Computational Fluid Dynamics for Nuclear Reactor Safety (CFD4NRS)", Šanghaj, Kitajska, 4.9.2018 – 6.9.2018 V z...
18th UIT Summer School on Advanced experimental techniques in heat and mass transfer
18th UIT Summer School on Advanced experimental techniques in heat and mass transfer   »UIT Summer school« je tečaj, ki ga organizira italijansko združenje strokovnjakov iz termodinamike UIT (Unione I...
Udeležba na tečaju projekta SOTERIA, PUV – Politehniška Univerza Valencia, Španija, 3.-7.9.2018
Udeležba na tečaju projekta SOTERIA, PUV – Politehniška Univerza Valencia, Španija, 3.-7.9.2018 Projekt SOTERIA (»Safe long term operation of light water reactors based o...
Delavnica v okviru projekta »Analysis to Support Implementation in Practice of Articles 8a-8c of Directive 2014/87/Euratom«
Delavnica v okviru projekta »Analysis to Support Implementation in Practice of Articles 8a-8c of Directive 2014/87/Euratom« Direktorat za energijo pri Evropski komisiji je pri združen...
Srečanje CSARP/MCAP ter delavnica za uporabnike programa MELCOR
Srečanje CSARP/MCAP ter delavnica za uporabnike programa MELCOR, Rockville, Maryland, ZDA, 4. – 15. 6. 2018 Po težki nesreči v jedrski elektrarni v Fukušimi so se zaostrili standardi...
SAMHYCO-NET drugi sestanek, Karlsruhe, Nemčija, 3. – 7. 6. 2018
SAMHYCO-NET drugi sestanek, Karlsruhe, Nemčija, 3. – 7. 6. 2018 Projekt SAMHYCO-NET je projekt brez financiranja (»in-kind project«), ki je nastal na iniciativo Institut de Radiop...
12th International Conference of the Croatian nuclear society – Nuclear Option for CO2 Free Energy Generation
12th International Conference of the Croatian nuclear society – Nuclear Option for CO2 Free Energy Generation Dvoletno mednarodno konferenco »Nuclear Option for CO2 Free Energy Generatio...
Spring 2018 CAMP meeting, Ottawa, Kanada, 28.5. – 30.5.2018
Spring 2018 CAMP meeting, Ottawa, Kanada, 28.5. – 30.5.2018   CAMP (Code Applications and Maintenance Program) je največji raziskovalni program, ki poteka pod okriljem ameri&scar...
Konferenca BEPU 2018, Lucca, Italija, 13.05. do 19.05, 2018
Konferenca BEPU 2018, Lucca, Italija, 13.05. do 19.05, 2018 Tematika mednarodne konference BEPU-2018 (Best Estimate Plus Uncertainty) zajema razvoj, aplikacije in napredek na področju simulacijskih...
Sestanek delovne skupine WP5 projekta SOTERIA, EDF Lab Les Renardières, Francija, 17.-18.5.2018
Sestanek delovne skupine WP5 projekta SOTERIA, EDF Lab Les Renardières, Francija, 17.-18.5.2018   Projekt SOTERIA (»Safe long term operation of...
GA-21 EUROfusion, Sofia, Bolgarija, 10.04.-12.04.2018
GA-21 EUROfusion, Sofia, Bolgarija, 10.04.-12.04.2018 Evropske fuzijske raziskave v okviru Obzorja 2020 združuje ciljno orientiran 5-letni (2014-2018) fuzijski program EUROfusion, ki poteka pod okr...
22. sestanek upravnega odbora SNETP
22. sestanek upravnega odbora SNETP, Bruselj, 24.1.2018 Evropska tehnološka platforma za trajnostno jedrsko energijo SNETP združuje več kot 117 jedrskih deležnikov iz vseh evropskih jedrskih držav. Med ...
Generalna skupščina, upravni odbor in 15 letnica združenja ENEN
Generalna skupščina, upravni odbor in 15 letnica združenja ENEN, Bruselj, Belgija, 28.2.-2.3.2018 Več kot 60 članic združenja ENEN predstavlja večino evropskih univerz in raziskovalnih inštitut...
Začetni sestanek projekta ENER/D3/2017-209-2, Luksemburg, Luksemburg
Začetni sestanek projekta ENER/D3/2017-209-2, Luksemburg, Luksemburg, 18.-19.2.2018 Direktorat za energijo pri Evropski komisiji je pri združenju pooblaščenih izvedencev za jedrsko varnost ETSON naročil študij...
mobile view