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Thermal Hydraulics (THS)

list of publications on thermal-hydraulics topics over the last 10 years

Journal papers

 

2021

A. S. Al-Awad, M. Pérez-Ferragut and J. Freixa. Application of a BEPU-based code assessment to the ATLAS upper head SBLOCA test. Annals of Nuclear Energy, 2021, 164, 108581

J. Freixa, A. Laborda, V. Martínez-Quiroga. Effectiveness of the ASVAD valve in a reactor vessel bottom leak scenario. Annals of Nuclear Energy, 2021, 160, 108387.

J. Freixa, V. Martínez-Quiroga, M. Casamor, F. Reventós, R. Mendizábal, M. Sánchez-Perea. On the validatio nof BEPU methodologies through the simulation of integral experiments: Application to the PKL test facility. Nuclear Engineering and Design, Vol 379, 2021, 111238.

2020

E. Mas de les Valls, A. Cegielski, M. Jaros, M. Pérez-Ferragut, L. Batet, T. Sandeep, V. Chaudhari and J. Freixa. Development of flow regime maps for lead lithium eutectic - helium flows. Nuclear Fusion and Design, 2020

J. Freixa, V. Martinez-Quiroga, and F. Reventós. Modelling guidelines for safety analysis of Station Black Out sequences based on experiments at the PKL test facility. Annals of Nuclear Energy, 138:107179, apr 2020

2019

F. Reventos, V. Martínez-Quiroga, and J. Freixa. Perfecting the use of hybrid models in scaling analysis. Nuclear Engineering and Design, 354, 2019

M Casamor, V Martínez-Quiroga, F Reventós, and J. Freixa. On the Scaling of Uncertainties in Thermal Hydraulic System Codes. Annals of Nuclear Energy, 2019

T. Skorek, A. de Crécy, A. Kovtonyuk, A. Petruzzi, R. Mendizábal, E. de Alfonso,F. Reventós, J. Freixa, C. Sarrette, M. Kyncl, R. Pernica, J. Baccou, F. Fouet,P. Probst, B. Dong Chung, T. Tranh Tram, Deog Y. Oh, A. Gusev, A. Falkov, Y.i Shvestov, D. Li, X. Liu, J. Zhang, T. Alku, J. Kurki, W. Jäger, V. Sánchez, D. Wicaksono,O. Zerkak, and A. Pautz. Quantification of the uncertainty of the physical models in the systemthermal-hydraulic codes – PREMIUM benchmark. Nuclear Engineering and Design, 2019

2018

V. Martínez-Quiroga; J. Freixa; Reventos, F. PVST, a tool to assess the Power to Volume scaling distortions associated to code simulations (2018) Nuclear Engineering and Design, 332, pp. 173-185.

2016

J. Freixa; V. Martínez-Quiroga; Reventos, F. Qualification of a full plant nodalization for the prediction of the core exit temperature through a scaling methodology. Nuclear Engineering and Design, Volume 308, November 2016, Pages 115–132

J. Freixa; Elsa de Alfonso; Reventos, F. Testing methodologies for quantifying physical models uncertainties. A comparative exercise using CIRCE and IPREM (FFTBM). Nuclear Engineering and Design, Volume 305, August 2016, Pages 653–665

P. Pla, F. Reventos, M. Martin Ramos, M. Strucic, I. Sol, Simulation of steam generator plugging tubes in a PWR to analyze the operating impact. Nuclear Engineering and Design, Volume 305, August 2016, Pages 132–145, DOI: 10.1016/j.nucengdes.2016.05.002

R. Pericas, K. Ivanov, F. Reventos, L. Batet, Code improvement and model validation for Ascó-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal–hydraulic code. Annals of Nuclear Energy, Volume 87, part 2, January 2016, Pages 366–374, doi:10.1016/j.anucene.2015.09.024

2015

J. Freixa; V. Martínez-Quiroga; O. Zerkak; Reventos, F. Modelling guidelines for Core Exit Temperature simulations with system codes. Nuclear Engineering and Design. Nuclear Engineering and Design, Volume 286, May 2015, Pages 116–129, doi:10.1016/j.nucengdes.2015.02.003

Pla, P.; Pascal, G.; Tanarro, J.; Annunziato, A., The new STRESA tool for preservation of thermalhydraulic experimental data produced in the European Commission. Annals of Nuclear Energy, Volume 85, Nov. 2015, Pages 893-902, doi:10.1016/j.anucene.2015.07.007

2014

R. Szijártó, J. Freixa, H. -M Prasser, "Simulation of condensation in a closed, slightly inclined horizontal pipe with a modified RELAP5 code",Nuclear Engineering and Design, Volume 273, 1 July 2014, Pages 288-297, http://dx.doi.org/10.1016/j.nucengdes.2014.03.028

V. Martinez-Quiroga, F. Reventos, and J. Freixa, “Applying UPC Scaling-Up Methodology to the LSTF-PKL Counterpart Test,” Science and Technology of Nuclear Installations, vol. 2014, Article ID 292916, 18 pages, 2014. doi:10.1155/2014/292916

V. Martinez-Quiroga and F. Reventos, “The Use of System Codes in Scaling Studies: Relevant Techniques for Qualifying NPP Nodalizations for Particular Scenarios,” Science and Technology of Nuclear Installations, vol. 2014, Article ID 138745, 13 pages, 2014. doi:10.1155/2014/138745

2013

C. Arenas, R. Bratton, F. Reventos, and K. Ivanov, “Uncertainty Analysis of Light Water Reactor Fuel Lattices,” Science and Technology of Nuclear Installations, vol. 2013, Article ID 437409, 10 pages, 2013. doi:10.1155/2013/437409

2012

F. Reventós, P. Pla, C. Matteoli, et al., “Consistent Posttest Calculations for LOCA Scenarios in LOBI Integral Facility,” Science and Technology of Nuclear Installations, vol. 2012, Article ID 474162, 16 pages, 2012. doi:10.1155/2012/474162

C. M. Allison, J. K. Hohorst, B. S. Allison, D. Konjarek, T. Bajs, R. Pericas, F. Reventos, and R. Lopez, “Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM,” Science and Technology of Nuclear Installations, vol. 2012, Article ID 646327, 25 pages, 2012. doi:10.1155/2012/646327

G. Espinosa-Paredes, L. Batet, A. Nuñez-Carrera, and J. Sugimoto, “Severe Accident Analysis in Nuclear Power Plants,” Science and Technology of Nuclear Installations, vol. 2012, Article ID 430471, 2 pages, 2012. doi:10.1155/2012/430471

2011

M. Perez, F. Reventos, L. Batet, A. Guba, I. Tóth, T. Mieusset, P. Bazin, A. de Crécy, S. Borisov, T. Skorek, H. Glaeser, J. Joucla, P. Probst, A. Ui, B.D. Chung, D.Y. Oh, R. Pernica, M. Kyncl, J. Macek, A. Manera, J. Freixa, A. Petruzzi, F. D’Auria, A. Del Nevo, Uncertainty and sensitivity analysis of a LBLOCA in a PWR Nuclear Power Plant: Results of the Phase V of the BEMUSE programme, Nuclear Engineering and Design, Volume 241, Issue 10, October 2011, Pages 4206-4222.

S. Kamerow, K. Ivanov and C. Arenas "Uncertainty Analysis of Light Water Reactor Unit Fuel Pin Cells" International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011) Rio de Janeiro, RJ, Brazil, May 8-12, 2011, on CD - ROM, Latin American Section (LAS) / American Nuclear Society (ANS) ISBN 978-85-63688-00-2

F. Reventos, P. Pla, C. Matteoli, G. Nacci, M. Cherubini, A. Del Nevo and F. D'Auria “TConsistent Post-test Calculations for LOCA Scenarios in LOBI Integral Facility,” Science and Technology of Nuclear Installations, vol. 2011, Article ID 474162, 16 pages, 2011. doi:10.1155/2011/474162

 

2010

F. Reventós, C. Llopis, L. Batet, C. Pretel, I. Sol, Analysis of an actual reactor trip operating event due to a high variation of neutron flux occurring in the Vandellòs-II nuclear power plant, Nuclear Engineering and Design, Volume 240, Issue 10, October 2010, Pages 2999-3008, ISSN 0029-5493

Arias, F.J.; Reventos, F. Heat Transfer Enhancement in Film Boiling due to Lift Forces on the Taylor-Helmholtz Instability in Low Forced Convection from a Horizontal Surface. "Journal of enhanced heat transfer", Gener 2010, vol. 17, núm. 2, p. 1-97. <doi: 10.1615/JEnhHeatTransf.v17.i2.70>

M. Pérez, F. Reventós, L. Batet, R. Pericas, et al., “Main Results of Phase IV BEMUSE Project: Simulation of LBLOCA in an NPP,” Science and Technology of Nuclear Installations, vol. 2010, Article ID 219294, 9 pages, 2010. doi:10.1155/2010/219294

2009

Freixa, J; Reventos, F; Pretel, C, et al. SBLOCA with boron dilution in pressurized water reactors. Impact on operation and safety. Nuclear Engineering and Design Volume: 239 Issue: 4 Pages: 749-760 Published: 2009

Reventós, F., Pretel, C., Batet, L., Izquierdo, J., Arànega, M. Teaching basic Pressurized Water Reactor core thermal-hydraulics employing worksheet-based exercises (2009) International Journal of Engineering Education, 25 (6), pp. 1183-1193.

Arias, F.; Pla, P.; Reventos, F. Thermocapillary on film boiling heat transfer from a non isothermal horizontal surface: A theoretical study from CANDU reactors. "Progress in nuclear energy", Setembre 2009, vol. 51, núm. 6-7, p. 672-675.

Arias, F.; Reventos, F. A theoretical study of cyclon-effect in PWR downcomer during a LOCA blowdown. "Annals of nuclear energy", August 2009, vol. 36, núm. 8, p. 1294-1297.

2008

F. Reventós, J. Freixa, L. Batet, C. Pretel, D. Luebbesmeyer, D. Spaziani, J. Macek, F. Kasahara, K. Umminger. An analytical comparative exercise on the OECD-SETH PKL E2.2 experiment. “Nuclear engineering and design” Volume: 238 Issue: 4 Pages: 1146-1154 Published: 2008

A. de Crécy, P. Bazin, H. Glaeser, T. Skorek, J. Joucla, P. Probst, K. Fujioka, B.D. Chung, D.Y. Oh, M. Kyncl, R. Pernica, J. Macek, R. Meca, R. Macian, F. D’Auria, A. Petruzzi, L. Batet, M. Perez, F. Reventos, Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE programme, Nuclear Engineering and Design, Volume 238, Issue 12, December 2008, Pages 3561-3578, ISSN 0029-5493, http://dx.doi.org/10.1016/j.nucengdes.2008.06.004.

F. Reventós, L. Batet, C. Llopis, C. Pretel, and I. Sol, “Thermal-Hydraulic Analysis Tasks for ANAV NPPs in Support of Plant Operation and Control,” Science and Technology of Nuclear Installations, vol. 2008, Article ID 153858, 13 pages, 2008. doi:10.1155/2008/153858

A. Petruzzi, F. D'Auria, T. Bajs, F. Reventos, and Y. Hassan, “International Course to Support Nuclear Licensing by User Training in the Areas of Scaling, Uncertainty, and 3D Thermal-Hydraulics/Neutron-Kinetics Coupled Codes: 3D S.UN.COP Seminars,” Science and Technology of Nuclear Installations, vol. 2008, Article ID 874023, 16 pages, 2008. doi:10.1155/2008/874023

2007

Freixa J., Batet L. Pretel C., Reventós F. “Boron Transport Model With Physical Diffusion for RELAP5”. “Nuclear Technology” Volume: 160 Pages: 205-215 Published: 2007

C. Llopis, F. Reventós, L. Batet, C. Pretel, I. Sol, Analysis of low load transients for the Vandellòs-II NPP: Application to operation and control support, Nuclear Engineering and Design, Volume 237, Issue 18, October 2007, Pages 2014-2023, ISSN 0029-5493, http://dx.doi.org/10.1016/j.nucengdes.2007.02.005.

F. Reventós, L. Batet, C. Llopis, C. Pretel, M. Salvat, I. Sol, Advanced qualification process of ANAV NPP integral dynamic models for supporting plant operation and control, Nuclear Engineering and Design, Volume 237, Issue 1, January 2007, Pages 54-63, ISSN 0029-5493, http://dx.doi.org/10.1016/j.nucengdes.2006.05.002.

F. Reventós, L. Batet, C. Pretel, M. Ríos, I. Sol, Analysis of the Feed and Bleed procedure for the Ascó NPP: First approach study for operation support, Nuclear Engineering and Design, Volume 237, Issue 18, October 2007, Pages 2006-2013, ISSN 0029-5493, http://dx.doi.org/10.1016/j.nucengdes.2007.02.006.

International conference papers

Freixa, J., Martínez-Quiroga, V., Reventós, F. Modelling guidelines for CCFL representation during Ibloca scenarios of PWR reactors (2017) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2017-September

J. Freixa, V. Martínez-Quiroga, F. Reventós. Core Exit Temperature Response during an SBLOCA Event in the Ascó NPP. The 16th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-16 Chicago, Illinois, USA, Sep. 2015.

J. Freixa, M. Perez-Ferragut, F. Reventos, C. M. Allison, J. K. Hohorst (ISS). Revisiting ISP-13 with RELAP/SCDAPSIM/MOD3.5 using Core SCDAP Components. NURETH-16 Chicago, Illinois, USA, Sep. 2015.

M. Perez, J. Freixa, , E. Mas de les Valls, T. Sandeep, V. Chaudhari (Inst for Plasma Research). RELAP/SCDAPSIM/MOD4.0 Modification for Transient Accident Scenario of Test Blanket Modules Involving Helium Flows into Heavy Liquid Metal. NURETH-16 Chicago, Illinois, USA, Sep. 2015.

R. Pericas, K. Ivanov, F. Reventós. Comparison of Best Estimate Plus Uncertainties and Conservative Methodologies for a PWR MSLB Analysis using Coupled 3D Neutron Kinetics/Thermal-Hydraulic Code. NURETH-15 Pisa, Italy, May 12-15, 2013

J. Freixa (UPC, PSI), S. Belaid (NRCB, Algeria), O. Zerkak (PSI, Switzerland). Thermal-Hydraulic System Code Performance for SBLOCA Phenomenology under Different Geometries and Scales. NURETH-15 Pisa, Italy, May 12-17, 2013

H. Glaeser (GRS), F. D'Auria (University of Pisa, GRNSPG, Italy) A. De Crécy (CEA), F. Reventós. Main Results of the OECD Best Estimate Methods, Uncertainty and Sensitivity Evaluation (BEMUSE) Programme. NURETH-14, Toronto, Canada. September 25-30, 2011
F. Reventós, H. Glaeser (GRS), F. D'Auria (University of Pisa, GRNSPG, Italy), A. De Crécy (CEA). Uncertainty and Sensitivity Analysis for a Nuclear Power Plant Large Break Loss of Coolant Accident (LB-LOCA) in the Context of OECD BEMUSE Programme. NURETH-14, Toronto, Canada. September 25-30, 2011

D. Dupleac (Politehnica University of Bucarest), M. Pérez, F. Reventós, C. Allison (Innovative Systems Software). Uncertainty Analysis of the 35% Reactor Inlet Header Break in a CANDU 6 Reactor Using RELAP/SCDAPSIM/MOD4.0 with Integrated Uncertainty Analysis Option. NURETH-14, Toronto, Canada. September 25-30, 2011

P. Pla (GRNSPG-UNIPI/UPC), C. Parisi (GRNSPG-UNIPI), R. Galetti (CNEN), F. S. D'Auria (University of Pisa, GRNSPG, Italy), G. Galassi (GRNSPG-UNIPI), F. Reventós. Basis for Calculating Boron Dilution Scenarios in PWR by 3D Neutron Kinetics. NURETH-14, Toronto, Canada. September 25-30, 2011

J. Freixa, F. Reventós, A. Manera. TRACE and RELAP5 Thermal-Hydraulic Analysis on Boron Dilution Tests at the PKL Facility. NURETH-13, Kanazawa, Japan. September 27-October 2, 2009

M. Perez, F. Reventós, R. Wagner (ISS), C. Allison (ISS). Integrated Uncertainty Analysis using RELAP/SCDAPSI M/MOD4.0. NURETH-13, Kanazawa, Japan. September 27-October 2, 2009

V. Martínez-Quiroga, F. Reventós, C. Pretel "Code Validation and Scaling of the ROSA/LSTF Test 3-1 Experiment" TOPSAFE International Topical Meeting on Safety of Nuclear I ns tallations, Dubrovnik, Croatia, 30.9 – 3.10. 2008