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Featured researches published by J. Freixa.


Science and Technology of Nuclear Installations | 2014

Applying UPC Scaling-Up Methodology to the LSTF-PKL Counterpart Test

V. Martinez-Quiroga; F. Reventós; J. Freixa

In the framework of the nodalization qualification process and quality guarantee procedures and following the guidelines of Kv-scaled analysis and UMAE methodology, further development has been performed by UPC team resulting in a scaling-up methodology. Such methodology has been applied in this paper for analyzing discrepancies that appear between the simulations of two counterpart tests. It allows the analysis of scaling-down criterion used for the design of an ITF and also the investigation of the differences of configuration between an ITF and a particular NPP. For analyzing both, it applies two concepts “scaled-up nodalizations” and “hybrid nodalizations.” The result of this activity is the explanation of appeared distortions and its final goal is to qualify nodalizations for their use in the analysis of equivalent scenarios at an NPP scale. In this sense, the experimental data obtained in the OECD/NEA PKL-2 and ROSA-2 projects as counterpart test are of a great value for the testing of the present methodology. The results of the posttest calculations of LSTF-PKL counterpart tests have allowed the analyst to define which phenomena could be well reproduced by their nodalizations and which not, in this way establishing the basis for a future extrapolation to an NPP scaled calculation. The application of the UPC scaling up methodology has demonstrated that selected phenomena can be scaled-up and explained between counterpart simulations by carefully considering the differences in scale and design.


Nuclear Technology | 2007

Boron transport model with physical diffusion for RELAP5

J. Freixa; F. Reventós; C. Pretel; L. Batet

Rapid boron dilution transients have shown the need for accurate knowledge of the solute particle distribution in pressurized water reactors (PWRs). Small-break loss-of-coolant accidents (SBLOCAs) enable the formation of low-borated slugs in the loop seals. Low-borated water, if driven to the core, could cause a reactivity excursion. Since online boron concentration measurement is impractical in the primary system of PWR plants and quite difficult in test facilities, best-estimate codes should be seen as the most suitable tools. However, transport of a low-borated slug through the primary system requires accuracy of the methods. Several studies have shown high numerical diffusion introduced by the upwind difference schemes habitually used by system codes. Furthermore, most of the boron tracking models implemented in system codes at present do not consider physical diffusion. Nevertheless, to introduce physical diffusion, it is necessary to considerably reduce numerical diffusion. The implicit Godunov scheme, which is available in RELAP5, has proved its capability in almost eradicating numerical diffusion. However, the formulated equation in RELAP5 does not deal with physical diffusion. A new tracking model for the solute field is presented, along with results of its implementation in the RELAP5 code. To evaluate the new model, a numerical test has been performed that demonstrates both the reduction of numerical diffusion and the correct simulation of physical diffusion. Moreover, the UPC model has shown its consistency in experiment F1.1, which is an SBLOCA with boron dilution. The test was part of the OECD-PKL2 program directed by the Organisation for Economic Cooperation and Development (OECD).


Nuclear Engineering and Design | 2011

Uncertainty and sensitivity analysis of a LBLOCA in a PWR Nuclear Power Plant: Results of the Phase v of the BEMUSE programme

M. Perez; F. Reventós; 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; Francesco D’Auria; A. Del Nevo


Nuclear Engineering and Design | 2009

SBLOCA with boron dilution in pressurized water reactors. Impact on operation and safety

J. Freixa; F. Reventós; C. Pretel; L. Batet; I. Sol


Nuclear Engineering and Design | 2008

An analytical comparative exercise on the OECD-SETH PKL E2.2 experiment

F. Reventós; J. Freixa; L. Batet; C. Pretel; D. Luebbesmeyer; D. Spaziani; J. Macek; F. Lahovsky; F. Kasahara; Klaus Umminger; R. Wegner


Nuclear Engineering and Design | 2015

Modelling guidelines for core exit temperature simulations with system codes

J. Freixa; V. Martinez-Quiroga; O. Zerkak; F. Reventós


Nuclear Engineering and Design | 2014

Simulation of condensation in a closed, slightly inclined horizontal pipe with a modified RELAP5 code

R. Szijártó; J. Freixa; Horst-Michael Prasser


Nuclear Engineering and Design | 2016

Qualification of a full plant nodalization for the prediction of the core exit temperature through a scaling methodology

J. Freixa; V. Martinez-Quiroga; F. Reventós


Nuclear Engineering and Design | 2016

Testing methodologies for quantifying physical models uncertainties. A comparative exercise using CIRCE and IPREM (FFTBM)

J. Freixa; Elsa de Alfonso; F. Reventós


Nuclear Engineering and Design | 2018

PVST, a tool to assess the Power to Volume scaling distortions associated to code simulations

V. Martinez-Quiroga; J. Freixa; F. Reventós

Collaboration


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F. Reventós

Polytechnic University of Catalonia

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L. Batet

Polytechnic University of Catalonia

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V. Martinez-Quiroga

Polytechnic University of Catalonia

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C. Pretel

Polytechnic University of Catalonia

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I. Tóth

Hungarian Academy of Sciences

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J. Joucla

Institut de radioprotection et de sûreté nucléaire

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P. Probst

Institut de radioprotection et de sûreté nucléaire

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