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A review of the current thermal-hydraulic modeling of the Jules Horowitz Reactor: A loss of flow accident analysis
KTH, School of Engineering Sciences (SCI), Physics, Reactor Technology.ORCID iD: 0000-0003-1271-9795
CEA, DEN, DER, SRJH, CEA Cadarache.
CEA, DEN, DER, SRJH, CEA Cadarache.
KTH, School of Engineering Sciences (SCI), Physics, Reactor Technology.ORCID iD: 0000-0001-5595-1952
2014 (English)In: Nuclear Engineering and Design, ISSN 0029-5493, E-ISSN 1872-759X, Vol. 280, 294-304 p.Article in journal (Refereed) Published
Abstract [en]

The newest European high performance material testing reactor, the Jules Horowitz Reactor, will support existing and future nuclear reactor designs. The reactor is under construction at CEA Cadarache research center in France and is expected to start operation at the end of this decade. R&D and analytical works have already been performed to set-up the methodology for thermal-hydraulic calculations of the reactor. This paper presents the off-line coupled thermal-hydraulic modeling of the reactor using the CATHARE system code and the FLICA4 core analysis code. The main objective of the present work is to analyze the thermal-hydraulic calculations of the reactor during the loss of flow accident using CEA methodology. Possible improvements of the current methodology are shortly discussed and suggested.

Place, publisher, year, edition, pages
2014. Vol. 280, 294-304 p.
Keyword [en]
Pressure-Drop, Computer Code, Heat-Transfer
National Category
Fluid Mechanics and Acoustics
URN: urn:nbn:se:kth:diva-156849DOI: 10.1016/j.nucengdes.2014.09.019ISI: 000347265100030ScopusID: 2-s2.0-84914159990OAI: diva2:768168
Jules Horowitz Reactor, CATHARE, FLICA4, LOFA
Swedish Research Council

QC 20150130

Available from: 2014-12-03 Created: 2014-12-03 Last updated: 2015-01-30Bibliographically approved

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