Benchmarking LWR codes capability to model radionuclide deposition within SFR containments: An analysis of the Na ABCOVE tests

dc.contributor.authorHerranz, L.E.
dc.contributor.authorGarcia, M.
dc.contributor.authorMorandi, S.
dc.date.accessioned2025-01-27T14:22:03Z
dc.date.available2025-01-27T14:22:03Z
dc.date.issued2013-12
dc.description.abstractPostulated BDBAs in SFRs might result in contaminated-coolant discharge at high temperature into the containment. A full scope safety analysis of this reactor type requires computation tools properly validated in all the related fields. Radionuclide transport, particularly within the containment, is one of those fields. This sets two major challenges: to have reliable codes available and to build up a sound data base. Development of SFR source term codes was abandoned in the 80’s and few data are available at present. The ABCOVE experimental programme conducted in the 80’s is still a reference in the field. Postulated BDBAs in SFRs might result in contaminated-coolant discharge at high temperature into the containment. A full scope safety analysis of this reactor type requires computation tools properly validated in all the related fields. Radionuclide deposition, particularly within the containment, is one of those fields. This sets two major challenges: to have reliable codes available and to build up a sound data base. Development of SFR source term codes was abandoned in the 80’s and few data are available at present. The ABCOVE experimental programme conducted in the 80’s is still a reference in the field. The present paper is aimed at assessing the current capability of LWR codes to model aerosol deposition within a SFR containment under BDBA conditions. Through a systematic application of the ASTEC, ECART and MELCOR codes to relevant ABCOVE tests, insights have been gained into drawbacks and capabilities of these computation tools. Hypotheses and approximations have been adopted so that differences in boundary conditions between LWR and SFR containments under BDBA can be accommodated to some extent. Two major outcomes result from this study: a reasonable approximation to the BDBA SFR scenario can be achieved with LWR codes if suitable hypotheses are made and development and implementation of new models is mandatory to enhance predictability to the required level in safety analyses. Vaporization, nucleation and oxidation of Na and turbulent agglomeration of particles are phenomena, for which models should be developed and implemented. Additionally, the importance of a good morphological characterization of aerosol particles has been highlighted.es_ES
dc.description.sponsorshipCollaborative Project on European Sodium Fast Reactor (CP-ESFR – 2009–2012) project that was launched within the 7th EC Framework Programmees_ES
dc.identifier.doihttp://dx.doi.org/10.1016/j.nucengdes.2013.05.030
dc.identifier.issn0029-5493
dc.identifier.urihttps://hdl.handle.net/20.500.14855/4374
dc.language.isoenges_ES
dc.publisherNuclear Engineering and Designes_ES
dc.rights.accessRightsopen accesses_ES
dc.subjectLWR codeses_ES
dc.subjectSource termes_ES
dc.subjectSFRes_ES
dc.subjectContainmentes_ES
dc.titleBenchmarking LWR codes capability to model radionuclide deposition within SFR containments: An analysis of the Na ABCOVE testses_ES
dc.typejournal articlees_ES

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