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dc.contributor.authorFreixa Terradas, Jordi
dc.contributor.authorMartínez Quiroga, Víctor Manuel
dc.contributor.authorCasamor Vidal, Max
dc.contributor.authorReventós Puigjaner, Francesc Josep
dc.contributor.authorMendizabal Sanz, Rafael
dc.contributor.otherUniversitat Politècnica de Catalunya. Departament de Física
dc.contributor.otherUniversitat Politècnica de Catalunya. Doctorat en Enginyeria Nuclear i de les Radiacions Ionitzants
dc.date.accessioned2020-02-10T12:39:57Z
dc.date.issued2019
dc.identifier.citationFreixa, J. [et al.]. Validation of a BEPU methodology through a blind benchmark activity at the PKL test facility. A: International Topical Meeting on Nuclear Reactor Thermal Hydraulics. "18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics: NURETH-18: Portland, USA: 18-23 August, 2019". La Grange Park: American Nuclear Society (ANS), 2019, p. 366-379.
dc.identifier.isbn978-0-89448-767-5
dc.identifier.urihttp://hdl.handle.net/2117/177311
dc.description.abstractValidation is a key step in the field of thermal hydraulics and has played a crucial role in the implementation of system codes. These codes are then included in licensing methodologies being those either best estimate plus uncertainties (BEPU) or conservative approaches. However, only a small amount of efforts has been done on the validation of the methodologies as a whole. Such validation would imply the comparison of the bounding limits and the experimental data. Due to the lack of actual data of accidental situations, such validation should be carried out with data from integral test facility (ITF) experiments.The OECD/NEA PKL-4 test programme is investigating safety issues relevant for current pressurizedwater reactor (PWR) plants as well as for new PWR design concepts focusing on complex heat transfer mechanisms under two-phase flow. Within the project, a blind benchmark activity has been launched where an IBLOCA experiment has been simulated by 12 different organizations. The Universitat Politècnica de Catalunya(UPC) participated to the activity with a blind BEPU approach with the main objective to assess the validity of the methodology as a whole. At first, the acceptance criteria for the particular scenario have been evaluated. Secondly, in order to broaden the extend of the validation, the results of the different participants have been interpreted as if they were blind experiments as well. Finally, different output parameters have been considered providing a matrix of results that is used to evaluate the validity of the methodology.
dc.format.extent14 p.
dc.language.isoeng
dc.publisherAmerican Nuclear Society (ANS)
dc.rightsAttribution-NonCommercial-NoDerivs 3.0 Spain
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/3.0/es/
dc.subjectÀrees temàtiques de la UPC::Física
dc.subjectÀrees temàtiques de la UPC::Física::Termodinàmica
dc.subject.lcshHydraulics
dc.subject.lcshHeat--Transmission
dc.subject.otherBEPU
dc.subject.otherDSA
dc.subject.otherValidation
dc.subject.otherUncertaintied
dc.titleValidation of a BEPU methodology through a blind benchmark activity at the PKL test facility
dc.typeConference report
dc.subject.lemacHidràulica
dc.subject.lemacCalor--Transmissió
dc.contributor.groupUniversitat Politècnica de Catalunya. ANT - Advanced Nuclear Technologies Research Group
dc.rights.accessRestricted access - publisher's policy
local.identifier.drac26560904
dc.description.versionPostprint (published version)
dc.date.lift10000-01-01
local.citation.authorFreixa, J.; Martinez, V.; Casamor, M.; Reventos, F.; Mendizabal, R.
local.citation.contributorInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics
local.citation.pubplaceLa Grange Park
local.citation.publicationName18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics: NURETH-18: Portland, USA: 18-23 August, 2019
local.citation.startingPage366
local.citation.endingPage379


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