Show simple item record

dc.contributor.authorSoba, Alejandro
dc.contributor.authorCazado, Mauricio E.
dc.contributor.authorHouzeaux, Guillaume
dc.contributor.authorGutierrez Milla, Albert
dc.contributor.authorMantsinen, Mervi J.
dc.contributor.authorSaez Pous, Xavier
dc.contributor.otherBarcelona Supercomputing Center
dc.date.accessioned2021-03-23T15:45:14Z
dc.date.issued2021
dc.identifier.citationSoba, A. [et al.]. Validations of the radiation transport module NEUTRO: A deterministic solver for the neutron transport equation. "Fusion Engineering and Design", 2021, vol. 169, 112497.
dc.identifier.issn0920-3796
dc.identifier.urihttp://hdl.handle.net/2117/342302
dc.description.abstractWe present significant improvements and validations of a deterministic neutron transport code (NEUTRO) dedicated to solving the Boltzmann Transport Equation. The code is integrated as a module in the Alya software package developed by the Barcelona Supercomputing Center which uses the Discrete Ordinates Method on angular coordinates, multi-group for energy discretization and FEM on unstructured meshes to treat special complex domains. The anisotropy of the scattering medium is introduced into the scattering kernel using real base expressions for spherical harmonics. In order to build the total cross-section and the respective group matrix for the elastic cross-section, we use the NJOY code. We test the solver using different geometries, orders of integration for the angular discretization and number of energy groups. Finally, we compare our results against benchmarks obtained from an NEA database that reported measurements of leakage spectra of several materials.
dc.description.sponsorshipThis work has been partially carried out within the framework of the EUROlab4HPC and Severo Ochoa fellowship and has been partly co-financed by the European Union Regional Development Fund (ERDF) within the framework of the ERDF Operational Program of Catalonia 2014-2020. The authors would like to thank Dr A. Portone and Dr M. Fabbri for useful discussions.
dc.format.extent12 p.
dc.language.isoeng
dc.publisherElsevier
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.subject.lcshBoltzmann transport equation
dc.subject.lcshNeutron transport theory
dc.subject.lcshHigh performance computing
dc.subject.otherRadiation transport
dc.subject.otherNeutron-wall interaction
dc.subject.otherFusion reactors shielding
dc.subject.otherSINBAD
dc.titleValidations of the radiation transport module NEUTRO: A deterministic solver for the neutron transport equation
dc.typeArticle
dc.subject.lemacFusió nuclear
dc.identifier.doi10.1016/j.fusengdes.2021.112497
dc.description.peerreviewedPeer Reviewed
dc.relation.publisherversionhttps://www.sciencedirect.com/science/article/abs/pii/S0920379621002738#!
dc.rights.accessRestricted access - publisher's policy
dc.description.versionPostprint (author's final draft)
dc.date.lift2023-03-16
local.citation.other112497
local.citation.publicationNameFusion Engineering and Design
local.citation.volume169


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record

Attribution-NonCommercial-NoDerivs 3.0 Spain
Except where otherwise noted, content on this work is licensed under a Creative Commons license : Attribution-NonCommercial-NoDerivs 3.0 Spain