Neutronic and thermal-hydraulic modelling of High Performance Light Water Reactor

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dc.contributorAalto-yliopistofi
dc.contributorAalto Universityen
dc.contributor.advisorDaavittila, Antti 
dc.contributor.authorSeppälä, Malla
dc.contributor.departmentTeknillisen fysiikan laitosfi
dc.contributor.schoolTeknillinen korkeakoulufi
dc.contributor.schoolHelsinki University of Technologyen
dc.contributor.supervisorSalomaa, Rainer 
dc.date.accessioned2020-12-05T13:46:43Z
dc.date.available2020-12-05T13:46:43Z
dc.date.issued2008 
dc.description.abstractHigh Performance Light Water Reactor (HPLWR) is a new reactor concept that operates at supercritical pressure conditions. VTT participates in the `HPLWR2' project, in which the technological feasibility and economical competitiveness of the concept are assessed, by calculating coupled neutronic and thermal-hydraulic analysis of the HPLWR plant. An advanced core model TRAB-3D was chosen for neutronics calculation internally coupled to thermal-hydraulic system code SMABRE. The work done for this thesis is part of VTT's contribution to the project. To initiate the modelling of HPLWR at VTT, a thorough literature survey on the current state of the design was done in this thesis. Based on the gathered data, input models of the HPLWR plant were made for TRAB-3D and SMABRE. The capability of SMABRE to calculate supercritical pressure conditions were shown by calculating the Edwards-O'Brien blowdown test modified to supercritical pressures. A functioning thermal-hydraulic steady-state for the HPLWR model was achieved with SMABRE. However, due to complications with SMABRE, testing of the coupled model could not be started yet. In addition to the coupled transient analysis, two-group constants for HPLWR fuel assembly were generated with PSG Monte Carlo neutron transport code developed at VTT. The results were compared to parameterized cross sections received from Hungarian Academy of Sciences KFKI Atomic Energy Research Institute. Reference values for infinite multiplication factor were calculated also with MCNP4C.en
dc.format.extent74 
dc.identifier.urihttps://aaltodoc.aalto.fi/handle/123456789/95658
dc.identifier.urnURN:NBN:fi:aalto-2020120554492
dc.language.isoenen
dc.programme.majorYdin- ja energiatekniikkafi
dc.programme.mcodeTfy-56fi
dc.rights.accesslevelclosedAccess
dc.subject.keywordfissionen
dc.subject.keywordfissiofi
dc.subject.keywordnuclearen
dc.subject.keyword4. sukupolven reaktoritfi
dc.subject.keywordGeneration IVen
dc.subject.keywordydinvoimafi
dc.subject.keywordsupercritical water reactoren
dc.subject.keywordsuperkriittinen vesifi
dc.subject.keywordHigh Performance Light Water Reactoren
dc.subject.keywordHPLWRfi
dc.subject.keywordneutronicsen
dc.subject.keywordneutroniikkafi
dc.subject.keywordthermal-hydraulicsen
dc.subject.keywordtermohydrauliikkafi
dc.subject.keywordcross sectionen
dc.subject.keywordvaikutusalatfi
dc.titleNeutronic and thermal-hydraulic modelling of High Performance Light Water Reactoren
dc.titleHPLWR-reaktorin neutroniikan ja termohydrauliikan mallintaminenfi
dc.type.okmG2 Pro gradu, diplomityö 
dc.type.ontasotMaster's thesisen
dc.type.ontasotPro gradu -tutkielmafi
dc.type.publicationmasterThesis 
local.aalto.digiauthask
local.aalto.digifolderAalto_43257
local.aalto.idinssi35894
local.aalto.openaccessno
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