Thermal hydraulic analysis improvement for the IEA-R1 research reactor and fuel assembly design modification

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dc.contributor.authorUMBEHAUN, PEDRO E.
dc.contributor.authorTORRES, WALMIR M.
dc.contributor.authorSOUZA, JOSE A.B.
dc.contributor.authorYAMAGUCHI, MITSUO
dc.contributor.authorSILVA, ANTONIO T. e
dc.contributor.authorMESQUITA, ROBERTO N. de
dc.contributor.authorSCURO, NIKOLAS L.
dc.contributor.authorANDRADE, DELVONEI A. de
dc.coverageInternacionalpt_BR
dc.date.accessioned2018-08-02T17:02:02Z
dc.date.available2018-08-02T17:02:02Z
dc.date.issued2018pt_BR
dc.description.abstractThis paper presents the sequence of activities to improve the thermal hydraulic analysis of the IEA-R1 research reactor to operate in safe conditions after power upgrade from 2 to 5 MW and core size reduction from 30 to 24 fuel assemblies. A realistic analysis needs the knowledge of the actual operation conditions (heat flow, flow rates) beyond the geometric data and the uncertainties associated with manufacturing and measures. A dummy fuel assembly was designed and constructed to measure the actual flow rate through the core fuel assemblies and its pressure drop. First results showed that the flow distribution over the core is nearly uniform. Nevertheless, the values are below than the calculated ones and the core bypass flow rate is greater than those estimated previously. Based on this, several activities were performed to identify and reduce the bypass flow, such as reduction of the flow rate through the sample irradiators, closing some unnecessary secondary holes on the matrix plate, improvement in the primary flow rate system and better fit of the core components on the matrix plate. A sub-aquatic visual system was used as an important tool to detect some bypass flow path. After these modifications, the fuel assemblies flow rate increased about 13%. Additional tests using the dummy fuel assembly were carried out to measure the internal flow distribution among the rectangular channels. The results showed that the flow rate through the outer channels is 10% - 15% lower than the internal ones. The flow rate in the channel formed between two adjacent fuel assemblies is an estimated parameter and it is difficult to measure because this is an open channel. A new thermal hydraulic analysis of the outermost plates of the fuel assemblies takes into account all this information. Then, a fuel design modification was proposed with the reduction of 50% in the uranium quantity in the outermost fuel plates. In order to avoid the oxidation of the outermost plates by high temperature, low flow rate, a reduction of 50% in the uranium density in the same ones was shown to be adequate to solve the problem.pt_BR
dc.format.extent54-69pt_BR
dc.identifier.citationUMBEHAUN, PEDRO E.; TORRES, WALMIR M.; SOUZA, JOSE A.B.; YAMAGUCHI, MITSUO; SILVA, ANTONIO T. e; MESQUITA, ROBERTO N. de; SCURO, NIKOLAS L.; ANDRADE, DELVONEI A. de. Thermal hydraulic analysis improvement for the IEA-R1 research reactor and fuel assembly design modification. <b>World Journal of Nuclear Science and Technology</b>, v. 8, n. 2, p. 54-69, 2018. DOI: <a href="https://dx.doi.org/10.4236/wjnst.2018.82006">10.4236/wjnst.2018.82006</a>. Disponível em: http://repositorio.ipen.br/handle/123456789/29014.
dc.identifier.doi10.4236/wjnst.2018.82006pt_BR
dc.identifier.fasciculo2pt_BR
dc.identifier.issn2161-6795pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0002-6689-3011
dc.identifier.orcidhttps://orcid.org/0000-0002-5355-0925
dc.identifier.orcidhttps://orcid.org/0000-0002-7308-5784
dc.identifier.orcidhttps://orcid.org/0000-0002-2887-0759
dc.identifier.percentilfiSem Percentilen
dc.identifier.percentilfiCiteScoreSem Percentil CiteScore
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/29014
dc.identifier.vol8pt_BR
dc.relation.ispartofWorld Journal of Nuclear Science and Technologypt_BR
dc.rightsopenAccesspt_BR
dc.subjectthermal hydraulics
dc.subjectreactors
dc.subjectresearch reactors
dc.subjecturanium
dc.subjectfuel assemblies
dc.subjectiear-1 reactor
dc.subjectflow rate
dc.subjectloss of coolant
dc.subjectmaterials testing reactors
dc.subjecteccs
dc.titleThermal hydraulic analysis improvement for the IEA-R1 research reactor and fuel assembly design modificationpt_BR
dc.typeArtigo de periódicopt_BR
dspace.entity.typePublication
ipen.autorMITSUO YAMAGUCHI
ipen.autorNIKOLAS LYMBERIS SCURO
ipen.autorDELVONEI ALVES DE ANDRADE
ipen.autorROBERTO NAVARRO DE MESQUITA
ipen.autorANTONIO TEIXEIRA E SILVA
ipen.autorJOSE ANTONIO BATISTA DE SOUZA
ipen.autorWALMIR MAXIMO TORRES
ipen.autorPEDRO ERNESTO UMBEHAUN
ipen.codigoautor1338
ipen.codigoautor14552
ipen.codigoautor1258
ipen.codigoautor1375
ipen.codigoautor1085
ipen.codigoautor1274
ipen.codigoautor188
ipen.codigoautor754
ipen.contributor.ipenauthorMITSUO YAMAGUCHI
ipen.contributor.ipenauthorNIKOLAS LYMBERIS SCURO
ipen.contributor.ipenauthorDELVONEI ALVES DE ANDRADE
ipen.contributor.ipenauthorROBERTO NAVARRO DE MESQUITA
ipen.contributor.ipenauthorANTONIO TEIXEIRA E SILVA
ipen.contributor.ipenauthorJOSE ANTONIO BATISTA DE SOUZA
ipen.contributor.ipenauthorWALMIR MAXIMO TORRES
ipen.contributor.ipenauthorPEDRO ERNESTO UMBEHAUN
ipen.date.recebimento18-08pt_BR
ipen.identifier.fiSem F.I.pt_BR
ipen.identifier.fiCiteScoreSem CiteScore
ipen.identifier.ipendoc24804pt_BR
ipen.type.genreArtigo
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sigepi.autor.atividadeUMBEHAUN, PEDRO E.:754:420:Spt_BR
sigepi.autor.atividadeTORRES, WALMIR M.:188:450:Npt_BR
sigepi.autor.atividadeSOUZA, JOSE A.B.:1274:410:Npt_BR
sigepi.autor.atividadeYAMAGUCHI, MITSUO:1338:420:Npt_BR
sigepi.autor.atividadeSILVA, ANTONIO T. E:1085:420:Npt_BR
sigepi.autor.atividadeMESQUITA, ROBERTO N. DE:1375:420:Npt_BR
sigepi.autor.atividadeSCURO, NIKOLAS L.:14552:420:Npt_BR
sigepi.autor.atividadeANDRADE, DELVONEI A. DE:1258:420:Npt_BR
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