Total and partial loss of coolant experiments in an instrumented fuel assembly of IEA-R1 research reactor

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dc.contributor.authorMAPRELIAN, EDUARDOpt_BR
dc.contributor.authorTORRES, WALMIR M.pt_BR
dc.contributor.authorBELCHIOR JUNIOR, ANTONIOpt_BR
dc.contributor.authorUMBEHAUN, PEDRO E.pt_BR
dc.contributor.authorBERRETTA, JOSE R.pt_BR
dc.contributor.authorSABUNDJIAN, GAIANEpt_BR
dc.coverageInternacionalpt_BR
dc.date.accessioned2020-09-30T19:36:27Z
dc.date.available2020-09-30T19:36:27Z
dc.date.issued2020pt_BR
dc.description.abstractThe safety of nuclear facilities has been a growing global concern, mainly after the Fukushima nuclear accident. Studies on nuclear research reactor accidents such as the Loss of Coolant Accident (LOCA), many times considered a design basis accident, are important for ensure the integrity of the plant. A LOCA may lead to the partial or complete uncovering of the fuel assemblies and it is necessary to assure the decay heat removal as a safety condition. This work aimed to perform, in a safe way, partial and complete uncovering experiments for an Instrumented Fuel Assembly (IFA), in order to measure and compare the actual fuel temperatures behavior for LOCA in similar conditions to research reactors. A test section for experimental simulation of Loss of Coolant Accident named STAR was designed and built. The IFA was irradiated in the IEA-R1 core and positioned in the STAR, which was totally immersed in the reactor pool. Thermocouples were installed in the IFA to measure the clad and fluid temperatures in several axial and radial positions. Experiments were carried out for five levels of uncovering of IFA, being one complete uncovering and four partial uncovering, in two different conditions of decay heat. It was observed that the cases of complete uncovering of the IFA were the most critical ones, that is, those cases presented higher clad temperatures when compared with partial uncovering cases, for the specific conditions of heat decay intensity and dissipation analyzed. The maximum temperatures reached in all experiments were quite below the fuel blister temperature, which is around 500 °C. The STAR has proven to be a safe and reliable experimental apparatus for conducting loss of coolant experiments.pt_BR
dc.format.extent1-11pt_BR
dc.identifier.citationMAPRELIAN, EDUARDO; TORRES, WALMIR M.; BELCHIOR JUNIOR, ANTONIO; UMBEHAUN, PEDRO E.; BERRETTA, JOSE R.; SABUNDJIAN, GAIANE. Total and partial loss of coolant experiments in an instrumented fuel assembly of IEA-R1 research reactor. <b>Nuclear Engineering and Design</b>, v. 363, p. 1-11, 2020. DOI: <a href="https://dx.doi.org/10.1016/j.nucengdes.2020.110610">10.1016/j.nucengdes.2020.110610</a>. Disponível em: http://repositorio.ipen.br/handle/123456789/31409.
dc.identifier.doi10.1016/j.nucengdes.2020.110610pt_BR
dc.identifier.issn0029-5493pt_BR
dc.identifier.orcid0000-0001-9544-4509pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0001-9544-4509
dc.identifier.orcidhttps://orcid.org/0000-0002-2887-0759
dc.identifier.percentilfi75.00pt_BR
dc.identifier.percentilfiCiteScore66.17
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/31409
dc.identifier.vol363pt_BR
dc.relation.ispartofNuclear Engineering and Designpt_BR
dc.rightsopenAccesspt_BR
dc.subjectcomputer codes
dc.subjectcomputerized simulation
dc.subjectdata covariances
dc.subjectfuel assemblies
dc.subjectloss of coolant
dc.subjectnatural convection
dc.subjectr codes
dc.subjectradiosensitivity effects
dc.subjectreactor accident simulation
dc.subjectresearch reactors
dc.subjectsensitivity analysis
dc.titleTotal and partial loss of coolant experiments in an instrumented fuel assembly of IEA-R1 research reactorpt_BR
dc.typeArtigo de periódicopt_BR
dspace.entity.typePublication
ipen.autorGAIANE SABUNDJIAN
ipen.autorJOSE ROBERTO BERRETTA
ipen.autorPEDRO ERNESTO UMBEHAUN
ipen.autorANTONIO BELCHIOR JUNIOR
ipen.autorWALMIR MAXIMO TORRES
ipen.autorEDUARDO MAPRELIAN
ipen.codigoautor202
ipen.codigoautor710
ipen.codigoautor754
ipen.codigoautor6367
ipen.codigoautor188
ipen.codigoautor736
ipen.contributor.ipenauthorGAIANE SABUNDJIAN
ipen.contributor.ipenauthorJOSE ROBERTO BERRETTA
ipen.contributor.ipenauthorPEDRO ERNESTO UMBEHAUN
ipen.contributor.ipenauthorANTONIO BELCHIOR JUNIOR
ipen.contributor.ipenauthorWALMIR MAXIMO TORRES
ipen.contributor.ipenauthorEDUARDO MAPRELIAN
ipen.date.recebimento20-09
ipen.identifier.fi1.869pt_BR
ipen.identifier.fiCiteScore3.5
ipen.identifier.ipendoc27183pt_BR
ipen.identifier.iwosWoSpt_BR
ipen.range.fi1.500 - 2.999
ipen.range.percentilfi75.00 - 100.00
ipen.type.genreArtigo
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relation.isAuthorOfPublicatione05a9eb7-8471-4f24-9991-018ed148a2e2
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relation.isAuthorOfPublicationc8145d12-477e-4ddc-9c99-207115907d7d
relation.isAuthorOfPublication.latestForDiscoveryc8145d12-477e-4ddc-9c99-207115907d7d
sigepi.autor.atividadeSABUNDJIAN, GAIANE:202:420:Npt_BR
sigepi.autor.atividadeBERRETTA, JOSE R.:710:240:Npt_BR
sigepi.autor.atividadeUMBEHAUN, PEDRO E.:754:420:Npt_BR
sigepi.autor.atividadeBELCHIOR JUNIOR, ANTONIO:6367:450:Npt_BR
sigepi.autor.atividadeTORRES, WALMIR M.:188:450:Npt_BR
sigepi.autor.atividadeMAPRELIAN, EDUARDO:736:420:Spt_BR
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