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dc.contributor.authorROBERTO, Thiago D.-
dc.contributor.authorLAPA, Celso M. F.-
dc.contributor.authorALVIM, Antonio C. M-
dc.date.accessioned2018-02-08T14:17:07Z-
dc.date.available2018-02-08T14:17:07Z-
dc.date.issued2017-10-
dc.identifier.urihttp://carpedien.ien.gov.br:8080/handle/ien/2155-
dc.languageengpt_BR
dc.publisherInstituto de Engenharia Nuclearpt_BR
dc.rightsopenAccesspt_BR
dc.subjectACCIDENTAL CONDITIONSpt_BR
dc.titleSCALE ANALYSIS OF DECAY HEAT REMOVAL SYSTEM BETWEEN HTR-10 AND HTR-PM REACTORS UNDER ACCIDENTAL CONDITIONSpt_BR
dc.typeconferenceObjectpt_BR
dc.description.resumoThe 10 MW high-temperature gas-cooled test module (HTR-10) is a graphite-moderated and helium-cooled pebble bed reactor prototype that was designed to demonstrate the technical and safety feasibility of this type of reactor project under normal and accidental conditions. In addition, one of the systems responsible for ensuring the safe operation of this type of reactor is the passive decay heat removal system (DHRS), which operates using passive heat removal processes. A demonstration of the heat removal capacity of the DHRS under accidental conditions was analyzed based on a benchmark problem for design-based accidents on an HTR-10, i.e., the pressurized loss of forced cooling (PLOFC) described in technical reports produced by the International Atomic Energy Agency. In fact, the HTR-10 is also a proof-of-concept reactor for the high-temperature gas-cooled reactor pebble-bed module (HTR-PM), which generates approximately 25 times more heat than the HTR-10, with a thermal power of 250 MW, thereby requiring a DHRS with a higher system capacity. Thus, because an HTR-10 is a prototype reactor for an HTR-PM, a scaling analysis of the heat transfer process from the reactor to the DHRS was carried out between the HTR-10 and HTR-PM systems to verify the distortions of scale and the differences between the main dimensionless numbers from the two projectspt_BR
dc.publisher.countryBrasilpt_BR
dc.publisher.initialsIENpt_BR
dc.citation.issue2017pt_BR
dc.creator.affiliationPrograma de Engenharia Nuclear (PEN/ COPPE/UFRJ - RJ)-
dc.creator.affiliationInstituto de Engenharia Nuclear (IEN)-
dc.creator.affiliationPrograma de Engenharia Nuclear (PEN/ COPPE/UFRJ - RJ)-
Aparece nas coleções:Engenharia e Segurança de Reatores Nucleares - Trabalhos de Congresso

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