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dc.contributoren-US
dc.creatorSlobodchuk, V.I.
dc.creatorAvramova, E.A.
dc.creatorShchennikova, E.M.
dc.creatorShal'kov, D.A.
dc.date2018-02-21
dc.date.accessioned2018-02-23T17:16:28Z
dc.date.available2018-02-23T17:16:28Z
dc.identifierhttps://knepublishing.com/index.php/KnE-Engineering/article/view/1627
dc.identifier10.18502/keg.v3i3.1627
dc.identifier.urihttp://ridda2.utp.ac.pa/handle/123456789/4343
dc.descriptionThe paper evaluates the possibility of modeling the heat transfer phenomena in a liquid-metal coolant using a light water test facility. A large nuclear power reactor (like the BN-1200 project) was selected as a reactor installation to be modeled. To validate the model, the similarity theory and the “black box” method were used. The paper uses the experience of a number of researchers in this field, in particular, the accepted assumptions which do not result in serious loss in modeling accuracy. The governing criteria of similarity were estimated based on the fundamental differential equations of convective heat transfer, so were the conditions under which it is possible to model sodium coolant by using  light water with adequate accuracy. The paper presents the scales of the parameters used for the model - reactor comparison. Dependence curves of certain scales with regard to others are constructed, and the possibility of achieving similarity of certain parameters in modeling was estimated. Recommendations are provided on designing a water test model of the BN reactor and on carrying out experiments using this test model.en-US
dc.formatapplication/pdf
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dc.languageeng
dc.publisherKnE Publishingen-US
dc.relationhttps://knepublishing.com/index.php/KnE-Engineering/article/view/1627/3845
dc.relationhttps://knepublishing.com/index.php/KnE-Engineering/article/view/1627/3846
dc.rightsinfo:eu-repo/semantics/embargoedAccessen-US
dc.sourceKnE Engineering; XIII International Youth Scientific and Practical Conference "FUTURE OF ATOMIC ENERGY - AtomFuture 2017"; 279-290en-US
dc.source2518-6841
dc.titlePossibility of Simulating Forced Convection in Fast Neutron Reactors Using a Light Water Test Facilityen-US
dc.typeinfo:eu-repo/semantics/article
dc.typeinfo:eu-repo/semantics/publishedVersion
dc.typePeer-reviewed Articleen-US


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  • 2017: 6th Engineering, Science and Technology Conference - Panama (ESTEC 2017)
    The 6th Engineering, Science and Technology Conference (ESTEC 2017) organized by the Universidad Tecnologica de Panama (UTP) is the most relevant conference, engineering-based, of our country. The topics of the conference are focused on areas of interest of Panama and the Latin America region, including: agroindustry, astronomy, bioengineering, education on engineering, energy and environment, ICT engineering, infrastructure and construction, logistics and transportation, manufacturing processes and material science, robotic, automation and artificial intelligence. This year, ESTEC partnered with IEEE Panama Section to ensure the quality of the peer-reviewed process; we received more than 180 full papers from 20 countries and 50% of those were accepted to participate in the conference and will be published in the conference’s proceeding. Furthermore, the conference included technical tours to the Cocoli’s Gate and the Miraflores Visitors Center of The Panama Canal and to the Wind Power Park in Penonome, Panama.

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