Thermochemical reactions in partially exposed nuclear fuel

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dc.contributor.author Elias, E. en
dc.contributor.author Hasan, D. en
dc.contributor.author Nekhamkin, Y. en
dc.date.accessioned 2017-09-19T12:48:55Z
dc.date.available 2017-09-19T12:48:55Z
dc.date.issued 2017 en
dc.description Papers presented at the 13th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics, Portoroz, Slovenia on 17-19 July 2017 . en
dc.description.abstract Oxidation of fuel-cladding during a hypothetical severe accident in light water reactors is theoretically investigated in an attempt to realistically simulate the time dependent heat generation in a partially uncovered reactor core. Two modes of oxidation, heterogeneous and homogeneous, are generally considered. Heterogeneous oxidation refers to chemical reactions with steam at the outer cladding surface in which a dense oxide layer is formed that physically hinders the oxidant from reaching the reacting metal. That mode of oxidation may not fully explain the kinetics of cladding oxidation following severe accident, where thermochemical reactions take place in pores and cracks inside the metal. A theoretical model is, therefore, developed to quantitatively understand the homogeneous oxidation of degraded fuel cladding. A dimensionless cracks’ concentration parameter, , is developed in order to study the effect of cracks on the ignition temperature of zirconium. A critical parameter, max  , is identified above which runaway ignition conditions are expected. Steam temperature and decay power are the main conditions leading to cladding heterogeneous ignition. Cracks density could be important for evaluating homogeneous oxidation of degraded cladding. en
dc.description.sponsorship International centre for heat and mass transfer. en
dc.description.sponsorship American society of thermal and fluids engineers. en
dc.format.extent 6 pages en
dc.format.medium PDF en
dc.identifier.uri http://hdl.handle.net/2263/62459
dc.language.iso en en
dc.publisher HEFAT en
dc.rights University of Pretoria en
dc.subject Thermochemical reactions en
dc.subject Nuclear fuel en
dc.title Thermochemical reactions in partially exposed nuclear fuel en
dc.type Presentation en


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