Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario

dc.creatorGIOVEDI, CLAUDIA
dc.creatorABE, ALFREDO
dc.creatorMUNIZ, RAFAEL O.R.
dc.creatorGOMES, DANIEL de S.
dc.creatorSILVA, ANTONIO T. e
dc.creatorMARTINS, MARCELO R.
dc.creatorINTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
dc.date2018-01-02T12:39:13Z
dc.date2018-01-02T12:39:13Z
dc.dateOctober 22-27, 2017
dc.date.accessioned2023-09-28T14:05:04Z
dc.date.available2023-09-28T14:05:04Z
dc.identifierhttp://repositorio.ipen.br/handle/123456789/28187
dc.identifier.urihttps://repositorioslatinoamericanos.uchile.cl/handle/2250/8998441
dc.descriptionAccident tolerant fuels (ATF) has been studied since the Fukushima Daiichi accident in the research efforts to develop new materials which under accident scenarios could maintain the fuel rod integrity for a longer period compared to the cladding and fuel system usually utilized in Pressurized Water Reactors (PWR). The efforts have been focused on new materials applied as cladding, then iron-base alloys appear as a possible candidate. The aim of this paper is to implement modifications in a fuel performance code to evaluate the behavior of ironbased alloys under Loss-of-Coolant Accident (LOCA) scenario. For this, initially the properties related to the thermal and mechanical behavior of iron-based alloys were obtained from the literature, appropriately adapted and introduced in the fuel performance code subroutines. The adopted approach was step by step modifications, where different versions of the code were created. The assessment of the implemented modification was carried out simulating an experiment available in the open literature (IFA-650.5) related to zirconium-based alloy fuel rods submitted to LOCA conditions. The obtained results for the iron-based alloy were compared to those obtained using the regular version of the fuel performance code for zircaloy-4. The obtained results have shown that the most important properties to be changed are those from the subroutines related to the mechanical properties of the cladding. The results obtained have shown that the burst is observed at a longer time for fuel rods with iron-based alloy, indicating the potentiality of this material to be used as cladding with ATF purposes.
dc.publisherAssocia????o Brasileira de Energia Nuclear
dc.rightsopenAccess
dc.subjectaccident-tolerant nuclear fuels
dc.subjectcladding
dc.subjectcomputerized simulation
dc.subjectf codes
dc.subjectfuel rods
dc.subjectiron alloys
dc.subjectloss of coolant
dc.subjectperformance
dc.subjectpwr type reactors
dc.subjectstainless steel-348
dc.titleModification of fuel performance code to evaluate iron-based alloy behavior under loca scenario
dc.typeTexto completo de evento
dc.coverageI
dc.localRio de Janeiro, RJ


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