Assessment of uranium dioxide fuel performance with the addition of beryllium oxide
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2017
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INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
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The Fukushima Daiichi accident in 2011 pointed the problem related to the hydrogen generation under accident
scenarios due to the oxidation of zirconium-based alloys widely used as fuel rod cladding in water-cooled
reactors. This problem promoted research programs aiming the development of accident tolerant fuels (ATF)
which are fuels that under accident conditions could keep longer its integrity enabling the mitigation of the
accident effects. In the framework of the ATF program, different materials have been studied to be applied as
cladding to replace zirconium-based alloy; also efforts have been made to improve the uranium dioxide thermal
conductivity doping the fuel pellet. This paper evaluates the addition of beryllium oxide (BeO) to the uranium
dioxide in order to enhance the thermal conductivity of the fuel pellet. Investigations performed in this area
considering the addition of 10% in volume of BeO, resulting in the UO2-BeO fuel, have shown good results
with the improvement of the fuel thermal conductivity and the consequent reduction of the fuel temperatures
under irradiation. In this paper, two models obtained from open literature for the thermal conductivity of UO2-
BeO fuel were implemented in the FRAPCON 3.5 code and the results obtained using the modified code
versions were compared. The simulations were carried out using a case available in the code documentation
related to a typical pressurized water reactor (PWR) fuel rod irradiated under steady state condition. The results
show that the fuel centerline temperatures decrease with the addition of BeO, when compared to the
conventional UO2 pellet, independent of the model applied.
Como referenciar
MUNIZ, RAFAEL O.R.; GIOVEDI, CLAUDIA; ABE, ALFREDO; GOMES, DANIEL S.; AGUIAR, AMANDA A.; SILVA, ANTONIO T. Assessment of uranium dioxide fuel performance with the addition of beryllium oxide. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 22-27, 2017, Belo Horizonte, MG. Proceedings... Rio de Janeiro, RJ: Associação Brasileira de Energia Nuclear, 2017. Disponível em: http://repositorio.ipen.br/handle/123456789/28186. Acesso em: 28 Mar 2025.
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