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<doi>0676-cd</doi>
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<article-title>Reactivity Sensitivity Analysis for a Fuel Rod with Biconcave Cross Section in a PWR</article-title>
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<author>M. V. A. Oliveira<sup>a</sup>, D. G. Teixeira<sup>b</sup>, T. D. Roberto<sup>c</sup>, E. Henrice Jr.<sup>d</sup> and P.F. Frutuoso e Melo<sup>e</sup></author>

<aff>Graduate Program of Nuclear Engineering, Federal University of Rio de Janeiro/COPPE, Brazil</aff>

<email><a href="mailto:moliveira@nuclear.ufrj.br"><sup>a</sup>moliveira@nuclear.ufrj.br</a></email>

<email><a href="mailto:dteixeira@nuclear.ufrj.br"><sup>b</sup>dteixeira@nuclear.ufrj.br</a></email>

<email><a href="mailto:troberto@con.ufrj.br"><sup>c</sup>troberto@con.ufrj.br</a></email>

<email><a href="mailto:ejunior@nuclear.ufrj.br"><sup>d</sup>ejunior@nuclear.ufrj.br</a></email>

<email><a href="mailto:frutuoso@nuclear.ufrj.br"><sup>e</sup>frutuoso@nuclear.ufrj.br</a></email>

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<title>ABSTRACT</title>
<p>The objective of this work is to make a preliminary reactivity analysis of an original design of a fuel rod with biconcave cross section. In this phase of the project, reactivity sensitivity tests were carried out through the subchannel area, considering UO<sub>2</sub> fuel enriched at 4&#37; and 5&#37;, for the fuel temperatures of 600K and 900K. We observed that the best area ranges were the regions from 7.5 to 7.9 cm<sup>2</sup> for the UO<sub>2</sub> enrichment of 5&#37; and from 6.2 to 6.6 cm<sup>2</sup> for the UO<sub>2</sub> enrichment of 4&#37;. The next step will be a study of the fuel temperature coefficient.</p>
<p><italic>Keywords: </italic>Innovative designs, Nuclear fuels, Hollow biconcave fuel rod, Reactivity, SERPENT, Reactivity factor.</p>
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