Editors: | F. Kongoli, P. Assis, H.A.C. Lopera, S. Diaz, V. Scarpini Candido |
Publisher: | Flogen Star OUTREACH |
Publication Year: | 2024 |
Pages: | 288 pages |
ISBN: | 978-1-998384-18-1 (CD) |
ISSN: | 2291-1227 (Metals and Materials Processing in a Clean Environment Series) |
Advancements in materials research for the nuclear industry coincide with the rising energy demand [1],[2]. Consequently, discussions around new materials aim to enhance the efficiency of their applications within the nuclear domain. An essential aspect of reactor operation involves understanding the behavior of fuel rods during UO2 pellet fission reactions [3],[4], and consequently, the heat transfer mechanisms involved in this process. To delve into these pivotal characteristics, a study was conducted on the criticality of a fuel rod clad with Zircaloy doped with graphene nanotubes [6],[7] via simulation using the MCNP code. Simulations of the fuel element were conducted with enrichment distributions of 3.2%, 2.5%, and 1.9% of UO2, based on a hypothetical PWR type reactor model [5]. The hypothetical scenario considered a fuel for a PWR reactor comprising 25 fuel rods with UO2 pellets exhibiting three enrichment zones of 3.2%, 2.5%, and 1.9%, as illustrated in Figure 1, with a height of 3.6 m, simulated using the MCNP5 software. To fulfill the study's objective, the first simulation involved pure Zircaloy-4, serving as the reference standard for criticality of the fuel element. Subsequently, another simulation entailed this alloy doped with 10% of graphene nanotubes. The result obtained for the effective multiplication factor (keff) with the coated rod under study was keff = 1.39132 ± 0.00064. When compared to the reference value of the hypothetical fuel element keff = 1.39207 ± 0.05, a relative percentage deviation of approximately δ ≈ 0.1% was observed. Based on this analysis, it can be concluded that doping Zircaloy-4 with 10% graphene nanotubes does not significantly alter the criticality parameter, indicating no significant changes in the neutronic parameters. Subsequent steps of the study will focus on assessing the heat transfer efficiency of the doped cladding and any associated mechanical alterations.