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Oral Presentations


SESSION:
CompositeMonPM3-R8
Monteiro International Symposium on Composite, Ceramic & Nano Materials Processing, Characterization & Applications (10th Intl. Symp.)
Mon. 21 Oct. 2024 / Room: Ariadni B
Session Chairs: Afonso Rangel Garcez De Azevedo; Henry Alonso Colorado Lopera; Student Monitors: TBA

16:05: [CompositeMonPM309] OS
SIMULATION OF A HYPOTHETICAL PWR FUEL ELEMENT WITH MOLYBDENIUM-DOPEED 316 STEEL CLADDING
Thomaz Jacintho Lopes1; Ary Machado De Azevedo2; Marcos Paulo Cavaliere de Medeiros2; Sergio Monteiro2; Fernando Manuel Araújo Moreira2
1Military Institute of Engineering, Duque de Caxias, Brazil; 2Military Institute of Engineering, Rio de Janeiro, Brazil
Paper ID: 211 [Abstract]

This study explores the importance of simulations conducted with MCNP5 and the modifications implemented in 316 steel to optimize energy efficiency in nuclear power production. Molybdenum (Mo) is investigated as a promising additive due to its low absorption cross-section for thermal neutrons, which enhances neutron participation in fission and heat generation. Using the MCNP5 code, simulations were performed to analyze a hypothetical UO2 fuel element with different enrichment zones to evaluate its performance[1-3]. The results indicate that incorporating molybdenum into the fuel cladding alloy significantly impacts neutron production, suggesting that this addition might affect energy generation efficiency. In summary, this study highlights the potential of molybdenum as an additive to improve nuclear fuel performance[4-8], promoting safer, more efficient, and sustainable nuclear energy. The comparison of the results from the two simulations allowed for the assessment of the impact of molybdenum inclusion on the criticality of the simulated fuel. Conversely, if the inclusion of molybdenum does not positively influence or even reduce the fuel's criticality, this suggests that such a strategy is not viable for optimizing nuclear fuel performance. Therefore, the results of this analysis have significant implications for the development of more efficient and environmentally sustainable nuclear fuels. The effective multiplication factor (keff) obtained for the clad rod under study was keff=1.12086 ± 0.00064, while the reference value without doping was keff=1.04355 ± 0.00076, resulting in a relative percentage deviation of approximately 6.897%. Doping 316 steel with molybdenum nanoparticles presented a significant alteration in neutron production, suggesting that this addition may compromise energy generation efficiency.

References:
[1] MURTY, K. Linga; CHARIT, Indrajit. Structural materials for Gen-IV nuclear reactors: Challenges and opportunities. Journal of nuclear materials, v. 383, n. 1-2, p. 189-195, 2008.
[2] LAMARSH, John R. et al. Introduction to nuclear engineering. Upper Saddle River, NJ: Prentice hall, 2001.
[3] DUDERSTADT, James J.; HAMILTON, Louis J. Nuclear reactor analysis. Wiley, 1976.
[4] LI, Bingbing et al. Combined role of molybdenum and nitrogen in Limiting corrosion and pitting of super austenitic stainless steel. Heliyon, 2024.
[5] ZHAO, Jiaxuan et al. Fiber Laser Fillet Welding of Nb1Zr Thin Tube and Molybdenum End Plug in Ultra-high-Temperature Heat Pipe. Journal of Materials Engineering and Performance, p. 1-14, 2024.
[6] ZHANG, Chi et al. Molybdenum-14Rhenium alloy—The most promising candidate for high-temperature semiconductor substrate materials. Journal of Alloys and Compounds, v. 991, p. 174391, 2024.
[7] ISHIKAWA, Kyohei et al. Effect of Molybdenum Content on the Hardenability and Precipitation Behaviors of Boron Steel Austenitized at High Temperatures. ISIJ International, v. 64, n. 5, p. 847-858, 2024.
[8] , Qi et al. Research status and progress of welding technologies for molybdenum and molybdenum alloys. Metals, v. 10, n. 2, p. 279, 2020.


16:25: [CompositeMonPM310] OS
SIMULATION OF A HYPOTHETICAL PWR FUEL ASSEMBLY FEATURING MOLYBDENUM-DOPED ZIRCALOY CLADDING
Thomaz Jacintho Lopes1; Ary Machado De Azevedo2; Marcos Paulo Cavaliere de Medeiros2; Sergio Monteiro2; Fernando Manuel Araújo Moreira2
1Military Institute of Engineering, Duque de Caxias, Brazil; 2Military Institute of Engineering, Rio de Janeiro, Brazil
Paper ID: 212 [Abstract]

The advancement of materials research for the nuclear industry is growing as energy demand increases [1],[2]. As a result, new materials are being explored to improve the efficiency of nuclear applications. Molybdenum has been studied for decades as an alloying element due to its low thermal neutron absorption cross-section and high strength under nuclear reactor temperature conditions [3],[4]. A critical reactor condition is understanding how fuel rods behave during the fission reaction of UO2 pellets [5],[6] and, consequently, how heat transfer occurs in this process. To understand these key characteristics, a study was conducted on the criticality of a fuel rod clad with Zircaloy doped with molybdenum nanoparticles [7],[8] using MCNP code simulations. Simulations of the fuel element were performed with a 3.2%, 2.5%, and 1.9% UO2 enrichment distribution based on a hypothetical PWR reactor model [6]. A hypothetical fuel element for a hypothetical PWR reactor was simulated using the MCNP5 software. The element consisted of 25 fuel rods with UO2 pellets with three enrichment zones (3.2%, 2.5%, and 1.9%), as shown in Figure 1, and a height of 3.6 m. The kcode was used in the simulation to calculate the criticality of the simulated fuel. 10,000 neutrons per cycle and a total of 100 cycles were used, with 50 of them being passive. To achieve the objective of the work, the first simulation was performed with pure Zircaloy-4, and this result was considered as the reference standard criticality for the fuel element. The second simulation was performed with this alloy doped with 10% molybdenum.The result obtained for the effective multiplication factor (kef f ) with the coated rod under study was equal to kef f = 1.314503 ± 0.0007, which when compared to the reference value without doping kef f = 1.39207 ± 0.00072, a relative percentage deviation of approximately |δ| ≈ 5.57% is obtained. Doping Zircaloy with molybdenum nanoparticles does not significantly alter neutron production. This enables the improvement of the alloy without loss of energy production efficiency. The results of the simulations indicate that the doping of Zircaloy with molybdenum nanoparticles does not significantly alter the neutron production of the fuel rod. This is an important finding, as it suggests that the addition of molybdenum nanoparticles can improve the properties of the Zircaloy alloy without sacrificing its efficiency in terms of energy production. The relative percentage deviation of |δ| ≈ 5.57% between the kef f values for the doped and undoped rods is considered to be small. This suggests that the doping of Zircaloy with molybdenum nanoparticles does not have a significant impact on the criticality of the fuel rod. Overall, the results of this study suggest that the doping of Zircaloy with molybdenum nanoparticles is a promising approach for improving the properties of the alloy without sacrificing its efficiency in terms of energy production. Further research is needed to confirm these findings and to explore the potential benefits of molybdenum doping in more detail.

References:
[1] MURTY, K. Linga; CHARIT, Indrajit. Structural materials for Gen-IV nuclear reactors: Challenges and opportunities. Journal of nuclear materials, v. 383, n. 1-2, p. 189-195, 2008.
[2] LAMARSH, John R. et al. Introduction to nuclear engineering. Upper Saddle River, NJ: Prentice hall, 2001.
[3] DUDERSTADT, James J.; HAMILTON, Louis J. Nuclear reactor analysis. Wiley, 1976.
[4] LI, Bingbing et al. Combined role of molybdenum and nitrogen in Limiting corrosion and pitting of super austenitic stainless steel. Heliyon, 2024.
[5] ZHAO, Jiaxuan et al. Fiber Laser Fillet Welding of Nb1Zr Thin Tube and Molybdenum End Plug in Ultra-high-Temperature Heat Pipe. Journal of Materials Engineering and Performance, p. 1-14, 2024.
[6] ZHANG, Chi et al. Molybdenum-14Rhenium alloy—The most promising candidate for high-temperature semiconductor substrate materials. Journal of Alloys and Compounds, v. 991, p. 174391, 2024.
[7] ISHIKAWA, Kyohei et al. Effect of Molybdenum Content on the Hardenability and Precipitation Behaviors of Boron Steel Austenitized at High Temperatures. ISIJ International, v. 64, n. 5, p. 847-858, 2024.
[8] ZHU, Qi et al. Research status and progress of welding technologies for molybdenum and molybdenum alloys. Metals, v. 10, n. 2, p. 279, 2020.


16:45: [CompositeMonPM311] OS
COMPARATIVE CRITICALITY ASSESSMENT OF A HYPOTHETICAL FUEL ELEMENT WITH 316 STAINLESS STEEL-CLAD RODS DOPED WITH SiC THROUGH COMPUTATIONAL SIMULATION: AN UPDATED ANALYSIS
Ary Machado De Azevedo1; Thomaz Jacintho Lopes2; Sergio Monteiro1; Marcos Paulo Cavaliere de Medeiros1; Fernando Manuel Araújo Moreira1; André Ben-Hur Da Silva Figueiredo1
1Military Institute of Engineering, Rio de Janeiro, Brazil; 2Military Institute of Engineering, Duque de Caxias, Brazil
Paper ID: 219 [Abstract]

This study explored the influence of incorporating silicon carbide (SiC) nanoparticles into Stainless Steel 316 on the performance of nuclear fuel using computational simulations with the MCNP5 software[1]. The findings revealed that the introduction of SiC had minimal impact on the effective multiplication factor (keff), suggesting that this modification could be a viable approach to enhancing fuel characteristics without compromising efficacy[2-3]]. Furthermore, the integration of SiC could provide added advantages such as improved thermal stability and resistance to corrosion. These results underscore the potential of SiC as a promising additive for enhancing the safety and efficiency of nuclear fuel elements in reactors, opening avenues for future advancements and research in nuclear energy[4-5]. The results for the effective multiplication factor (keff) with a rod coated and doped with 10% SiC showed keff = 1.12759 ± 0.00064. Compared to the undoped reference value of keff = 1.12086 ± 0.00064, there is a relative increase in criticality of approximately 0.6%. The computational simulation using MCNP5 with kcode provided a detailed analysis of nuclear fuel criticality. The data indicate that doping Stainless Steel 316 with SiC nanoparticles increased the effective multiplication factor (keff) by about 0.6%. This suggests that adding SiC significantly affects neutron production, which is crucial for the safety and efficiency of nuclear reactors[6]. These results point to potential improvements in nuclear fuel performance. Including SiC may offer additional benefits such as greater thermal stability, corrosion resistance, and reduced deformation, contributing to the safety and longevity of fuel elements[7-8]. Moreover, maintaining energy production without compromising neutron efficiency is promising, allowing for advancements in the materials used in nuclear reactor construction. Therefore, the neutron results obtained in this simulation highlight SiC's potential as an effective additive to enhance nuclear fuel properties, paving the way for future research and developments in nuclear energy.

References:
[1] MURTY, K. Linga; CHARIT, Indrajit. Structural materials for Gen-IV nuclear reactors: Challenges and opportunities. Journal of nuclear materials, v. 383, n. 1-2, p. 189-195, 2008.
[2] LAMARSH, John R. et al. Introduction to nuclear engineering. Upper Saddle River, NJ: Prentice hall, 2001.
[3] DUDERSTADT, James J.; HAMILTON, Louis J. Nuclear reactor analysis. Wiley, 1976.
[4] PETTERSSON, Kjell et al. Nuclear fuel behaviour in loss-of-coolant accident (LOCA) conditions. 2009.
[5] OZBEN, Tamer; KILICKAP, Erol; CAKIR, Orhan. Investigation of mechanical and machinability properties of SiC particle reinforced Al-MMC. Journal of materials processing technology, v. 198, n. 1-3, p. 220-225, 2008.
[6] AKBARPOUR, M. R. et al. Microstructural development and mechanical properties of nanostructured copper reinforced with SiC nanoparticles. Materials Science and Engineering: A, v. 568, p. 33-39, 2013.
[7] ISHIKAWA, Kyohei et al. Effect of Molybdenum Content on the Hardenability and Precipitation Behaviors of Boron Steel Austenitized at High Temperatures. ISIJ International, v. 64, n. 5, p. 847-858, 2024.
[8] PINEM, Surian; SEMBIRING, Tagor Malem; SURBAKTI, Tukiran. Neutronic parameters analysis of a PWR fuel element using silicon carbide claddings with SRAC2006/NODAL3 codes. In: AIP Conference Proceedings. AIP Publishing, 2019.


17:05: [CompositeMonPM312] OS
SIMULATION OF A HYPOTHETICAL PWR FUEL ELEMENT WITH 316 STEEL CLADDING ENHANCED BY GRAPHENE NANOTUBES
Thomaz Jacintho Lopes1; Ary Machado De Azevedo2; Sergio Monteiro2; Marcos Paulo Cavaliere de Medeiros2; Fernando Manuel Araújo Moreira2
1Military Institute of Engineering, Duque de Caxias, Brazil; 2Military Institute of Engineering, Rio de Janeiro, Brazil
Paper ID: 206 [Abstract]

This study explores the significance of simulations performed in MCNP5 and the modifications applied to 316 steel to enhance energy efficiency in nuclear power production. Graphene Nanotubes (GNTs) are examined as promising additives owing to their low absorption cross-section for thermal neutrons, facilitating increased neutron involvement in fission and heat generation. Using the MCNP5 code[1], simulations were carried out to analyze a hypothetical UO2 fuel element with varying enrichment zones to assess its performance[2,3]. The findings underscore the substantial impact of incorporating graphene nanotubes[4] into the fuel cladding alloy on neutron production, implying a potential compromise in energy generation efficiency. The comparison between the results of two simulations allowed us to assess the impact of including graphene nanotubes[5,6] on the criticality of the simulated fuel. If the addition of these nanotubes [7] results in an improvement in criticality, this may indicate superior performance of the nuclear reactor, with higher fuel efficiency and reduced nuclear waste generation. On the other hand, if the inclusion does not positively affect or even reduces criticality, this suggests that this strategy is not viable for optimizing nuclear fuel performance [8]. Therefore, the results of this analysis have significant implications for the development of more efficient and environmentally sustainable nuclear fuels. The result of the effective multiplication factor (keff) for the studied clad rod was keff=1.12086 ± 0.00064, while the reference value without doping was keff=1.13565 ± 0.00076, resulting in a relative percentage deviation of approximately Δ = -1.32%. Doping 316 steel with graphene nanotubes causes a significant alteration in neutron production, which may compromise efficiency in energy generation.

References:
[1] MURTY, K. Linga; CHARIT, Indrajit. Structural materials for Gen-IV nuclear reactors: Challenges and opportunities. Journal of nuclear materials, v. 383, n. 1-2, p. 189-195, 2008.
[2] LAMARSH, John R. et al. Introduction to nuclear engineering. Upper Saddle River, NJ: Prentice hall, 2001.
[3] ] DUDERSTADT, James J.; HAMILTON, Louis J. Nuclear reactor analysis. Wiley, 1976.
[4] XU, Zhengwu et al. Flexible, high temperature resistant and highly efficient E-heating graphene/polyimide film. AIP Advances, v. 14, n. 1, 2024..
[5] ABIOYE, Samson Oluwafemi et al. Graphene-based nanomaterials for the removal of emerging contaminants of concern from water and their potential adaptation for point-of-use applications. Chemosphere, p. 141728, 2024.
[6] GÜZEL, Tamer; İŞLEK, Yasemin; YILDIZ, Oğuzhan. Morphological and Thermal Characterization of Low-Cost Graphene Produced by Electrochemical Exfoliation Method. Sakarya University Journal of Science, v. 28, n. 2, p. 283-293, 2024.
[7] HOU, Yandong et al. Numerical simulation study of boiling Critical Heat Flux characteristics of graphene nanofluids. Progress in Nuclear Energy, v. 172, p. 105228, 2024.
[8] YAN, Jianwei; YI, Shangjie; YUAN, Xiaoyu. Graphene and its composites: A review of recent advances and applications in logistics transportation. Packaging Technology and Science, v. 37, n. 4, p. 335-361, 2024.


17:25 POSTERS/EXHIBITION - Ballroom Foyer