Next Article in Journal
Ferroelectric Liquid Crystal Compound Lens Based on Pancharatnam–Berry Phase
Next Article in Special Issue
Optimization of Effective Doping Concentration of Emitter for Ideal c-Si Solar Cell Device with PC1D Simulation
Previous Article in Journal
Effects of Gradient Hot Rolled Deformation on Texture Evolution and Properties of 1561 Aluminum Alloy
 
 
Font Type:
Arial Georgia Verdana
Font Size:
Aa Aa Aa
Line Spacing:
Column Width:
Background:
Article

Mechanism and Properties of UO2–Graphene Composite Fuel Prepared by In Situ Synthesis

China Institute of Atomic Energy, Beijing 102413, China
*
Author to whom correspondence should be addressed.
Crystals 2022, 12(2), 230; https://doi.org/10.3390/cryst12020230
Submission received: 16 December 2021 / Revised: 30 January 2022 / Accepted: 31 January 2022 / Published: 7 February 2022
(This article belongs to the Special Issue Silicon and Graphene Based Materials and Related Devices)

Abstract

:
A nucleation method based on a composite of uranium dioxide (UO2) and graphene is presented by in situ synthesis, and the relevant mechanism and fuel properties are investigated. UO2–graphene composite fuel powders containing graphene volume (2%, 4%, 6%, and 8%) were prepared using a nucleation method through the reactive deposition of uranyl nitrate and aqueous ammonia on graphene by controlling the reaction parameters. The composite fuel pellets were prepared using spark plasma sintering (SPS). The results showed that the uniformity of UO2–graphene powder prepared by in situ synthesis reached up to 96.39%. An analysis on the relevant phase structure showed that only UO2 and graphene existed in the sintered pellets at 1723 K, graphene and UO2 were not destroyed during the reaction, and the pellet densities for the in-situ synthesis were 95.56%TD, 95.32%TD, 95.08%TD, and 94.76%TD for graphene contents of 2%, 4%, 6%, and 8%, respectively. The thermal conductivities of pellets at 293 K increased by 12.27%, 20.13%, 27.47%, and 34.13%, and by 18.36%, 35.00%, 47.07%, and 58.93% at 1273 K for 2%, 4%, 6%, and 8% graphene contents, respectively. The performance of graphene in the fuel was superior at high temperatures, which overcame shortcomings due to the low thermal conductivity of UO2 at high temperatures. SEM results showed that the grain sizes of the pellets prepared by synthesis in situ were 10–30 μm, and there was no obvious pore at the grain boundary because the grains were closely bound. The graphene was uniformly coated by UO2, and the thermal conductivity of the pellets improved upon the formation of a bridging heat conduction network.

1. Introduction

Uranium dioxide (UO2) has always been a nuclear fuel widely used in pressurized water reactor nuclear power plants due to its high melting point, high irradiation resistance, and good compatibility with cladding and coolants [1]. However, UO2 has a low thermal conductivity (7.5 W/m·K at room temperature and 2.8 W/m·K at 1273 K), which results in a radial temperature gradient of 2273–4273 K/cm inside the fuel pellets of UO2 in the running reactor. The maximum temperature in the center exceeds 1973 K, while at the edge it is only about 873 K; this gradient results in large thermal stresses and cracks. The cracking of pellets may increase the fission gas release rate, and the extremely high temperature at the fuel center may cause fuel irradiation swelling and limit the life of UO2 fuel [2,3,4,5].
After the Fukushima nuclear accident in Japan in 2011, the Advanced Fuels Working Group of the U.S. Office of Nuclear Energy adjusted the goal for research and development of the advanced fuel cycle technologies for light water reactors (LWRs) as follows: using standard UO2–Zr as the reference, improvements should be made to the resistance of fuels to serious accidents, the safety of reactors under conditions for serious accidents, and the performance of fuels under normal conditions via the research and development of accident-tolerant fuels (ATFs) [6,7]. Based on the ATF development program, the United States regards UO2 doped with a second phase as key for studies of the modification of high-performance nuclear fuels and has expended considerable efforts in this endeavor. Improving the thermal conductivity of UO2 through adding a second phase with excellent performance (high thermal conductivity, a small neutron absorption cross section, high melting point) represents a hotspot for research on advanced nuclear fuels.
As a promising second-phase additive in UO2 fuel pellets, graphene has a high melting point (~3773 K) and thermal conductivity (~3000 W/(m·K)) at room temperature, and is stable at high temperatures [8,9]. T. Yao et al. reported highly thermally conductive and mechanically strong UO2–graphene composite fuels using a metallurgical approach; the composite fuels possessed greatly improved thermal conductivities (74% and 162 wt.% enhancement at room temperature along the radial direction for 1 wt.% and 5 wt.% graphene composites), and they observed 150% improvement in fracture toughness compared to UO2 [8]. D. Zhang et al. reported a hydrothermal approach to synthesize UO2 and RGO sheets with an enhancement of approximately 35.4% in thermal conductivity [9]. Current research on UO2–graphene composite fuels remain in its infancy. In 2016, South Korea evaluated the safety of UO2–graphene composite fuels under working conditions, and their results showed that, in service, 5% graphene reduced the core temperature of the fuel from 2087 K to 1717 K and the surface temperature of the instantaneously activated cladding from 1228 K to 1125 K, which significantly improved the reactor power density and the maximum allowable fuel consumption [10].
In this study, a multi-step UO2 wet process was adopted to form an effective and firm combination between UO2 and graphene. In this process, small quantities of gas and liquid were produced, but these gases were collected and treated effectively. A nucleation method based on graphene enabled an in situ synthesis through the reactive deposition of a uranyl nitrate solution and ammonia water on graphene, and through controlling the reaction parameters, UO2–graphene composite fuel powders containing 2%, 4%, 6%, and 8% graphene (based on nuclear reactor core design requirements and the economic needs of the power plants, the reactor should have a certain 235U loading capacity, and the estimated graphene content should not exceed 8%) were prepared, and the composite fuel pellets were formed via spark plasma sintering (SPS). The relevant mechanisms and fuel properties were investigated.

2. Experiment

2.1. Materials and Methods

The graphene purity was > 95% (impurities: free carbon: ~4.7%, Fe: ~0.3%) [11]. The purity of the UO2 powder was > 99.5%, with a median particle size of ~30 μm [12]. Concentrated sulfuric acid (18.4 mol/L), concentrated nitric acid (15.2 mol/L), ammonia (13.33 mol/L), anhydrous ethanol (98%, mass fraction), and Ar-5% H2 mixed gas were used.

2.2. Preparation of UO2–Graphene Composite Powders by In Situ Synthesis

(1) Preparation of uranyl nitrate.
UO2 + HNO3→UO2(NO3)·6H2O
We measured 30 mL of concentrated nitric acid into a beaker and slowly added 10 g of UO2 powder to the concentrated nitric acid. The solution was heated in a 333 K water bath and slowly stirred until the UO2 dissolved completely to form a yellowish mixed solution of uranyl nitrate and concentrated nitric acid.
(2) Preparation of graphene dispersion.
We weighed 0.04 g of raw graphene into the uranyl nitrate mixture and it was sonicated for 2 h to obtain a dispersed mixture of graphene and uranyl nitrate.
(3) Preparation of heavy uranium amide ((NH4)2U2O7) by in situ synthesis.
We added 50 mL of concentrated aqueous ammonia into the mixed solution and stirred it slowly to produce the following chemical reaction:
UO2(NO3)·6H2O + NH3·H2O→(NH4)2U2O7 + H2O
The pH value of the solution was adjusted (7–9) so that UO22+ in the solution formed a complex ion dominated by three nuclei and precipitates, (NH4)2U2O7. Due to the large surface energy of graphene, (NH4)2U2O7 can first nucleate and grow on the surface of the graphene, which allows the precipitate to wrap the graphene.
(4) Decomposition of heavy uranium amide ((NH4)2U2O7) and reduction of U3O8.
(NH4)2U2O7→2UO3 + NH3↑ + H2O (623 K)
UO3 + H2→UO2 + H2O (873 K)
The graphene and (NH4)2U2O7 precipitate mixture was heated in a vacuum at 623 K for 4 h. Upon complete decomposition of (NH4)2U2O7, the chamber was filled with Ar-5%H2 gas, held at 873 K for 4 h, and then cooled to room temperature. We then crushed the mixed powder and sifted it through a 100-mesh screen. Finally, a UO2–graphene 2% mixed powder was obtained by in situ synthesis, as shown in Figure 1, with UO2–graphene powders of 4%, 6%, and 8% also prepared in the same manner [10,13].

2.3. Preparation of UO2–Graphene Composite Fuel Pellets

The pellet preparation experiment was carried out for the mixed powders prepared by in situ synthesis. The procedure was as follows: the appropriate quantityUO2–graphene mixed powder was weighed into a graphite mold and sintered for 1 h at 1723 K and 60 MPa to yield UO2–graphene composite fuel sintered pellets [8,14].

2.4. Performance Testing and Characterization of Samples

The sintering density of the pellets was measured using a Mettler Toledo density balance, and the chemical reactions of mixed powders were analyzed with an STA449 F3 differential thermal analyzer. The phase structure of the pellets was tested via X-ray diffraction, the microstructure of sintered pellets characterized with scanning electron microscopy, and the thermal diffusivity of the pellets was measured with an LFA467HT thermal diffusivity meter.

3. Results and Discussion

3.1. UO2–Graphene Powder Mixing Uniformity

Graphene is a sheet structure composed of carbon atoms arranged in a plane with a low density (2.2 g/cm3); it is prone to agglomeration and difficult to disperse. The UO2 powder is granular with a high density (10.96 g/cm3). It is extremely difficult to evenly mix a lightweight flaky material with a heavyweight granular material [15].
To quantify the uniformity of graphene in the mixed powder, composition analysis was performed by random sampling, and the dispersion was quantified using the composition analysis results, calculated as follows: the mixed powder of UO2 and graphene was heated in the air at 1073 K to remove graphene via oxidation, and UO2 oxidized to U3O8. Then, U3O8 was weighed to determine the mass of UO2 by reverse calculation to obtain the proportion of reactants. The coefficient of variation (CV) was used to evaluate the mixing uniformity.
With the graphene content of measurements x1, x2, x3, x4, and x5, the average value ( x ¯ ) is calculated as follows:
x ¯ = x 1 + x 2 + x 3 + x 4 + x 5 5
s = ( x 1 x ¯ ) 2 + ( x 2 x ¯ ) 2 + ( x 3 x ¯ ) 2 + ( x 4 x ¯ ) 2 + ( x 5 x ¯ ) 2 5 1
C V = s x ¯ × 100   ( % )
where s represents the standard deviation and CV the coefficient of variation. Thus, the mixing uniformity (M) can be quantified as follows:
M = 1 C V   ( % )
Table 1 and Figure 2 show the mixing uniformity of powders with different graphene levels. The mixing uniformity of powders prepared by physical mixing was less than 92%. When the graphene content was low (2%), it was more difficult to mix the powder evenly, since the density difference between graphene and UO2 was too large and the physical mixing tended to agglomerate the graphene. For powders prepared by in situ synthesis, the mixing uniformity was not only high (>96% for all), but also not as dependent on the content of graphene. The reason for this was that the graphene synthesized in situ had been completely coated by the UO2 powder, which resulted in the formation of composite particles. These particles were similar to matrix UO2 in density, and their surfaces were homogenous. Therefore, they mixed evenly.

3.2. Reaction Kinetics and Phase Structure

Figure 3 shows the DTA curve of UO2–graphene reaction kinetics. Below 1773 K, there was no obvious reaction between UO2 and graphene. UO2 reacted with graphene at 1838 K and exothermic peaks appeared in the curve. Figure 4 shows a phase structure comparison for sintered pellets. At 1723 K, the sintered pellets had two phases, that is, UO2 and graphene phases. UO2 did not react with graphene and graphene dispersed in the UO2 matrix intact, and the second phase was protected [16]. The XRD phase pattern was consistent with the DTA analysis results.

3.3. Factors Influencing the Density of UO2–Graphene Sintered Pellets

The density of UO2–graphene sintered pellets was measured by drainage, as shown in Table 2 and Figure 5. With higher graphene content, the density of sintered pellets prepared by physical mixing and in situ synthesis both decreased. This was because the sintering densification of UO2 was mainly achieved by atomic diffusion, and the doping of graphene prevented UO2 from diffusing between atoms, which could have decreased the density of the sintered pellets [17,18].
However, the density of the sintered pellets prepared by physical mixing decreased more significantly. When the graphene content was 8%, the density decreased to 90.97%TD, which failed to meet the relevant requirement for reactor use (no less than 94%TD). The density decrease of sintered pellets prepared by in situ synthesis was very slow, and the density did not decrease significantly with added graphene. When the graphene content was 8%, the density was 94.96%TD, which met the relevant requirement for use in the reactor. The main reasons why in situ synthesis differed from physical mixing are as follows: for the UO2–graphene mixed powder prepared by in situ synthesis, graphene—as the nuclei for reactive deposition of UO2—made UO2 coat its surface fully and evenly so that UO2 bound to graphene at the molecular level. When sintering pellets prepared from this powder, the inter-particle contact was UO2, while the graphene was just a coating. This was conducive to the diffusion and densification of UO2 atoms at high temperatures and greatly offset the negative effect of graphene on pellet densification.
This experiment utilized spark plasma sintering (SPS) because it was difficult to densify the pellets by conventional pressureless sintering after UO2 was doped with graphene powder. Results showed that the density of sintered pellets obtained by pressureless sintering was <88%TD, which failed to meet relevant design requirements for nuclear fuel. An advantage of SPS lies in the rapid temperature rise for sintering. At the same time, pressurizing helped to densify the pellets. At a sintering time of less than 1 h, the pellet density did not meet relevant requirements. For example, at a sintering time of 30 min, the density of pellets doped with 2% graphene was 90.82%TD. Therefore, the sintering time for these experiments was 1 h.

3.4. Factors Influencing Thermal Conductivity of UO2–Graphene Sintered Pellets

For the thermal conductivities of UO2–graphene sintered pellets, see Table 3 and Figure 6 and Figure 7. The thermal conductivities of sintered pellets prepared by either physical mixing or in situ synthesis increased gradually with graphene, and the graphene improved the heat transfer capacity of the pellets. For sintered pellets with the same graphene content, the thermal conductivity of pellets prepared by in situ synthesis was relatively high for three reasons: first, for pellets prepared by in situ synthesis, graphene dispersed fully with a good mixing uniformity (as shown in Table 1). The pellets with high graphene mixing uniformity were more likely to form a network bridge in the pellets, which was conducive to the outward transfer of pellet heat. Second, the UO2–graphene interfacial binding properties for the pellets prepared by in situ synthesis were better than physical mixing; for the mixed powder prepared by a wet process, a contact at the molecular level may be achieved, which is conducive to interfacial bonding during sintering. Third, the sintering density for pellets prepared by in situ synthesis exceeded that of physical mixing (as shown in Table 2), and the sintering density directly influenced the thermal conductivity of pellets. Therefore, the thermal conductivity of pellets prepared by in situ synthesis was relatively high. At room temperature, the thermal conductivities of sintered pellets doped with 2%, 4%, 6%, and 8% graphene prepared by in situ synthesis increased by 12.27%, 20.13%, 27.47, and 34.13% respectively.
This study also found that the increase rate for the thermal conductivity of pellets at 1273 K was higher than at 293 K because the thermal conductivity of UO2 decreased sharply at high temperatures, though graphene did not change much. At this point, graphene further advanced the thermal conductivity of the pellets due to its better thermal conductivity at higher temperatures. This could increase the safety and economic efficiency of the fuel in service at high temperatures and compensate for the low thermal conductivity of UO2 at high temperatures. Compared to physical mixing, in situ synthesis advanced the thermal conductivity of pellets at 1273 K, the graphene in the pellets was more evenly distributed, the interfacial contact was better, and the thermal conductivity of graphene was fully exerted.

3.5. Microstructure of UO2–Graphene Sintered Pellets

Figure 8 shows the microstructures of UO2–graphene sintered pellets (graphene contents 8% and 4%) prepared by physical mixing and in situ synthesis. The pellets prepared by physical mixing showed more pores concentrated along the grain boundary due to lack of physically mixed pellets, as the UO2 did not mix with the graphene powder evenly, which resulted in agglomeration. The agglomerated graphene concentrated at the grain boundary of UO2 hindered the sintering densification of UO2 pellets, which produced more pores, while pellets prepared by in situ synthesis did not show obvious pores at the grain boundary because the grains were closely bonded. This was due to graphene coating UO2 during the preparation of the mixed powder, which bound at the molecular level. Such a mixed powder has two advantages: first, UO2 evenly mixes with graphene without the agglomeration of graphene. Second, during sintering, homogenous substances between UO2 particles bound directly and increased the sintering density. Graphene was uniformly coated by UO2, and the thermal conductivity of the pellets improved by forming a bridging heat conduction network [19,20].

4. Conclusions

The problem of uneven mixing of UO2 with graphene was solved by in situ synthesis. The in-situ synthesis method elevated the mixing uniformity of graphene powder to 96.39%, which provided an excellent mixed powder for subsequent pellet sintering.
In the sintered pellets at 1723 K, there were only phase structures of UO2 and graphene. Graphene was not destroyed during the reaction with UO2. The densities of pellets doped with 2%, 4%, 6%, and 8% graphene prepared by in situ synthesis were 95.56%TD, 95.32%TD, 95.08%TD, and 94.76%TD, respectively. The pellet density did not decrease significantly with increased graphene. The thermal conductivities of the pellets at 293 K increased by 12.27%, 20.13%, 27.47%, and 34.13%, respectively, and increased by 18.36%, 35.00%, 47.07%, and 58.93% at 1273 K, respectively. The performance of graphene in the fuel was better at high temperatures, which overcame the shortcomings due to the low thermal conductivity of UO2 at high temperatures.
The grain sizes of the pellets prepared by in situ synthesis were 10–30 μm, and there was no obvious pore at the grain boundary because the grains were closely bound. Graphene was coated by UO2 uniformly, and the thermal conductivity of the pellets improved by forming a bridging heat conduction network.

Author Contributions

Conceptualization, X.W. and B.Y.; methodology, X.W.; software, B.Y.; validation, B.Y., X.W.; formal analysis, X.W.; investigation, X.W.; resources, B.Y.; data curation, X.W.; writing—original draft preparation, X.W.; writing—review and editing, B.Y.; visualization, B.Y.; supervision, X.W.; project administration, X.W.; funding acquisition, X.W. All authors have read and agreed to the published version of the manuscript.

Funding

This research received no external funding.

Institutional Review Board Statement

Not applicable.

Informed Consent Statement

Informed consent was obtained from all subjects involved in the study.

Conflicts of Interest

The authors declare no conflict of interest.

References

  1. Fink, J.; Chasanov, M.; Leibowitz, L. Thermophysical properties of uranium dioxide. J. Nucl. Mater. 1981, 102, 17–25. [Google Scholar] [CrossRef]
  2. Brandt, R.; Neuer, G. Thermal Conductivity and Thermal Radiation Properties of UO2. J. Non-Equilib. Thermodyn. 1976, 1. [Google Scholar] [CrossRef]
  3. Harding, J.; Martin, D. A recommendation for the thermal conductivity of UO2. J. Nucl. Mater. 1989, 166, 223–226. [Google Scholar] [CrossRef]
  4. Latta, R.; Fryxell, R. Determination of Solidus-Liquidus Temperatures in the UO2 + x System (−0.50 < x < 0.20). J. Nucl. Mater. 1970, 35, 195–210. [Google Scholar] [CrossRef]
  5. Bates, J. Melting point of irradiated uranium dioxide. J. Nucl. Mater. 1970, 36, 234–236. [Google Scholar] [CrossRef]
  6. Kim, H.-G.; Yang, J.-H.; Kim, W.-J.; Koo, Y.-H. Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea. Nucl. Eng. Technol. 2016, 48, 1–15. [Google Scholar] [CrossRef] [Green Version]
  7. Yang, J.H.; Kim, H.G.; In, W.K.; Kim, W.J.; Koo, Y.H.; Lee, S.J. Development Status of Accident Tolerant Fuels for Light Water Reactors in Korea. In Proceedings of the 2016 Spring Meeting of the KNS, Jeju, Korea, 12–13 May 2016. [Google Scholar]
  8. Yao, T.; Xin, G.; Scott, S.M.; Gong, B.; Lian, J. Thermally-Conductive and Mechanically-Robust Graphene Nanoplatelet Reinforced UO2 Composite Nuclear Fuels. Sci. Rep. 2018, 8, 1–9. [Google Scholar] [CrossRef] [PubMed] [Green Version]
  9. Zhang, D.; Li, Y.; Gao, R.; Li, B.; Yang, Z.; Yan, B.; Liu, X.; Wang, Z.; Huang, Q.; Tang, H.; et al. Hydrothermal synthesis of uranium dioxide and graphene composite and its application as an additive for uranium-dioxide-based accident tolerant fuel. Ceram. Int. 2021, 47, 11249–11256. [Google Scholar] [CrossRef]
  10. Lee, S.W.; Kim, H.T.; Bang, I.C. Performance evaluation of UO2/graphene composite fuel and SiC cladding during LBLOCA using MARS-KS. Nucl. Eng. Des. 2013, 257, 139–145. [Google Scholar] [CrossRef]
  11. Smith, A.T.; LaChance, A.M.; Zeng, S.; Liu, B.; Sun, L. Synthesis, properties, and applications of graphene oxide/reduced graphene oxide and their nanocomposites. Nano Mater. Sci. 2019, 1, 31–47. [Google Scholar] [CrossRef]
  12. Abbott, E.C.; Brenkmann, A.; Galbraith, C.; Ong, J.; Schwerdt, I.J.; Albrecht, B.D.; Tasdizen, T.; McDonald IV, L.W. Dependence of UO2 surface morphology on processing history within a single synthetic route. Radiochim. Acta 2019, 107, 1121–1131. [Google Scholar] [CrossRef]
  13. Jaques, B.J.; Watkins, J.; Croteau, J.R.; Alanko, G.; Tyburska-Püschel, B.; Meyer, M.; Xu, P.; Lahoda, E.J.; Butt, D.P. Synthesis and sintering of UN-UO2 fuel composites. J. Nucl. Mater. 2015, 466, 745–754. [Google Scholar] [CrossRef] [Green Version]
  14. Zhang, D.; Li, Y.; Yang, Z.; Li, B.; Wang, Z.; Huang, Q.; Yan, B.; Chu, M.; Yu, L.; Zeng, R. In-situ synthesized nanocrystalline UO2/SiC composite with superior thermal conductivity. Ceram. Int. 2021, 47, 31160–31167. [Google Scholar] [CrossRef]
  15. Binti Mohamad, A. Fundamental Studies on New Silicides-Based Accident Tolerant Fuel. Ph.D. Thesis, Osaka University, Suita, Japan, March 2019. [Google Scholar]
  16. Chen, Z. Densification Evolution and Properties Evaluation of UO2-Based Composites Prepared by Spark Plasma Sintering (SPS). Ph.D. Thesis, University of Florida, Gainesville, FL, USA, December 2015. [Google Scholar]
  17. Massih, A.R.; Jernkvist, L.O. Effects of Additives on UO2 Fuel Behavior: Expanded Edition; The Swedish Radiation Safety Authority: Stockholm, Sweden, 2021.
  18. Gomes, D.S.; Silva, A.T. Performance analysis of UO2–SiC fuel under normal conditions. In Proceedings of the International Nuclear Atlantic Conference (INAC), São Paulo, Brazil, 21–25 October 2019; pp. 5056–5069. [Google Scholar]
  19. Lian, J. Thermal Transport and Fracture Behavior of Sintered Fuel Pellets: Experimental Validation of NEAMS Tool MARMOT; Technical Report for Rensselaer Polytechnic Inst.: Troy, NY, USA, 2019. [Google Scholar]
  20. Ohai, D. Technologies for Manufacturing UO2 Sintered Pellets to Fuel Burnup Extension. In Proceedings of the Technical Committee Meeting on Technical and Economic Limits to Fuel Burnup Extension; International Atomic Energy Agency (IAEA): San Carlos de Bariloche, Argentina, 2002; pp. 193–209. [Google Scholar]
Figure 1. Experimental steps (a) (UO2(NO3)·6H2O) solution, (b) Graphene dispersion suspension, (c) UO2 + graphene mixed powder, and (d) UO2 + graphene sintered pellet for the preparation of UO2–graphene composite powder by in situ synthesis.
Figure 1. Experimental steps (a) (UO2(NO3)·6H2O) solution, (b) Graphene dispersion suspension, (c) UO2 + graphene mixed powder, and (d) UO2 + graphene sintered pellet for the preparation of UO2–graphene composite powder by in situ synthesis.
Crystals 12 00230 g001
Figure 2. Relationship between graphene content and the mixing uniformity of powders.
Figure 2. Relationship between graphene content and the mixing uniformity of powders.
Crystals 12 00230 g002
Figure 3. UO2–graphene reaction kinetic curve.
Figure 3. UO2–graphene reaction kinetic curve.
Crystals 12 00230 g003
Figure 4. XRD images of UO2–graphene sintered pellets.
Figure 4. XRD images of UO2–graphene sintered pellets.
Crystals 12 00230 g004
Figure 5. Influence of graphene content on pellet density.
Figure 5. Influence of graphene content on pellet density.
Crystals 12 00230 g005
Figure 6. Influence of graphene content on the pellet thermal conductivity.
Figure 6. Influence of graphene content on the pellet thermal conductivity.
Crystals 12 00230 g006
Figure 7. Influence of graphene content on thermal conductivity increase rate of pellets.
Figure 7. Influence of graphene content on thermal conductivity increase rate of pellets.
Crystals 12 00230 g007
Figure 8. SEM images of the microstructure of UO2–graphene sintered pellets with a (a,b) graphene content of 8% prepared by physical mixing and (c) a graphene content of 4% prepared by in situ synthesis.
Figure 8. SEM images of the microstructure of UO2–graphene sintered pellets with a (a,b) graphene content of 8% prepared by physical mixing and (c) a graphene content of 4% prepared by in situ synthesis.
Crystals 12 00230 g008
Table 1. Relationship between graphene content and the mixing uniformity of powders.
Table 1. Relationship between graphene content and the mixing uniformity of powders.
Graphene Content (vol.%)2468
Mixing uniformity (M) (%)96.3296.3596.3096.3796.3996.3596.4196.4296.3896.4696.4896.51
Table 2. Relationship between graphene level and pellet density (%TD).
Table 2. Relationship between graphene level and pellet density (%TD).
Graphene Content (vol.%)02468
Pellet density (%TD)95.8895.2195.0995.0194.96
Table 3. Relationship between graphene content and thermal conductivity of pellets.
Table 3. Relationship between graphene content and thermal conductivity of pellets.
Graphene Content (vol.%)02468
Thermal conductivity
(293 K)
Value (W/(m·K))7.508.429.019.5610.06
Increase rate (%)012.2720.1327.4734.13
Thermal conductivity
(1273 K)
Value(W/(m·K))2.803.313.784.124.45
Increase rate (%)018.3635.0047.0758.93
Publisher’s Note: MDPI stays neutral with regard to jurisdictional claims in published maps and institutional affiliations.

Share and Cite

MDPI and ACS Style

Wu, X.; Yin, B. Mechanism and Properties of UO2–Graphene Composite Fuel Prepared by In Situ Synthesis. Crystals 2022, 12, 230. https://doi.org/10.3390/cryst12020230

AMA Style

Wu X, Yin B. Mechanism and Properties of UO2–Graphene Composite Fuel Prepared by In Situ Synthesis. Crystals. 2022; 12(2):230. https://doi.org/10.3390/cryst12020230

Chicago/Turabian Style

Wu, Xuezhi, and Bangyue Yin. 2022. "Mechanism and Properties of UO2–Graphene Composite Fuel Prepared by In Situ Synthesis" Crystals 12, no. 2: 230. https://doi.org/10.3390/cryst12020230

APA Style

Wu, X., & Yin, B. (2022). Mechanism and Properties of UO2–Graphene Composite Fuel Prepared by In Situ Synthesis. Crystals, 12(2), 230. https://doi.org/10.3390/cryst12020230

Note that from the first issue of 2016, this journal uses article numbers instead of page numbers. See further details here.

Article Metrics

Back to TopTop