Microstructural evolution of gas bubbles and thermal conductivity in UO2-BeO bicrystal
Bibliographic record
Abstract
No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.
Source: Not provided · Quality: missing
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (41)
Show source-provided references
1. Bragg-Sitton SM (2014) Development of advanced accident-tolerant fuels for commercial LWRs. Nucl News 53:83–91
2. Pillai C, George AM (1993) Thermal conductivity of uranium dioxide. J Nucl Mater 200:78–8110.1016/0022-3115(93)90011-M ↗
3. Olander DR (1976) Fundamental aspects of nuclear reactor fuel elements. California University, Berkeley, Department of Nuclear Engineering10.2172/7343826 ↗
4. Ronchi C, Sheindlin M, Staicu D, Kinoshita M (2004) Effect of burn-up on the thermal conductivity of uranium dioxide up to 100.000 MWdt-1. J Nucl Mater 327:58–7610.1016/j.jnucmat.2004.01.018 ↗
5. Zhou W, Zhou W (2018) Enhanced thermal conductivity accident tolerant fuels for improved reactor safety—a comprehensive review. Ann Nucl Energy 119:66–8610.1016/j.anucene.2018.04.040 ↗
6. Latta R, Revankar ST, Solomon AA (2008) Modeling and measurement of thermal properties of ceramic composite fuel for light water reactors. Heat Transfer Eng 29:357–36510.1080/01457630701825390 ↗
7. Kim SH, Joung CY, Kim HS et al (2006) Fabrication method and thermal conductivity assessment of molybdenum-precipitated uranium dioxide pellets. J Nucl Mater 352:151–15610.1016/j.jnucmat.2006.02.049 ↗
8. Lee SW, Kim HT, Bang IC (2013) Performance evaluation of UO2/graphene composite fuel and SiC cladding during LBLOCA using MARS-KS. Nucl Eng Des 257:139–14510.1016/j.nucengdes.2013.01.012 ↗
9. Kim DJ, Rhee YW, Kim JH et al (2015) Fabrication of micro-cell UO2–Mo pellet with enhanced thermal conductivity. J Nucl Mater 462:289–29510.1016/j.jnucmat.2015.04.003 ↗
10. Cartas A, Wang H, Subhash G, Baney R, Tulenko J (2015) Influence of carbon nanotube dispersion in UO2–carbon nanotube ceramic matrix composites utilizing spark plasma sintering. Nucl Technol 189:258–26710.13182/NT14-7 ↗
11. Chen Z, Subhash G, Tulenko JS (2015) Spark plasma sintering of diamond-reinforced uranium dioxide composite fuel pellets. Nucl Eng Des 294:52–5910.1016/j.nucengdes.2015.08.021 ↗
12. Slack GA, Austerman SB (1971) Thermal conductivity of BeO single crystals. J Appl Phys 42:4713–471710.1063/1.1659844 ↗
13. Ishimoto S, Hirai M, Ito K, Korei Y (1996) Thermal conductivity of UO2-BeO pellet. J Nucl Sci Technol 33:134–14010.1080/18811248.1996.9731875 ↗
14. Garcia CB, Brito RA, Ortega LH, Malone JP, Mcdeavitt SM (2017) Manufacture of a UO2-based nuclear fuel with improved thermal conductivity with the addition of BeO. Metall Mater Trans E 4:70–76
15. Shrestha K, Yao T, Lian J et al (2019) The grain-size effect on thermal conductivity of uranium dioxide. J Appl Phys 126:12511610.1063/1.5116372 ↗
16. Liu M, Kang Q, Xu H (2021) Grain-scale study of the grain boundary effect on UO2 fuel oxidation and fission gas release under reactor condition. Chem Eng Sci 229:11602610.1016/j.ces.2020.116026 ↗
17. Millett PC, Wolf D, Desai T, Rokkam S, A EI-Azab, (2008) Phase-field simulation of thermal conductivity in porous polycrystalline microstructures. J Appl Phys 104:03351210.1063/1.2964116 ↗
18. Cahill DG, Ford WK, Goodson KE et al (2003) Nanoscale thermal transport. J Appl Phys 93:793–81810.1063/1.1524305 ↗
19. Zacharie I, Lansiart S, Combette P, Trotabas M, Groos M (1998) Microstructural analysis and modelling of intergranular swelling of an irradiated UO2 fuel treated at high temperature. J Nucl Mater 255:92–10410.1016/S0022-3115(98)00040-3 ↗
20. Gulden ME (1967) Migration of gas bubbles in irradiated uranium dioxide. J Nucl Mater 23:30–3610.1016/0022-3115(67)90128-6 ↗
21. Zacharie I, Lansiart S, Combette P, Trotabas M, Groos M (1998) Thermal treatment of uranium oxide irradiated in pressurized water reactor: Swelling and release of fission gases. J Nucl Mater 255:85–9110.1016/S0022-3115(98)00039-7 ↗
22. Millett PC, EI-Azab A, Wolf D (2011) Phase-field simulation of irradiated metals Part II: Gas bubble kinetics. Comput Mater Sci 50:960–97010.1016/j.commatsci.2010.10.032 ↗
23. Zhu X, Gao R, Gong H, Liu T, Lin DY, Song H (2021) UO2/BeO interfacial thermal resistance and its effect on fuel thermal conductivity. Ann Nucl Energy 154:10810210.1016/j.anucene.2020.108102 ↗
24. Hu S, Henager CH Jr, Heinisch HL, Stan M, Baskes MI, Valone SM (2009) Phase-field modeling of gas bubbles and thermal conductivity evolution in nuclear fuels. J Nucl Mater 392:292–30010.1016/j.jnucmat.2009.03.017 ↗
25. Li B, Yang Z, Jia J et al (2018) High temperature thermal physical performance of BeO/UO2 composites prepared by spark plasma sintering (SPS). Scr Mater 142:70–7310.1016/j.scriptamat.2017.08.031 ↗
26. Badry F, Brito R, Abdoelatef MG, Mcdeavitt S, Ahmed K (2019) An experimentally validated mesoscale model of thermal conductivity of a UO2 and BeO composite nuclear fuel. JOM 71:4829–483810.1007/s11837-019-03831-y ↗
27. Millett PC, EI-Azab A, Rokkam S, Tonks M, Wolf D (2011) Phase-field simulation of irradiated metals Part I: Void kinetics. Comput Mater Sci 50:949–95910.1016/j.commatsci.2010.10.034 ↗
28. Cahn JW, Hilliard JE (1958) Free energy of a nonuniform system. I. interfacial free energy. J Chem Phys 28:258–26710.1063/1.1744102 ↗
29. Allen SM, Cahn JW (1979) A microscopic theory for antiphase boundary motion and its application to antiphase domain coarsening. Acta Metall 27:1085–109510.1016/0001-6160(79)90196-2 ↗
30. Hohenberg PC, Halperin BI (1977) Theory of dynamic critical phenomena. Rev Mod Phys 49:435–47910.1103/RevModPhys.49.435 ↗
31. Moelans N, Blanpain B, Wollants P (2008) An introduction to phase-field modeling of microstructure evolution. Calphad 32:268–29410.1016/j.calphad.2007.11.003 ↗
32. Chen LQ, Yang W (1994) Computer simulation of the domain dynamics of a quenched system with a large number of nonconserved order parameters: the grain-growth kinetics. Phys Rev B 50:1575210.1103/PhysRevB.50.15752 ↗
33. Tonks M, Andersson D, Devanathan R et al (2018) Unit mechanisms of fission gas release: Current understanding and future needs. J Nucl Mater 504:300–31710.1016/j.jnucmat.2018.03.016 ↗
34. Fink JK (2000) Thermophysical properties of uranium dioxide. J Nucl Mater 279:1–1810.1016/S0022-3115(99)00273-1 ↗
35. Yaws CL, Braker W (2001) Matheson gas data book, 7th edn. McGraw-Hill Professional, New York
36. Chen W, Cooper MWD, Xiao Z, Andersson DA, Bai X-M (2019) Effect of Xe bubble size and pressure on the thermal conductivity of UO2—A molecular dynamics study. J Mater Res 34:2295–230510.1557/jmr.2019.93 ↗
37. Han WZ, Demkowicz MJ, Fu EG, Wang YQ, Misra A (2012) Effect of grain boundary character on sink efficiency. Acta Mater 60:6341–635110.1016/j.actamat.2012.08.009 ↗
38. Lu C, Lu Z, Xie R, Liu C, Wang L (2016) Microstructure of HIPed and SPSed 9Cr-ODS steel and its effect on helium bubble formation. J Nucl Mater 474:65–7510.1016/j.jnucmat.2016.03.010 ↗
39. Hu S, Casella AM, Lavender CA, Senor DJ, Burkes DE (2015) Assessment of effective thermal conductivity in U-Mo metallic fuels with distributed gas bubbles. J Nucl Mater 462:64–7610.1016/j.jnucmat.2015.03.039 ↗
40. Wei J, Feng B, Ishikawa R et al (2021) Direct imaging of atomistic grain boundary migration. Nat Mater 20:951–95510.1038/s41563-020-00879-z ↗
41. Fan DN, Chen LQ (1997) Diffusion-controlled grain growth in two-phase solids. Acta Mater 45:3297–331010.1016/S1359-6454(97)00022-0 ↗