본문 바로가기
KERD
논문KCI 등재

Phase-field simulation of radiation-induced bubble evolution in recrystallized U-Mo alloy

Ping Chen|Xiao Liu|Yanbo Jiang|Yong Xin|Wenbo Liu|Zhipeng Sun|Dan Sun|Mingyang Zhou|Di Yun
한국원자력학회 (Korean Nuclear Society)|2022.01|Nuclear Engineering and Technology|제54권 제1호|pp. 226-233|DOI https://doi.org/10.1016/j.net.2021.07.034

2

조회

0

다운로드

0

인용

0

참고문헌

키워드

BubbleRecrystallizationPhase-fieldUeMoFission density
주제분류원자력공학

초록

In the present work, a phase-field model was developed to investigate the influence of recrystallizationon bubble evolution during irradiation. Considering the interaction between bubbles and grain boundary(GB), a set of modified Cahn-Hilliard and Allen-Cahn equations, with field variables and order parametersevolving in space and time, was used in this model. Both the kinetics of recrystallization characterized inexperiments and point defects generated during cascade were incorporated in the model. The bubbleevolution in recrystallized polycrystalline of UeMo alloy was also investigated. The simulation resultsshowed that GB with a large area fraction generated by recrystallization accelerates the formation andgrowth of bubbles. With the formation of new grains, gas atoms are swept and collected by GBs. Thesimulation results of bubble size and distribution are consistent with the experimental results.

Abstract

In the present work, a phase-field model was developed to investigate the influence of recrystallizationon bubble evolution during irradiation. Considering the interaction between bubbles and grain boundary(GB), a set of modified Cahn-Hilliard and Allen-Cahn equations, with field variables and order parametersevolving in space and time, was used in this model. Both the kinetics of recrystallization characterized inexperiments and point defects generated during cascade were incorporated in the model. The bubbleevolution in recrystallized polycrystalline of UeMo alloy was also investigated. The simulation resultsshowed that GB with a large area fraction generated by recrystallization accelerates the formation andgrowth of bubbles. With the formation of new grains, gas atoms are swept and collected by GBs. Thesimulation results of bubble size and distribution are consistent with the experimental results.

참고문헌 (48)

  1. J. L. Snelgrove, "Development of very-high-density low-enriched-uranium fuels", Nucl. Eng. Des, 178, pp.119~126 (1997)[DOI]
  2. D. D. Keiser, "low-enriched uranium fuel for nuclear research reactors", JOM(J. Occup. Med. ), 55, pp.55~58 (2003)[DOI]
  3. S. Van den Berghe, "Review of 15 years of High-density Low-enriched UMo Dispersion Fuel Development for Research Reactors in Europe", Nuclear Engineering and Technology, 46(2), pp.125~146 (2014), 한국원자력학회
  4. M. K. Meyer, "Low-temperature irradiation behavior of uraniumemolybdenum alloy dispersion fuel", J. Nucl. Mater, 304, pp.221~236 (2002)[DOI]
  5. D.R. Olander, "Fundamental Aspects of Nuclear Reactor Fuel Elements: Solutions to Problems", pp.1976
  6. G. L. Hofman, "Microscopic investigation into the irradiation behavior of U3O8-Al dispersion fuel", Nucl. Technol, 72, pp.338~344 (1986)[DOI]
  7. R. M. Berman, "Fission fragment distribution in irradiated UO2", Nucl. Sci. Eng, 16, pp.315~328 (1963)[DOI]
  8. J. Gan, "TEM characterization of Ue7Mo", Ale2Si dispersion fuel irradiated to intermediate and high fission densities, 2012, pp.424, 43~50
  9. Y. S. Kim, "Fission product induced swelling of UeMo alloy fuel", J. Nucl. Mater, 419, pp.291~301 (2011)[DOI]
  10. J. Spino, "High burn-up rim structure: evidences that xenon-depletion, pore formation and grain subdivision start at different local burn-ups", J. Nucl. Mater, 256, pp.189~196 (1998)[DOI]
  11. S. Kashibe, "Formation and growth of intragranular fission gas bubbles in UO2 fuels with burnup of 6-83 GWd", t, 1993, pp.206, 22~34
  12. H. Matzke, "On the rim effect in high burnup UO2 LWR fuels", JNuM, 189, pp.141~148 (1992)[DOI]
  13. K. Nogita, "Radiation-induced microstructural change in high burnup UO2 fuel pellets", Nucl. Instrum. Methods Phys. Res., Sect. B, 91, pp.301~306 (1994)[DOI]
  14. V. V. Rondinella, "The high burn-up structure in nuclear fuel", Mater. Today, 13, pp.24~32 (2010)[DOI]
  15. J. Noirot, "Detailed characterizations of high burn-up structures in oxide fuels", J. Nucl. Mater, 372, pp.318~339 (2008)[DOI]
  16. J. Spino, "Detailed characterisation of the rim microstructure in PWR fuels in the burn-up range 40-67 GWd", tM, 1996, pp.231, 179~190
  17. S. Y. Hu, "Atomistic simulations of thermodynamic properties of Xe gas bubbles in U10Mo fuels", J. Nucl. Mater, 490, pp.49~58 (2017)[DOI]
  18. H. X. Xiao, "Atomistic simulations of the small xenon bubble behavior in U-Mo alloy", Mater. Des, 74, pp.55~60 (2015)[DOI]
  19. J. Rest, "precipitate pinning and fission gas behavior on irradiation-induced recrystallization of nuclear fuels", J. Nucl. Mater, 326, pp.175~184 (2004)[DOI]
  20. J. Rest, "Model for the effect of the progression of irradiation-induced recrystallization from initiation to completion on swelling of UO2 and Ue10Mo nuclear fuels", J. Nucl. Mater, 324, pp.226~232 (2005)[DOI]
  21. M. R. Tonks, "A coupling methodology for mesoscaleinformed nuclear fuel performance codes", Nucl. Eng. Des, 240, pp.2877~2883 (2010)[DOI]
  22. Amani Cheniour, "Development of a grain growth model for U3Si2 using experimental data, phase field simulation and molecular dynamics", Journal of Nuclear Materials, 532, pp.152069~ (2020), Elsevier BV[DOI]
  23. Z. G. Mei, "Grain growth in Ue7Mo alloy : a combined firstprinciples and phase field study", J. Nucl. Mater, 473, pp.300~308 (2016)[DOI]
  24. Yanbo Jiang, "Phase-field simulation of the interaction between intergranular voids and grain boundaries during radiation in UO2", Computational Materials Science, 188, pp.110176~ (2021), Elsevier BV[DOI]
  25. L. Liang, "Three-dimensional phase-field simulations of intragranular gas bubble evolution in irradiated U-Mo fuel", Comput. Mater. Sci, 145, pp.86~95 (2018)[DOI]
  26. P. C. Millett, "Phase-field simulation of irradiated metals : Part II : gas bubble kinetics", Comput. Mater. Sci, 50, pp.960~970 (2011)[DOI]
  27. M. G. Abdoelatef, "Mesoscale modeling of high burn-up structure formation and evolution in UO2", JOM(J. Occup. Med. ), 71, pp.4817~4828 (2019)[DOI]
  28. L. Liang, "Fission gas bubbles and recrystallization-induced degradation of the effective thermal conductivity in U-7Mo fuels", J. Nucl. Mater, 511, pp.438~445 (2018)[DOI]
  29. L. Liang, "Fission-induced recrystallization effect on intergranular bubble-driven swelling in U-Mo fuel", Comput. Mater. Sci, 138, pp.16~26 (2017)[DOI]
  30. S. Hu, "A rate-theoryephase-field model of irradiationinduced recrystallization in UMo nuclear fuels", JOM(J. Occup. Med. ), 69, pp.2554~2562 (2017)[DOI]
  31. L. Q. Chen, "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, pp.15752~ (1994)[DOI]
  32. Z. Xiao, "A quantitative phase-field model of gas bubble evolution in UO2", Comput. Mater. Sci, 184, pp.109867~ (2020)[DOI]
  33. J. W. Cahn, "Free energy of a nonuniform system. I. Interfacial free energy", J. Chem. Phys, 28, pp.258~267 (1958)[DOI]
  34. Y. Wang, "A phase field study of the thermal migration of gas bubbles in UO2 nuclear fuel under temperature gradient", Comput. Mater. Sci, 183, pp.109817~ (2020)[DOI]
  35. I. Steinbach, "Phase-field model for microstructure evolution at the mesoscopic scale", Annu. Rev. Mater. Res, 43, pp.89~107 (2013)[DOI]
  36. P. C. Millett, "Phase-field simulation of irradiated metals : Part I : void kinetics", Comput. Mater. Sci, 50, pp.949~959 (2011)[DOI]
  37. Effect of recrystallization in high-burnup UO{sub 2} on gas release during RIA-type transients, "J. Rest", ~, pp.ANL (1994), ET[DOI]
  38. N. Moelans, "A quantitative and thermodynamically consistent phase-field interpolation function for multi-phase systems", Acta Mater, 59, pp.1077~1086 (2011)[DOI]
  39. J. Rest, "An analytical study of gas-bubble nucleation mechanisms in uraniumalloy nuclear fuel at high temperature", J. Nucl. Mater, 402, pp.179~185 (2010)[DOI]
  40. D. R. Olander, "Fundamental Aspects of Nuclear Reactor Fuel Elements", United State, ~ (1976), .
  41. Z. G. Mei, "First-principles study of the surface properties of U-Mo system", Comput. Mater. Sci, 142, pp.355~360 (2018)[DOI]
  42. R.C. Reid, "The Properties of Gases and Liquids", ~ (1987)
  43. S. Hu, "Assessment of effective thermal conductivity in UeMo metallic fuels with distributed gas bubbles", J. Nucl. Mater, 462, pp.64~76 (2015)[DOI]
  44. N. Moelans, "Quantitative analysis of grain boundary properties in a generalized phase field model for grain growth in anisotropic systems", Physical Review B, 78(2) (2008), American Physical Society (APS)[DOI]
  45. Y. S. Kim, "Recrystallization and fission-gas-bubble swelling of U-Mo fuel", J. Nucl. Mater, 436, pp.14~22 (2013)[DOI]
  46. P. C. Millett, "Phase-field simulation of intergranular bubble growth and percolation in biocrystals", J. Nucl. Mater, 425, pp.130~135 (2012)[DOI]
  47. J. Rest, "The effect of irradiation-induced gas-atom re-solution on grainboundary bubble growth", J. Nucl. Mater, 321, pp.305~312 (2003)[DOI]
  48. Y. S. Kim, "In-pile test results of U-silicide or U-nitride coated U-7Mo particle dispersion fuel in Al", J. Nucl. Mater, 454, pp.238~246 (2014)[DOI]

관련 논문AI추천

The effects of different factors on obstacle strength of irradiation defects: An atomistic studyCui Wen-dong, Gu Guo-chao, He Lei, Lin Pan-dong, Lu Yu-peng, Nie Jun-feng, Xiao Gui-yong한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제6호A reduced order model for fission gas diffusion in columnar grainsBarani T., Cammi A., Di Gennaro M., Lorenzi S., Pizzocri D., Silva F.A.B., Zullo G.한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제11호On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigationD. Pizzocri, L. Luzzi, M. Romano한국원자력학회 · Nuclear Engineering and Technology2022 · 제54권 제5호Molecular dynamics simulation of primary irradiation damage in Ti-6Al-4V alloysFeng Miaolin, He Tengwu, Li Xipeng, Qi Yuming, Zhao Min한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제4호Study of the effect of PKA energy on long-term microstructural evolution in irradiated FeMnNi alloysBalbuena J.P., Li Jianyang, Yang Yitao, Zhang Chonghong, Zhao Shijun한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제5호TEM investigation of helium bubble evolution in tungsten and ZrC-strengthened tungsten at 800 and 1000°C under 40keV He+ irradiationChiu Y.-L., Gilbert M.R., Greaves G., Ipatova I., Terentyev D.한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제4호

이 간행물의 다른 논문 (21건)

Possibility of Curium as a Fuel for VVER-1200 ReactorMahmud Hasan Ovi, Afroza Shelleypp. 11-18Analysis and comparison of the 2D/1D and quasi-3D methods with the direct transport code SHARKXingjie Peng, Zhang Chen, Qing Li, Wenbo Zhao, Hongbo Zhang, Chen Zhaopp. 19-29Application of POD reduced-order algorithm on data-driven modeling of rod bundleZhaofei Tian, Tianyu Wang, Lei Li, Huilun Kang, Guangliang Chenpp. 36-48Experimental study on the Influence of Heating Surface Inclination Angle on Heat Transfer and CHF performance for Pool BoilingWenxi Tian, Chenglong Wang, Panxiao Li, Dalin Zhang, Suizheng Qiu, G.H. Su, Jian Dengpp. 61-71Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate박일웅, 송민섭, 이연건, 김응수pp. 72-83
원문 보기