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Thermal-fluid-structure coupling analysis on plate-type fuel assembly under irradiation. Part-II Mechanical deformation and thermal-hydraulic characteristics

  • Li, Yuanming (Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Ren, Quan-yao (Science and Technology on Reactor System Design Technology Laboratory) ;
  • Yuan, Pan (Science and Technology on Reactor System Design Technology Laboratory) ;
  • Su, Guanghui (Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Yu, Hongxing (Science and Technology on Reactor System Design Technology Laboratory) ;
  • Zheng, Meiyin (Science and Technology on Reactor System Design Technology Laboratory) ;
  • Wang, Haoyu (Science and Technology on Reactor System Design Technology Laboratory) ;
  • Wu, Yingwei (Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Ding, Shurong (Institute of Mechanics and Computational Engineering, Department of Aeronautics and Astronautics, Fudan Univeristy)
  • Received : 2020.06.21
  • Accepted : 2020.11.30
  • Published : 2021.05.25

Abstract

The plate-type fuel assembly adopted in nuclear research reactor suffers from complicated effect induced by non-uniform irradiation, which might affect stress conditions, mechanical behaviors and thermal-hydraulic performance of the fuel assembly. This paper is the Part II work of a two-part study devoted to analyzing the complex unique mechanical deformation and thermal-hydraulic characteristics for the typical plate-type fuel assembly under irradiation effect, which is on the basis of developed and verified numerical thermal-fluid-structure coupling methodology under irradiation in Part I of this work. The mechanical deformation, thermal-hydraulic performance and Mises stress have been analyzed for the typical plate-type fuel assembly consisting of support plates under non-uniform irradiation. It was interesting to observe that: the plate-type fuel assembly including the fuel plates and support plates tended to bend towards the location with maximum fission rate; the hot spots in the fuel foil appeared at the location with maximum thickness increment; the maximum Mises stress of fuel foil was located at the adjacent location with the maximum plate thickness increment et al.

Keywords

Acknowledgement

The authors are grateful for the support of the Natural Science Foundation of China (Grant No: U20B2013, U1867219, 11675161).

References

  1. Y.S. Kim, G.L. Hofman, Fission product induced swelling of U-Mo alloy fuel [J], J. Nucl. Mater. 419 (1-3) (2011) 291-301. https://doi.org/10.1016/j.jnucmat.2011.08.018
  2. Y.S. Kim, G.L. Hofman, J.S. Cheon, et al., Fission induced swelling and creep of U-Mo alloy fuel [J], J. Nucl. Mater. 437 (1-3) (2013) 37-46. https://doi.org/10.1016/j.jnucmat.2013.01.346
  3. F. Yan, et al., Effects of UMo irradiation creep on the thermo-mechanical behaviorin monolithic UMo/Al fuel plates [J], J. Nucl. Mater. 524 (2019) 209-217. https://doi.org/10.1016/j.jnucmat.2019.07.006
  4. X. Jian, X. Kong, S. Ding, A mesoscale stress model for irradiated U-10Mo monolithic fuels based on evolution of volume fraction/radius/internal pressure of bubbles [J], Nuclear Engineering and Technology 51 (6) (2019).
  5. Y. Cui, S. Ding, Z. Chen, et al., Modifications and applications of the mechanistic gaseous swelling model for UMo fuel [J], J. Nucl. Mater. 457 (2015) 157-164. https://doi.org/10.1016/j.jnucmat.2014.11.065
  6. M.K. Meyer, G.A. Moore, J.F. Jue, et al., Investigation of the Cause of Low Blister Threshold Temperatures in the RERTR-12 and AFIP-4 Experiments (R), Idaho National Laboratory, 2012.
  7. M.K. Meyer, J. Gan, J.F. Jue, et al., Irradiation performance of U-Mo monolithic fuel [J], Nuclear Engineering and Technology 2 (46) (2014) 169-182.
  8. D.R. Miller, General Electric Company, Critical flow velocities for collapse of reactor parallel-plate fuel assemblies/[J], J. Eng. Gas Turbines Power 82 (2) (1960).
  9. J.G. Mantecon, M.M. Neto, Numerical methodology for fluid-structure interaction analysis of nuclear fuel plates under axial flow conditions, Nucl. Eng. Des. 333 (FEB) (2018) 76-86. https://doi.org/10.1016/j.nucengdes.2018.04.009
  10. J.G. Mantecon, M.M. Neto, Numerical analysis on stability of nuclear fuel plates with inlet support comb [J], Nucl. Eng. Des. 342 (FEB) (2019) 240-248. https://doi.org/10.1016/j.nucengdes.2018.12.009
  11. J.C. Kennedy, Development and Experimental Benchmarking of Numeric Fluid Structure Interaction Models for Research Reactor Fuel Analysis, PhD Dissertation, University of Missouri, 2015.
  12. Mark Ho, Guang Hong, A.N.F. Mack, Experimental investigation of flow-induced vibration in a parallel plate reactor fuel assembly, in: 15th Austral-asian Fluid Mechanics Conference, 2004.
  13. Y. Deng, Y. Wu, D. Zhang, et al., Thermal-mechanical coupling behavior analysis on metal-matrix dispersed plate-type fuel [J], Prog. Nucl. Energy 95 (MAR.) (2017) 8-22. https://doi.org/10.1016/j.pnucene.2016.11.007
  14. Y. He, P. Chen, Y. Wu, et al., Preliminary evaluation of U3Si2-FeCrAl fuel performance in light water reactors through a multi-physics coupled way [J], Nucl. Eng. Des. 328 (2018) 27-35. https://doi.org/10.1016/j.nucengdes.2017.12.019
  15. R. Liu, W. Zhou, Multiphysics modeling of novel UO2-BeO sandwich fuel performance in a light water reactor [J], Ann. Nucl. Energy 109 (nov) (2017) 298-309. https://doi.org/10.1016/j.anucene.2017.05.037
  16. Q. Lu, S. Qiu, G.H. Su, Development of A Thermal-hydraulic analysis code for research reactors with plate fuels [J], Ann. Nucl. Energy 36 (4) (2009) 433-447. https://doi.org/10.1016/j.anucene.2008.11.038
  17. D. Jo, J. Park, H. Chae, Development of thermal hydraulic and margin analysis code for steady state forced and natural convective cooling of plate type fuel research reactors [J], Prog. Nucl. Energy 71 (mar) (2014) 39-51. https://doi.org/10.1016/j.pnucene.2013.11.006
  18. G. Daxin, H. Shanfang, W. Guanbo, et al., Heat transfer calculation on plate-type fuel assembly of high flux research reactor [J], Science & Technology of Nuclear Installations (2015) 1-13, 2015.
  19. L. Li, D. Fang, D. Zhang, et al., Flow and heat transfer characteristics in plate-type fuel channels after formation of blisters on fuel elements [J], Ann. Nucl. Energy 134 (2019) 284-298. https://doi.org/10.1016/j.anucene.2019.06.030
  20. Amgad Salama, CFD investigation of flow inversion in typical MTR research reactor undergoing thermalehydraulic transients, Ann. Nucl. Energy 38 (7) (2011) 1578-1592. https://doi.org/10.1016/j.anucene.2011.03.005
  21. M.K. Meyer, D.M. Wachs, J.F. Jue, et al., U.S. Progress in the development of very high density low enrichment research reactor fuels, in: European Research Reactor Conference, 2012. Brussels, Belgium.
  22. Z. Mei, L. Liang, Y.S. Kim, T. Wiencek, Grain Growth and Bubble Evolution in U-Mo Alloy by Multiscale Simulations, RERTR, Seoul, South Korea, 2015, 2015.
  23. H. Palancher, A. Bonnin, V. Honkimaki, et al., Quantitative crystallographic analysis of as-fabricated full size U-Mo/Al(Si) nuclear fuel plates [J], J. Alloys Compd. 527 (none) (2012), 0-65.
  24. Kusunoki, T Murayama, Y Wada, et al. Current Status of U-Mo Conversion Program in JRR-3.
  25. M. Hirano, Y. Sudo, Analytical study on thermal-hydraulic behavior of transient from forced circulation to natural circulation in JRR-3 [J], J. Nucl. Sci. Technol. 23 (4) (1986) 352-368. https://doi.org/10.1080/18811248.1986.9734992
  26. M.A. Albati, O.S. Al-Yahia, J. Park, et al., Thermal hydraulic analyses of JRR-3: code-to-code comparison of COOLOD-N2 and TMAP [J], Prog. Nucl. Energy 71 (mar) (2014) 1-8. https://doi.org/10.1016/j.pnucene.2013.10.015
  27. A. Salama, M.F. El-Amin, S. Sun, Three-dimensional, numerical investigation of flow and heat transfer in rectangular channels subject to partial blockage [J], Heat Tran. Eng. 36 (1-4) (2015) 152-165. https://doi.org/10.1080/01457632.2014.909191
  28. ANSYS Inc, ANSYS FLUENT Documentation - Release 15.0, 2014.
  29. Xing-min Liu, Guo-jing Tang, Xiao-chun Wu, Core physics scheme study of U-Mo alloy fuel applied in CARR [J], Atomic Energy Sci. Technol. 6 (49) (2015) 1018-1021.
  30. H. Tduruta, H. Ichikawa, J. Iwasaki et al. Neutronics Design of Upgraded JRR-3 Research Reactor [R].
  31. X. Jian, S. Ding, Thermal creep effects of aluminum alloy cladding on the irradiation-induced mechanical behavior in U-10Mo/Al monolithic fuel plates [J], Nuclear Engineering and Technology 52 (2020) 802-810. https://doi.org/10.1016/j.net.2019.09.008