DOI QR코드

DOI QR Code

Numerical study on fluid flow by hydrodynamic loads in reactor internals

  • 투고 : 2013.12.17
  • 심사 : 2014.06.19
  • 발행 : 2014.09.25

초록

Roles of reactor internals are to support nuclear fuel, provide insertion and withdrawal channels of nuclear fuel control rods, and carry out core cooling. In case of functional loss of the reactor internals, it may lead to severe accidents caused by damage of nuclear fuel assembly and deterioration of reactor vessel due to attack of fallen out parts. The present study is to examine fluid flows in reactor internals subjected to hydrodynamic loads. In this context, an integrated model was developed and applied to two kinds of numerical analyses; one is to analyze periodic loading effect caused by pump pulsation and the other is to analyze random loading effect employing different turbulent models. Acoustic pressure distributions and flow velocity as well as pressure and temperature fields were calculated and compared to establish appropriate analysis techniques.

키워드

참고문헌

  1. ANSYS Workbench ver.14.0 (2012).
  2. Autodesk inventor professional (2011).
  3. Autodesk showcase professional (2012).
  4. Bae, Y., Kim, Y.I. and Park, C.T. (2013), "CFD analysis of flow distribution at the core inlet of SMART", Nucl. Eng. Des., 258, 19-25. https://doi.org/10.1016/j.nucengdes.2013.02.003
  5. Chang, Y.S., Jhung, M.J., Lee, B.S., Kim, H.S. and Hur, N.S. (2013), Structural Integrity of Nuclear Components, Hanshouse, Seoul, Korea.
  6. Choi, S.B., Chang, Y.S., Choi, J.B., Kim, Y.J., Jhung, M.J. and Choi, Y.H. (2010), "Fatigue life assessment of reactor coolant system components by using transfer functions of integrated FE model", Nucl. Eng. Tech., 42(2), 590-599. https://doi.org/10.5516/NET.2010.42.5.590
  7. Gu, J.Y., Kim, K.H. and Kim, Y.S. (2010), "Development and validation of structural analysis methodology for comprehensive vibration assessment of reactor vessel internals", Proceedings of the KSME 2010 Fall Annual Meeting, 950-955.
  8. Hermansky, P. and Krajcovic, M. (2011), "The numerical simulation of the WWER440/V213 reactor pressure vessel internals response to maximum hypothetical large-break loss of coolant accident", Nucl. Eng. Des., 241(4), 1177-1183. https://doi.org/10.1016/j.nucengdes.2010.04.030
  9. Jhung, M.J. and Hwang, W.G. (1996), "Seismic response of reactor vessel internals for Korean standard nuclear power plant", Nucl. Eng. Des., 165, 57-66. https://doi.org/10.1016/0029-5493(96)01204-6
  10. Jhung, M.J., Yu, S.O. and Lim, Y.T. (2011), "Dynamic characteristics of a partially fluid-filled cylindrical shell", Nucl. Eng. Tech., 43(2), 167-174. https://doi.org/10.5516/NET.2011.43.2.167
  11. Kao, M.T., Wu, C.Y., Chieng, C.C., Xu, Y., Yuan, K., Dzodzo, M., Conner, M., Beltz, S., Ray, S. and Bissett, T. (2011), "CFD analysis of PWR core top and reactor vessel upper plenum internal subdomain models", Nucl. Eng. Des., 241(10), 4181-4193. https://doi.org/10.1016/j.nucengdes.2011.08.007
  12. Kim, K.H., Ko, D.Y. and Kim. Y.S. (2009), "Hydraulic and structural analysis methodology of RVI CVAP in Shin-Kori 4", Transaction of the Korean Nuclear Society Spring Meeting, Pyeongchang, Korea.
  13. Kim, K., Euh, D.J., Chu, I.C., Youn, Y.J., Choi, H.S. and Kwon, T.S. (2013), "Experimental study of the APR+ reactor core flow and pressure distributions under 4-pump running conditions", Nucl. Eng. Des., 265(12), 957-966. https://doi.org/10.1016/j.nucengdes.2013.07.021
  14. Kim, K.M., Lee, B.I., Lee, D., Cho, H.H., Park, J.S. and Jeong, K.H. (2012), "Pump-induced pulsating pressure distributions in a system-integrated modular reactor", Nucl. Eng. Des., 248, 216-225. https://doi.org/10.1016/j.nucengdes.2012.03.048
  15. Kim, Y.S., Kim, K.H. and Lee, J.H. (2010), "Hydraulic analysis methodology of reactor vessel internals for comprehensive vibration assessment program", Transactions of the Korean Nuclear Society Autumn Meeting, Jeju, Korea.
  16. Ko, D.Y., Kim, K.H. and Kim, S.H. (2011), "Selection criteria of measurement locations for advanced power reactor 1400 reactor vessel internals comprehensive vibration assessment program", Tran. Korean Soc. Noise Vib. Eng., 21(8), 708-713. https://doi.org/10.5050/KSNVE.2011.21.8.708
  17. Ko, D.Y. and Kim, K.H. (2013), "Structural analysis of CSB and LSS for APR1400 RVI CVAP", Nucl. Eng. Des., 261, 76-84. https://doi.org/10.1016/j.nucengdes.2013.03.012
  18. Lee, B.I., Kim, K.M., Lee, D.H., Cho, H.H., Jeong, K.H. and Park, J.S. (2012), "Measurement of flowinduced pressure variation in a scale-down SMART model", Nucl. Eng. Des., 253, 50-59. https://doi.org/10.1016/j.nucengdes.2012.08.006
  19. Park, S.Y. and Cho, J.R. (2012), "Adaptive fluid-structure interaction simulation of large-scale complex liquid containment with two-phase flow", Struct. Eng. Mech., 41(4), 559-573. https://doi.org/10.12989/sem.2012.41.4.559
  20. USNRC (2007), "Comprehensive Vibration Assessment Program for Reactor Internals during Preoperational and Initial Startup Testing", Regulatory Guide 1.20, Rev.0.
  21. USNRC (2010), "Generic Aging Lessons Learned (GALL) Report", NUREG-1801, Rev.2.
  22. Tsuji, N., Nakano, M., Takada, E., Tokuhara, K., Ohashi, K., Okamoto, F., Tazawa, Y., Inaba, Y. and Tachibana, Y. (2014), "Study of the applicability of CFD calculation for HTTR reactor", Nucl. Eng. Des., 271, 564-568. https://doi.org/10.1016/j.nucengdes.2013.12.033
  23. Wu, C.Y., Ferng, Y.M., Chieng, C.C. and Kang, Z.C. (2012), "CFD analysis for full vessel upper plenum in Maanshan nuclear power plant", Nucl. Eng. Des., 253, 285-293. https://doi.org/10.1016/j.nucengdes.2012.08.014
  24. Xu, Y., Conner, M., Yuan, K., Dzodzo, M.B., Karoutas, Z., Beltz, S.A., Ray, S., Bissett, T.A., Chieng, C.C, Kao, M.T. and Wu, C.Y. (2012), "Study of impact of the AP1000 reactor vessel upper internals design on fuel performance", Nucl. Eng. Des., 252, 128-134. https://doi.org/10.1016/j.nucengdes.2012.06.036

피인용 문헌

  1. Modal characteristics of partially perforated rectangular plate with triangular penetration pattern vol.55, pp.3, 2015, https://doi.org/10.12989/sem.2015.55.3.583
  2. Dynamic characteristics assessment of reactor vessel internals with fluid-structure interaction vol.49, pp.7, 2017, https://doi.org/10.1016/j.net.2017.05.003