Nuclear Engineering and Technology

  • 제54권5호
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  • Pages.1860-1873
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  • 2022
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Comparative study of constitutive relations implemented in RELAP5 and TRACE - Part II: Wall boiling heat transfer

  • Shin, Sung Gil (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology (KAIST)) ;
  • Lee, Jeong Ik (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology (KAIST))
  • 투고 : 2021.07.22
  • 심사 : 2021.11.15
  • 발행 : 2022.05.25
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초록

Nuclear thermal-hydraulic system analysis codes have been developed to comprehensively model nuclear reactor systems to evaluate the safety of a nuclear reactor system. For analyzing complex systems with finite computational resources, system codes usually solve simplified fluid equations for coarsely discretized control volumes with one-dimensional assumptions and replace source terms in the governing equations with constitutive relations. Wall boiling heat transfer models are regarded as essential models in nuclear safety evaluation among many constitutive relations. The wall boiling heat transfer models of two widely used nuclear system codes, RELAP5 and TRACE, are analyzed in this study. It is first described how wall heat transfer models are composed in the two codes. By utilizing the same method described in Part 1 paper, heat fluxes from the two codes are compared under the same thermal-hydraulic conditions. The significant factors for the differences are identified as well as at which conditions the non-negligible difference occurs. Steady-state simulations with both codes are also conducted to confirm how the difference in wall heat transfer models impacts the simulation results.

키워드

과제정보

This work was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KoFONS), granted financial resource from the Nuclear Safety and Security Commission (NSSC), Republic of Korea. (No. 1903002)

참고문헌

  1. S.G. Shin, Analysis of Two-phase Constitutive Relation Models Implemented in Thermal-Hydraulic System Analysis Codes, 2019.
  2. S.G. Shin, J.I. Lee, A. Shin, M.K. Cho, et al., RELAP5 and TRACE Constitutive Relations Comparison (NUREG/IA-0522), US Nuclear Regulatory Commission, 2020.
  3. J. Zhang, et al., Prediction of flow boiling heat transfer coefficient in horizontal channels varying from conventional to small-diameter scales by genetic neural network, Nucl. Eng. Technol. 51 (8) (2019) 1897-1904. https://doi.org/10.1016/j.net.2019.06.009
  4. E.F. Tanjung, B.O. Alunda, Y.J. Lee, D. Jo, Experimental study of bubble behaviors and CHF on printed circuit board (PCB) in saturated pool water at various inclination angles, Nucl. Eng. Technol. 50 (7) (2018) 1068-1078. https://doi.org/10.1016/j.net.2018.06.011
  5. S. Jun, J.C. Godinez, S.M. You, H.Y. Kim, Pool boiling heat transfer of a copper microporous coating in borated water, Nucl. Eng. Technol. 52 (9) (2020) 1939-1944. https://doi.org/10.1016/j.net.2020.02.023
  6. T.-W. Ha, J.J. Jeong, B.-J. Yun, Improvement of the MARS subcooled boiling model for a vertical upward flow, Nucl. Eng. Technol. 51 (4) (2019) 977-986. https://doi.org/10.1016/j.net.2019.01.001
  7. P. Wu, X. Xiong, J. Shan, J. Gou, B. Zhang, B. Zhang, Improvement and validation of the wall heat transfer package of RELAP5/MOD3. 3, Nucl. Eng. Des. 310 (2016) 418-428. https://doi.org/10.1016/j.nucengdes.2016.10.049
  8. V.H. Ransom, J. Trapp, R. Wagner, in: Idaho (Ed.), RELAP5/MOD3. 3 Code Manual Volume IV: Models and Correlations, Information Systems Laboratories, IR, Maryland Idaho Falls, 2001.
  9. U. Nrc, TRACE V5. 0 Theory Manual-Field Equations, Solution Methods and Physical Models, United States Nucl. Regul. Comm, 2010.
  10. B.D. Chung, et al., MARS Code Manual Volume V: Models and Correlations, Korea Atomic Energy Research Institute, 2010.
  11. D. Bestion, System Code Models and Capabilities, 2008.
  12. A. De Crecy, P. Bazin, H. Glaeser, T. Skorek, J. Joucla, P. Probst, in: BEMUSE Phase III Report Uncertainty and Sensitivity Analysis of the LOFT L2-5 Test, vol. 4, NEA/CSNI/R (2007), 2007.
  13. F. Reventos, M. Perez, L. Batet, A. Guba, I. Toth, T. Mieusset, in: BEMUSE Phase V Report Uncertainty and Sensitivity Analysis of a LB-LOCA in ZION Nuclear Power Plant, vol. 13, NEA/CSNI/R, 2009, p. 2009.
  14. N. Basu, G.R. Warrier, V.K. Dhir, Onset of nucleate boiling and active nucleation site density during subcooled flow boiling, J. Heat Tran. 124 (4) (2002) 717-728. https://doi.org/10.1115/1.1471522
  15. J. Stewart, D. Groeneveld, Low-quality and subcooled film boiling of water at elevated pressures, Nucl. Eng. Des. 67 (2) (1982) 259-272. https://doi.org/10.1016/0029-5493(82)90145-5
  16. N. Lee, PWR FLECHT SEASET Unblocked Bundle, Forced and Gravity Reflood Task Data Evaluation and Analysis Report (No. 10), The Commission, 1982.
  17. T. Anklam, ORNL Small-Break LOCA Heat Transfer Test Series I: High-Pressure Reflood Analysis, Oak Ridge National Lab., TN (USA), 1981.
  18. C. Hyman, T. Anklam, M. White, Experimental Investigations of Bundle Boiloff and Reflood under High-Pressure Low Heat Flux Conditions, Oak Ridge National Lab., 1982.
  19. J.R. Sellars, M. Tribus, J. Klein, Heat Transfer to Laminar Flow in a Round Tube or Flat Conduit: the Graetz Probem Extended, 1954.
  20. F. Dittus, L. Boelter, Heat transfer in automobile radiators of the tubular type, Int. Commun. Heat Mass Tran. 12 (1) (1985) 3-22. https://doi.org/10.1016/0735-1933(85)90003-X
  21. V. Gnielinski, New equations for heat and mass transfer in turbulent pipe and channel flow, Int. Chem. Eng. 16 (2) (1976) 359-368.
  22. J.C. Chen, Correlation for boiling heat transfer to saturated fluids in convective flow, Ind. Eng. Chem. Process Des. Dev. 5 (3) (1966) 322-329. https://doi.org/10.1021/i260019a023
  23. H. Forster, N. Zuber, Dynamics of vapor bubbles and boiling heat transfer, AIChE J. 1 (4) (1955) 531-535. https://doi.org/10.1002/aic.690010425
  24. K. Rezkallah, G. Sims, An examination of correlations of mean heat-transfer coefficients in two-phase two-component flow in vertical tubes, in: Heat Transfer: Pittsburgh, 1987, p. 1987.
  25. D. Gorenflo, E. Baumhogger, G. Herres, S. Kotthoff, Prediction methods for pool boiling heat transfer: a state-of-the-art review, Int. J. Refrig. 43 (2014) 203-226. https://doi.org/10.1016/j.ijrefrig.2013.12.012
  26. H.C. Hottel, W. McAdams, in: McGraw-Hill (Ed.), Heat Transmission, 1954. New York.
  27. W.H. McAdams, W. Kennel, C. Minden, R. Carl, P. Picornell, J. Dew, Heat transfer at high rates to water with surface boiling, Ind. Eng. Chem. 41 (9) (1949) 1945-1953. https://doi.org/10.1021/ie50477a027
  28. S. Levy, Generalized correlation of boiling heat transfer, J. Heat Tran. 810 (1959) 37-42. https://doi.org/10.1115/1.4008126
  29. J. Holman, Heat Transfer, 1986, Mc Gran-Hill Book Company, Soythern Methodist University, 1986.
  30. J.C. Chen, R. Sundaram, F. Ozkaynak, A Phenomenological Correlation for Post-CHF Heat Transfer," Lehigh Univ, Dept. of Mechanical Engineering and Mechanics, Bethlehem, Pa.(USA), 1977.
  31. T.A. Bjornard, P. Griffith, PWR blowdown heat transfer, in: Thermal and Hydraulic Aspects of Nuclear Reactor Safety, vol. I, 1977.
  32. L.A. Bromley, Heat Transfer in Stable Film Boiling, 1949.
  33. P.J. Berenson, Film-boiling heat transfer from a horizontal surface, J. Heat Tran. 83 (3) (1961) 351-356. https://doi.org/10.1115/1.3682280
  34. B.P. Breen, Effect of Diameter of Horizontal Tubes of Film Boiling, University of Illinois at Urbana-Champaign, 1961.
  35. K. Sun, J. Gonzalez-Santalo, C. Tien, Calculations of combined radiation and convection heat transfer in rod bundles under emergency cooling conditions, J. Heat Tran. 98 (3) (1976) 414-420. https://doi.org/10.1115/1.3450569
  36. N. Hammouda, D. Groeneveld, S. Cheng, Two-fluid modelling of inverted annular film boiling, Int. J. Heat Mass Tran. 40 (11) (1997) 2655-2670. https://doi.org/10.1016/S0017-9310(96)00278-5
  37. C.A. Sleicher, M. Rouse, A convenient correlation for heat transfer to constant and variable property fluids in turbulent pipe flow, Int. J. Heat Mass Tran. 18 (5) (1975) 677-683. https://doi.org/10.1016/0017-9310(75)90279-3
  38. A. Mills, Experimental investigation of turbulent heat transfer in the entrance region of a circular conduit, J. Mech. Eng. Sci. 4 (1) (1962) 63-77. https://doi.org/10.1243/JMES_JOUR_1962_004_010_02
  39. D. Groeneveld, S. Cheng, T. Doan, 1986 AECL-UO critical heat flux lookup table, Heat Tran. Eng. 7 (1-2) (1986) 46-62. https://doi.org/10.1080/01457638608939644
  40. D. Groeneveld, et al., The 1995 look-up table for critical heat flux in tubes, Nucl. Eng. Des. 163 (1-2) (1996) 1-23. https://doi.org/10.1016/0029-5493(95)01154-4