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논문 상세정보


An experimental study of heat transfer characteristics near the critical pressure has been performed with an internally-heated vertical annular channel cooled by R-134a fluid. Two series of tests have been completed: (a) steady-state critical heat flux (CHF) tests, and (b) heat transfer tests for pressure reduction transients through the critical pressure. In the present experimental range, the steady-state CHF decreases with increase of the system pressure for fixed inlet mass flux and subcooling. The CHF falls sharply at about 3.8 MPa and shows a trend towards converging to zero as the pressure approaches the critical point of 4.059 MPa. The CHF phenomenon near the critical pressure does not lead to an abrupt temperature rise of the heated wall, because the CHF occurs at remarkably low power levels. In the pressure reduction transients, as soon as the pressure passes below the critical pressure from the supercritical pressure, the wall temperatures rise rapidly up to very high values due to the departure from nucleate boiling. The wall temperature reaches a maximum at the saturation point of the outlet temperature, and then tends to decrease gradually.

참고문헌 (10)

  1. Y. Oka, 'Research and development of the supercritical-pressure light water cooled reactors,' Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Paper KL-02,Seoul, Seoul, Korea (2003) 
  2. D. Squarer, T. Schulenberg, D. Struwe, Y.Oka, D. Bittermann, N. Aksan, C. Maraczy, R. Kyrki-Rajamaki, A. Souyri and P. Dumaz, 'High performance light water reactor,' Nucl Eng. Des., 221, pp. 167-180 (2003) 
  3. J. D. Jackson and W. B. Hall, 'Forced convection heat transfer to fluids at supercritical pressure,' Turbulent forced convection in channels and bundles (Edited by S. Kakac and D. B.Spalding), Hemisphere,Vol. 2, pp. 563-612 (1979) 
  4. P. Dumaz and O. Antoni, 'The extension of the CATHARE2 computer code above the critical point, applications to a supercritical light water reactor,' Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Paper I00403, Seoul, Korea (2003) 
  5. S. T. Yin, T. J. Lui, Y. D. Huang and R. M. Tain, 'Measurements of critical heat flux in forced flow at pressures up to the vicinity of the critical point of water,' Proceeding of the 1988 National Heat Transfer Conference in U.S.A., Vol. 1, pp. 501-506, Houston (1988) 
  6. http://webbook.nist.gov/chemistry/, 'NIST Standard Reference Database Number 69 - March, 2003 Release,' (2003) 
  7. 'ANSI/ASME PTC 19.1, ASME performance test codes, supplement on instruments and apparatus, part 1, measurement uncertainty,' Published by ASME, New York (1985) 
  8. J. G. Collier and J. R. Thome, 'Convective boiling and condensation, 3rd edition' Oxford University Press, pp. 361-363(1994) 
  9. Se-Young Chun, Heung-June Chung, Sung-Deok Hong, Sun-Kyu Yang and Moon-Ki Chung, 'Critical heat flux in uniformly heated vertical annulus under a wide range of pressures-0.57 to 15.0 MPa,' Journal of the Korean Nuclear Society, 32[2], pp. 128-141 (2000) 
  10. I. L. Pioro, D. C. Groeneveld, L. K. H. Leung, S. S. Doerffer, S. C. Cheng, Yu. V. Antoshko, Y. Guo and A. Vasic, 'Comparison of CHF measurements in horizontal and vertical tubes cooled with R-134a,' Int. J. Heat Mass Transfer, 45, pp. 4435-4450 (2002) 

이 논문을 인용한 문헌 (1)

  1. 2008. "" Nuclear engineering and technology : an international journal of the Korean Nuclear Society, 40(2): 107~116 


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