Startup transient simulation for natural circulation boiling water reactors in PUMA facility

Nuclear Engineering and Design

Volumn 236, Issue 22, 2006, Pages 2365-2375

  Kuran, S ^a   Xu, Y ^a   Sun, X ^a   Cheng, L ^a   Yoon, H J ^a   Revankar, S T ^a   Ishii, M ^a   Wang, W ^b  

^a PURDUE UNIVERSITY   (United States)

^b U S NUCLEAR REGULATORY COMMISSION   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

BOILER CIRCULATION; COMPUTER SIMULATION; OSCILLATIONS; PRESSURE EFFECTS;

NATURAL CIRCULATIONS; PRESSURE SCALING; REACTOR DOME PRESSURES;

BOILING WATER REACTORS;

EID: 33748625147     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2005.11.002     Document Type: Article

References (39)

1. Abe N., Yokobori S., Nagasaka H., and Tsunoyama S. Two-phase flow natural circulation characteristics inside BWR vessels. Nucl. Eng. Des. 146 (1994) 253
2. Aritomi M., Chiang J., and Mori M. Geysering in parallel boiling channels. Nucl. Eng. Des. 141 (1993) 111
3. Aritomi M., Nagahashi T., Chiang J.H., Wataru M., and Mori M. Transient behaviour of natural circulation for boiling two-phase flow (experimental results). Proceedings of the 6th Nuclear Thermal-Hydraulic, ANS Winter Meeting. Washington, DC (1990)
4. Bragt D.D.B.V., and Hagen T.H.J.J.V.D. Stability of natural circulation boiling water reactors. Part I. Description stability model and theoretical analysis in terms of dimensionless groups. Nucl. Technol. 121 (1997) 40-51
5. Bragt D.D.B.V., and Hagen T.H.J.J.V.D. Stability of natural circulation boiling water reactors. Part II. Parametric study of coupled neutronic-thermohydraulic stability. Nucl. Technol. 121 (1997) 52-62
6. Bragt D.D.B.V., Kruijf W.J.M.D., Manera A., Hagen T.H.J.J.V.D., and Dam H.V. Analytical modeling of flashing-induced instabilities in a natural circulation cooled boiling water reactor. Nucl. Eng. Des. 215 (2002) 87-98
7. Chiang J., Aritomi M., Inoue R., and Mori M. Thermo-hydraulics during startup in natural circulation boiling water reactors. Nucl. Eng. Des. 146 (1994) 241
8. Duncan J.D. SBWR, a simplified boiling water reactor. Nucl. Eng. Des. 109 (1988) 73-77
9. Fukuda K., and Kobori T. Classification of two-phase flow instability by density wave oscillation model. J. Nucl. Sci. Technol. 16 (1979) 95-108
10. Goetzmann C.A., and Grner W. SBWR-200, a low-cost NPP with high inherent safety features. Nucl. Eng. Des. 136 (1992) 65-72
11. Hagen T.H.J.J.V.D., Bragt D.D.B.V., Kaa F.J.V.D., Karuza J., Killian D., Nissen W.H.M., Stekelenburg A.J.C., and Woters J.A.A. Exploring the Dodewaard type-I and type-II stability; from startup to shutdown, from stable to unstable. Ann. Nucl. Energy 24 (1997) 8
12. Hagen T.H.J.J.V.D., Stekelenburg A.J.C., and Bragt D.D.B.V. Reactor experiments on type-I and type-II BWR stability. Nucl. Eng. Des. 200 (2000) 177-185
13. Heisler M.P. Development of scaling requirements for natural convection liquid-metal fast breeder reactor shutdown heat removal test facility. Nucl. Eng. Des. 80 (1982) 347
14. Heisler M.P., and Singer R.M. Facility Requirements for Natural Convection Shutdown Heat Removal System Testing (1981), Hemisphere, Washington, DC p. 113
15. Inada F., Furuya M., and Yasuo A. Thermo-hydraulic instability of boiling natural circulation loop induced by flashing (analytical consideration). Nucl. Eng. Des. 200 (2000) 187-199
16. Ishii, M., 1971. Flow instabilities in two-phase mixtures in thermal equilibrium. Ph.D. thesis, Georgia Institute of Technology.
17. Ishii, M., 1976. Study on flow instabilities in two-phase mixtures. Tech. Re ANL-76-23, Argonne National Laboratory.
18. Ishii M., and Jones O.C. Derivation and application of scaling criteria for two-phase flows. Two-phase Flows and Heat Transfer, vol. 1 (1976), NATO Advanced Studies Institute, Istanbul, Turkey p. 163
19. Ishii M., and Kataoka I. Scaling laws for thermal-hydraulic system under single-phase and two-phase natural circulation. Nucl. Eng. Des. 81 (1984) 411-425
20. Ishii M., and Zuber N. Thermally induced flow instabilities in two-phase mixtures in thermal equilibrium. Proceedings of the 4th International Heat Transfer Conference, vol. V. Tokyo (1970) B5.11
21. Ishii, M., Revankar, S. T., Dowlati, R., Bertodano, M. L., Babelli, I., Wang, W., Pokharna, H., Ransom, V. H., Viskanta, R., Wilmarth, T., Han, J. T., 1996. Scientific design of Purdue University Multi-Dimensional Integral Test Assembly (PUMA) for GE SBWR. Tech. Rep. NUREG/CR-6309, U.S. Nuclear Regulatory Commission.
22. Ishii M., Revankar S.T., Leonardi T., Dowlati R., Bertadano M.L., Babelli I., Wang W., Pokharna H., Ransom V.H., Viskanta R., and Han J.T. The three-level scaling approach with application to the Purdue University Multi-Dimensional Integral Test Assembly (PUMA). Nucl. Eng. Des. 186 (1998) 177-211
23. Jiang S., Zhang Y., Bo J., and Wang F. Conversion from single to two-phase operation in a natural circulation nuclear reactor. Kerntechnik 63 (1998) 132
24. Jiang S.Y., Yao M.S., Bo J.H., and Wu S.R. Experimental simulation study on startup of the 5 MW nuclear heating reactor. Nucl. Eng. Des. 158 (1995) 111-123
25. Kocamustafaogullari G., and Ishii M. Scaling criteria for two-phase flow loops and their application to conceptual 2x4 simulation loop design. Nucl. Technol. 65 (1983) 146-160
26. Lahey, R. T., Drew, D. A., 1980. An assessment of literature related to LWR instability modes. Tech. Rep. NUREG/CR-1414, U.S. Nuclear Regulatory Commission.
27. Lin J.H., Huang R.L., and Dawyer C.D. SBWR core thermal-hydraulic analysis during startup. Proceedings of the ASME, JSME Nuclear Engineering Conference, vol. 1 (1993) 281-285
28. March-Leuba J., and Rey J.M. Coupled thermohydraulics-neutronic instabilities in boiling water nuclear reactors: a review of the state of the art. Nucl. Eng. Des. 145 (1993) 97-111
29. Nissen W., Voet J.V.D., and Karuza J. The startup of the dodewaard natural circulation BWR-experiences. Proceedings of the International Confernce on Design and Safety of Advanced Nuclear Power Plants, vol. II. Tokyo (1992) 25.2
30. Nissen W.H.M., Voet J.V.D., and Karuza J. The startup of the Dodewaard natural circulation boiling water reactor-experiences. Nucl. Technol. 107 (1993) 93-102
31. Rohatgi, U., Cheng, H., Khan, H., Slovik, G., 1996. RAMONA-4B: A computer code with three-dimensional neutron kinetics for BWR system transients-modification assessment application. Tech. Rep. NUREC/CR-6359, BNL.
32. Rohatgi, U.S., Cheng, H.S., Khan, H.J., Wulff, W., 1997. Preliminary phenomena identification and ranking tables (PIRT) for SBWR startup instability. Tech. Rep. NUREG/CR-6474, U.S. Nuclear Regulatory Commission.
33. Saha P., and Zuber N. Point of net vapor generation and vapor void fraction in subcooled boiling. Proceedings of the 5th International Heat Transfer Conference (1974)
34. Shiralkar B.S., Alamgir M., and Andersen J.G.M. Thermal-hydraulic aspects of the SBWR design. Nucl. Eng. Des. 144 (1993) 213-222
35. Sinha R.K., and Kakaodkar A. Requirements for the design of the advanced heavy water reactor. IAEA TCM Workshop for Next Generation Water Cooled Reactors. Beijing, China (1990)
36. Tanimoto K., Ishii M., and Lee S.Y. Examination of transient characteristics of two-phase natural circulation within a freon-113 boiling/condensation loop. Nucl. Eng. Des. 183 (1998) 77-95
37. Wang D. The design characteristics and construction experiences of the 5 MWt nuclear heating reactor. Nucl. Eng. Des. 143 (1993) 19-24
38. Wang D., Ma C., Dong D., and Ling J. A 5 MW nuclear heating reactor. Proceedings of the Transactions of the American Nuclear Society (1990) 468-481
39. Yadigaroglu G., and Zeller M. Fluid-to-fluid scaling for a gravity- and flashing-driven natural circulation loop. Nucl. Eng. Des. 151 (1994) 49-64