Development of a thermal-hydraulic safety analysis code RETAC for AP1000

Progress in Nuclear Energy

Volumn 55, Issue , 2012, Pages 49-60

  Wang, Weiwei ^a   Tian, Wenxi ^a   Su, Guanghui ^a   Qiu, Suizheng ^a  

^a XI'AN JIAOTONG UNIVERSITY   (China)

Author keywords

AP1000; Passive safety; RETAC; Safety analysis; Thermal hydraulic

Indexed keywords

AP1000; PASSIVE SAFETY; RETAC; SAFETY ANALYSIS; THERMAL HYDRAULICS;

ACCIDENTS; CODES (SYMBOLS); COMPUTER SIMULATION; DIFFERENTIAL EQUATIONS; GEARS; POWER QUALITY; SECURITY SYSTEMS; TWO PHASE FLOW;

TRANSIENT ANALYSIS;

EID: 84855695993     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2011.11.002     Document Type: Article

References (37)

1. M.A. Abdallah, H.M. Ahmed, A.R. Mohammad, and E.S.N. Mohammad Pressurizer transients dynamic model Nucl. Eng. Des. 73 1982 447 453
2. N. Nahavandia Amir, and Makkencheryb Suresh An improved pressurizer model with bubble rise and condensate drop dynamics Nucl. Eng. Des. 12 1970 135 147
3. G.S. Auh, C.S. Ko, S.J. Lee, D.H. Hwang, D.S. Kim, and S.H. Chae Development of transient simulation code for pressurized water reactors J. Kor. Nucl. Soc. 19 1987 198 204
4. S.M. Baek, H.C. No, and I.Y. Park A Non-equilibrium three region model for transient analysis pressurized water reactor pressurizer system Nucl. Technol. 74 1986 213 221
5. Barnett, T.W.T.; Mclntyre, C.J.; Buker, J.C.; 1972. LOFTRAN-PWR system transient code. WCAP-7907, Westinghouse Electric Corporation.
6. R.C. Baron Digital model simulation of a nuclear pressurizer Nucl. Sci. Eng. 52 1973 283 291
7. J.C. Chen Process design development Int. Eng. Chem. 5 1966 322
8. S.W. Churchill, and H.H.S. Chu Correlating equations for laminar and turbulent free convection from a vertical plate Int. J. Heat Mass Transfer 18 1975 1323
9. John G. Collier Convective Boiling and Condensation second ed. 1981 McGraw-Hill
10. C.W. Gear Numerical Initial Value Problems in Ordinary Differential Equation 1971 Prentice-Hall Englewood cliffs, NJ
11. Guo, Y.J.; 1994. The development and applications of the thermal-hydraulic analysis codes for nuclear power systems. Doctor thesis. Xi'an Jiaotong University, China.
12. G.Y. Han A mathematical model for the thermal-hydraulic analysis of nuclear power plants Int. Commun. Heat Mass Transfer 27 2000 795 805
13. G.Y. Han, P.A. Thomas, and A.S. Phillip Jr. Thermal-hydraulic modeling and transient analysis of pressurized water reactors Int. Commun. Heat Mass Transfer 26 1999 909 918
14. Hind marah, A.C.; 1974. Gear: ordinary differential equation system solver, Lawrence Livarmore Laboratory, Report UCID-30001, Revision 3, December.
15. Jens, W.H.; Lottes, P.A.; 1951. Argonne National Laboratory, Report No. 4627.
16. I. Langmuir Convection and conduction of heat in gases Phys. Rev. 34 1912 401
17. K.J. Lee, U.C. Lee, J.S. Kim, and S.H. Kim The loss of coolant flow accident analysis in Kori-1 J. Kor. Nucl. Soc. 17 1985 256 266
18. C.G. Lin, Z.S. Yu, and Y. Ouyang An Advanced Passive Plant AP1000 2008 Atomic Energy Press Beijing
19. McFadden, J.H.; Hughes, E.D.; Narum, R.E.; 1981. RETRAN-02: a program for transient thermal-hydraulic analysis of complex fluid flow system. EPRI-NP-1850-CCM, Idaho.
20. F.J. Moody Maximum two-phase vessel blowdown from pipes J. Heat Transfer 88 1966 285 295
21. J.A. Redfield, V. Prescop, and S.G. Margolis Pressurizer performance during loss of load tests at shippingport: analysis and test Nucl. Appl. 4 1968 189 196
22. RELAP5/MOD3.3, 2001. Code manual volume 1: code structure, system models, and solution methods, NUREG/CR-5535.
23. T.L. Schulz Westinghouse AP1000 advanced passive plant Nucl. Eng. Des. 236 2006 1547 1557
24. E.N. Sieder, and G.E. Tate Heat transfer and pressure drop of liquids in tubes Ind. Eng. Chem. 28 1936 1429 1435
25. W.X. Tian, S.Z. Qiu, Y. Guo, G.H. Su, and D.N. Jia Development of a thermal-hydraulic analysis code for CARR Ann. Nucl. Energy 32 3 2005 261 279 (Pubitemid 40142524)
26. W.X. Tian, S.Z. Qiu, G.H. Su, D.N. Jia, X.M. Liu, and J.W. Zhang Thermohydraulic and safety analysis on China advanced research reactor under station blackout accident Ann. Nucl. Energy 34 2007 288 296
27. Tong, L.S.; 1972. Boiling crisis and critical flux. TID-25887.
28. Untermeyer, S.; Weills, J.; 1952. Rep. ANL-4790.
29. U.S. NRC, 2004. Final safety evaluation report for AP1000 Design. Washington, DC.
30. W. Wagner, and J.R. Cooper The IAPWS industrial formulation 1997 for the thermodynamic properties of water and steam J. Eng. Gas Turbines Power 122 2000 150 184
31. Westinghouse Electric Company, 2004. Westinghouse AP1000 Design Control Document Rev. 14.
32. R.F. Wright Simulated AP1000 response to design basis small-break LOCA events in APEX-1000 test facility Nucl. Eng. Technol. 39 4 2007 287 298
33. Y.W. Wu, G.H. Su, S.Z. Qiu, and C.J. Zhuang Development of a thermal-hydraulic analysis software for the Chinese advanced pressurized water reactor Nucl. Eng. Des. 240 2010 112 122
34. T. Yonomoto, Y. Kukita, and R. Schultz Heat transfer analysis of the passive residual heat removal system in ROSA/AP600 experiments Nucl. Technol. 124 1 1998 18 30 (Pubitemid 128587503)
35. H.J. You, Z.H. Cui, and Y.P. Cheng A nonequilibrium multi-region model for nuclear power pressurizer Nucl. Power Eng. 22 2001 133 137
36. D.L. Zhang, S.Z. Qiu, C.L. Liu, and G.H. Su Steady thermal hydraulic analysis for a molten salt reactor Nucl. Sci. Techniq. 19 3 2008 187 192
37. D.L. Zhang, S.Z. Qiu, and G.H. Su Development of a safety analysis code for molten salt reactors Nucl. Eng. Des. 239 12 2009 2778 2785