A review of thermal hydraulic analysis methodology for PWR steam generators and ATHOS3 code applications

Progress in Nuclear Energy - Tập 25 - Trang 7-70 - 1991
A.K Singhal1, G Srikantiah2
1CFD Research Corporation, Huntsville, AL 35805, U.S.A.
2Electric Power Research Institute, Palo Alto, CA 94303, U.S.A.

Tài liệu tham khảo

Green, 1988, Thermal hydraulic and corrosion aspects of PWR steam generator problems, Heat Trans. Engng, 9, 1 Solomon, 1985, Principles of steam generator degradation Keeton, 1990, ATHOS3: A Computer Program for Thermal-Hydraulic Analysis of Steam Generators, Vol. 1: Mathematical and Physical Models and Method of Solution; Vol. 2: Programmer's Manual; Vol. 3: User's Manual, Vol. 1–3 Singhal, 1984, ATHOS: A Computer Program for Thermal-Hydraulic Analysis of Steam Generators, Vol. 4: Applications Vander Vorst, 1982, Calculation of Phase Separation by Centrifugal Force, ASME Paper 82-FE-5 Wang, 1985, Numerical modeling of the phase separation processes in BWR and PWR steam separators, Vol. 81, 245 Fortino, 1980, Thermal-Hydraulic Analyses of Once-Through Steam Generators, EPRI NP-1431 Patankar, 1976, A calculation procedure for the transient and steady state behavior of shell-and-tube heat exchangers Launder, 1972 Lee, 1988, ATHOS3 Computer Code Verification; Vol. 1: 2/3-Scale Test, EPRI NP-5557 Ishii, 1977, One-Dimensional Drift-Flux Model and Constitutive Equations for Relative Motion Between Phases in Various Two-Phase Flow Regimes, ANL-77-47, 34 Srikantiah, 1975 Ishii, 1975, Thermo-Fluid Dynamic Theory of Two-Phase Flow Wheeler, 1986, COBRA-NC: A Thermal-Hydraulic Code for Transient Analysis of Nuclear Reactor Components, NUREG/CR-3262, PNL-4710, Vol. 1 Hetsroni, 1982 Ishii, 1979, Local Drag Laws in Dispersed Two-Phase Flow, NUREG/CR-1230 1981, TRAC-PD2: An Advanced Best Estimate Computer Program for PWR LOCA Analysis, Los Alamos LA-8709-MS, NUREG/CR-2054 Martinelli, 1948, Prediction of Pressure Drop During Forced Circulation Boiling of Water, Trans. ASME 70-695 Thom, 1964, Prediction of pressure drop during forced circulation boiling of water, Int. J. Heat Mass Transfer, 7, 709, 10.1016/0017-9310(64)90002-X Lahey, 1977 Thompson, 1964, Boiling Water Heat Transfer Burnout in Uniformly Heated Round Tubes: A Compilation of World Data with Accurate Correlations Biasi, 1967, Studies on Burnout, Energy Nucl., 14, 530 Singhal, 1983, Thermal-Hydraulic Analysis of U-Tube and Once-Through Steam Generators, Vol. 79, 331 Lellouche, 1982, A Mechanistic Model for Predicting Two-Phase Void Fraction for Water in Vertical Tubes, Channels and Rod Bundles, EPRI NP-2246-SR Duckler, 1986, Flow pattern transition in gas liquid systems; measurement and modeling Stuhmiller, 1989, Numerical Simulation of Bubbly Flow, EPRI NP6557 Stewart, 1983, VIPRE-01 Thermal Hydraulic Analysis Code for Reactor Cores, EPRI NP-2511-CCM Chan, 1986, PORTHOS—A Computer Code for Solving General Three-Dimensional, Time-Dependent Two-Fluid Equations Patankar, 1980 Anderson, 1984 Carlucci, 1982, Thermal Hydraulic Analysis of the Westinghouse Model 51 Steam Generator, EPRI NP-2683 Lee, 1986, Three-dimensional two-fluid code for U-tube steam generator thermal design analysis, 3.21 Olive, 1982, Simulation of three dimensional two-phase flow in a P.W.R. steam generator, 136 Lee, 1988, ATHOS3 Computer Code Verification, Vol. 2: 0.95-Scale Test Hopkins, 1988, Verification of the ATHOS3 Code Against Feeding and Preheat Steam Generator Test Data, EPRI NP-5728 Keeton, 1986, Thermal-Hydraulic Analysis/Data Comparisons of Two U-Tube Steam Generators Using the ATHOS3 Code, ASME 86-WA/NE-1 Lee, 1986, Comparison of ATHOS Predictions of Tube Bundle Cross-Flow Velocity with Experimental Data, ASME 86-WA/NE-2 Hiestand, 1984, ATHOS and FLOW3 Simulation of the FRIGG Heated Rod Bundle Experiment, EPRI Report Hopkins, 1983, Thermal and Hydraulic Code Verification: ATHOS2 and Model Boiler No. 2 Data, EPRI NP-2887, Vol. 1–3 Kalra, 1985, Thermal-hydraulic performance of a U-tube steam generator under controlled feed flow oscillations, 341 Singhal, 1990, An improved primary separator region model for thermal hydraulic analysis of recirculating type steam generators, Nucl. Sci. Tech. Yeh, 1973, Potential flow theory of a pressurized water reactor Hassan, 1980, Steady-state and transient prediction of a 19-tube once-through steam generator using RELAP5/MODI, Nucl. Tech., 60, 143, 10.13182/NT83-A33110 Procaccia, 1982, Tests of Types 51A and 51M Steam Generators at Bugey-4 and Tricastin-1 Nuclear Power Plants, EPRI NP-2689 Keeton, 1991 Keeton, 1986, ATHOS3 Code Analysis of Tube Plugging Effects on the Thermal-Hydraulic Characteristics of a Once-Through Steam Generator, ASME 86-WA/NE-4 Masiello, 1988, ATHOS3 code application: a fluidelastic instability analysis of a tube bundle in a recirculating-type steam generator, A7 Schwarz, 1985, Utilization of the ATHOS code for split flow economizer and flow distribution plate calculations of steam generators, HTD-Vol. 51, 57