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