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A. R. Wazzan

University of California, Los Angeles

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Steady-state fission gas behavior in uraniumplutoniumzirconium metal fuel elements

1989 Nuclear Engineering and Design
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Thermal-hydraulic characteristics of pressurized water reactors during commercial operation. VII: Thermal-hydraulics of the PWR Paluel 1 steam generator during commercial operation

1988 Nuclear Engineering and Design
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Thermal-hydraulic characteristics of pressurized water reactors during commercial operation: VI. Chemical analysis of secondary water in the steam generators of Bugey 4 and Tricastin 1

1987 Nuclear Engineering and Design
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Spatial viscous instability of the incompressible Falkner–Skan similarity profile at separation

1986 Physics of Fluids
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Effect of Creep on Fission Gas Swelling and Release in Irradiated Carbide Fuels

1985
- A. R. Wazzan
- D. Okrent
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Thermal hydraulic performance of a moisture separator reheater at the 900 MWe PWR Saint Laurent Unit B1

1985 Nuclear Engineering and Design
- Graham Bell
- A. R. Wazzan
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Thermal-hydraulic characteristics of pressurized water reactors during commercial operation: V. Steady state thermal measurements on the secondary side of a PWR steam generator (Tricastin 1 nuclear power plant)

1984 Nuclear Engineering and Design
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The effect of Mach number on the spatial stability of adiabatic flat plate flow to oblique disturbances

1984 Physics of Fluids
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Fission gas disposition in decay heat environment

1982 Nuclear Engineering and Design
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Tests of types 51A and 51M steam generators at Bugey 4 and Tricastin 1 nuclear power plants. Final report

1982
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Citations (1)