22.251 / 22.351 Systems Analysis of the Nuclear Fuel Cycle, Fall 2005 由 Kazimi, Mujid S.

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Theoretical studies on some aspects of molten fuel-coolant thermal interaction 由 Kazimi, Mujid S.

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A condensed review of nuclear reactor thermal-hydraulic computer codes for two-phase flow analysis 由 Kazimi, Mujid S., Massoud, Mahmoud

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The effect of virtual mass on the characteristics and the numerical stability in two-phase flow 由 No, H. C., Kazimi, Mujid S.

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An investigation of the physical and numerical foundations of two-fluid representation of sodium boiling with applications to LMFBR experiments 由 No, Hee Cheon, Kazimi, Mujid S.

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Nuclear Energy Options for Hydrogen and Hydrogen-Based Liquid Fuels Production 由 Yildiz, Bilge, Kazimi, Mujid S.

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Sensitivity of Economic Performance of the Nuclear Fuel Cycle to Simulation Modeling Assumptions 由 Bonnet, Nicephore, Kazimi, Mujid S.

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Impact of Alternative Nuclear Fuel Cycle Options on Infrastructure and Fuel Requirements, Actinide and Waste Inventories, and Economics 由 Guérin, Laurent, Kazimi, Mujid S.

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Stability Analysis of Natural Circulation in BWRs at High Pressure Conditions 由 Hu, Rui, Kazimi, Mujid S.

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Sustainability Features of Nuclear Fuel Cycle Options 由 Passerini, Stefano, Kazimi, Mujid S

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Analysis of forced convection degraded core cooling in light water reactors 由 Mohammed, S. M., Kazimi Mujid S.

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Modeling of corium/concrete interaction 由 Lee, Min, Kazimi, Mujid S.

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Transient response of a single heated channel 由 Lee, Min, Kazimi, Mujid S.

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Thermal hydraulics of core/concrete interaction of severe LWR accidents 由 Kao, Lainsu, Kazimi, Mujid S.

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Nuclear systems / 由 Todreas, Neil E., Kazimi, Mujid S.

Nuclear systems [electronic resource] / 由 Todreas, Neil E., Kazimi, Mujid S.

Development and testing of three dimensional, two-fluid code THERMIT for LWR core and subchannel applications 由 Kelly, John Edward, Kazimi, Mujid S.

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Development of models for the sodium version of the two-phase three dimensional thermal hydraulics code THERMIT 由 Wilson, Gregory James, Kazimi, Mujid S.

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A two dimensional, two fluid model for sodium boiling in LMFBR fuel assemblies 由 Granziera, Mario Roberto, Kazimi, Mujid S.

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22.314J / 1.56J / 2.084J Structural Mechanics in Nuclear Power Technology, Spring 2004 由 Kazimi, Mujid S., Buyukozturk, O. (Oral)

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