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Publications by T. A. Taiwo

Liquid Salt - Very High Temperature Reactor : Survey of Sodium-Cooled Fast Reactor Fuel Handling Systems for Relevant Design and Operating Characteristics.

2006English

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Basis of Technical Standard on Fuel for Sodium-Cooled Fast Breeder Reactor

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Nuclear and Thermal Design for High Temperature Gas Cooled Reactor (GTHTR300C) Using MOX Fuel

Transactions of the Atomic Energy Society of Japan
RiskNuclear EnergyEngineeringReliabilitySafetyQuality
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Effective Coolant Flow Rate of Flange Type Fuel Element for Very High Temperature Gas-Cooled Reactor.

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
1989English

Options for Treating High-Temperature Gas-Cooled Reactor Fuel for Repository Disposal

1992English

An Analysis of Testing Requirements for Fluoride Salt Cooled High Temperature Reactor Components

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Gas-Cooled Fast Reactor

Nature
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1968English

Gas Cooled Fast Reactor

1972English

Uranium Nitride--Sodium Paste Fuel for Fast-Reactor Blankets.

1968English

Conceptual Reactor Design Study of Very High Temperature Reactor (VHTR) With Prismatic-Type Core

Journal of Power and Energy Systems
2008English

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