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Publications by Bryan L. Broadhead

Feasibility Assessment of Burnup Credit in the Criticality Analysis of Shipping Casks With Boiling Water Reactor Spent Fuel

Nuclear Technology
High Energy PhysicsNuclearEngineeringNuclear EnergyCondensed Matter Physics
1995English

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Impact Analysis of Spent Nuclear Fuel Shipping Casks

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Opportunities to Increase the Productivity of Spent Fuel Shipping Casks in the United States

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CIRFT Testing of High-Burnup Used Nuclear Fuel Rods From Pressurized Water Reactor and Boiling Water Reactor Environments

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Concept of Radiation Dose Rate Sensitivity Applicable to Spent Fuel Shipping Casks. Definition of Concept and Application to Evaluation of Array Effect Obtained Upon Arranging Spent Fuels in Different Burnup States Within Same Shipping Cask.

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
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Properties of the High Burnup Structure in Nuclear Light Water Reactor Fuel

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Analysis of the Daya Bay Reactor Antineutrino Flux Changes With Fuel Burnup

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Evaluation of the Use of Homogenized Fuel Assemblies in the Thermal Analysis of Spent Fuel Storage Casks

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Manufacture of Fuel Plates for the Experimental Boiling Water Reactor

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Assessment of the Use of Extended Burnup Fuel in Light Water Power Reactors

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