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Publications by T.I. McSweeney
Fast Reactor Fuel Assembly Thermal Hydraulic Development Program: Sodium Heat Transfer.
Improved Material Accounting for Plutonium Processing Facilities and a /Sup 235/U-HTGR Fuel Fabrication Facility
Related publications
Uranium Nitride--Sodium Paste Fuel for Fast-Reactor Blankets.
High Heat Program, Thermal Hydraulic Computer Models
Sodium Heat Engine Development Program
Use of Instrumented Fuel Assemblies for the Core Thermal--Hydraulic Analysis. Garigliano Development Program.
SODIUM-COOLED REACTORS FAST CERAMIC REACTOR DEVELOPMENT PROGRAM. Twenty- Seventh Quarterly Report, May--July 1968.
Basis of Technical Standard on Fuel for Sodium-Cooled Fast Breeder Reactor
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Use of Neutron Filters for Fast Reactor Fuel Irradiations in a Thermal Reactor Core.
Advanced Reactor Development: The LMR Integral Fast Reactor Program at Argonne
Fusion Technology
Development of Uranium-Free TRU Metallic Fuel Fast Reactor Core
