Browse TRAIL Inventories

Calculations of shielding for burned-out reactor fuel elements

Fuel costs in single-region homogeneous power reactors

Solubility relations among some fission product fluorides in NaF-ZrF₄-UF₄ (50-46-4 mole %)

Laboratory development of the sulfex process for the dissolution of consolidated Edison power reactor fuel

Zircex and modified zirflex processes for dissolution of 8% U-91% Zr-1% H TRIGA reactor fuel

Development of nondestructive testing techniques for the high flux isotope reactor fuel element


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