Browse TRAIL Inventories

Thermal and resonance absorption cross sections of the U²³³, U²³⁵, Pu²³⁹ fission products

The catalysis of the hydrogen-oxygen reaction by aqueous slurries of thorium oxide and thorium-uranium oxide

Recovery of uranium and thorium from graphite fuels.

Controlled pH stripping of uranium from amines

Zirflex process for PWR blanket fuel :

Recovery of uranium from DI (2-ethylhexyl) phosphoric acid (dapex) extractant with ammonium carbonate

Sulfex-thorex and darex-thorex processes for the dissolution of consolidated edison power reactor fuel :laboratory development

Inline instrumentation :gamma monitor, uranium coloimeter

Fused salt fuel processing in the ORNL volatility pilot plant

Modified zirflex process for dissolution of 1-10% U-Zr alloy fuels in aqueous NH₄F-NH₄NO₃-H₂O₂ :laboratory development

Processing of high-fired uranium dioxide fuels by a reduction - mercury extraction - oxidation process

Slurry feed-pump development

Nonnuclear uses for depleted uranium

Operational safety of the ORNL graphite reactor using enriched-uranium fuel

A study of the kinetics of uranyl sulfate exchange with a strong base anion resin

Laboratory development of the acid thorex process for recovery of Consolidated Edison Throium Reactor fuel

Preparation of high-density oxides and vibratory compaction in fuel tubes

Processing of uranium carbide reactor fuels.

Recovery of uranium from amine extractants with ammonium carbonate

McCabe-Thiele graphical solution of uranium-thorium partitioning from 30% TBP-AMSCO solvent

Solvent extraction of uranium from carbonate solutions

Direct reduction of uranium hexafluoride to uranium metal by sodium :(DRUHM process)

An oxyhydrochlorination process for preparing uranium-molybdenum reactor fuels for solvent extraction :laboratory development

Recovery of uranium from amines by the high nitrate-water stripping method

Further evaluation of amines as extractants for uranium from sulfate liquors

Sorption of uranium on zirconium oxide

Processes for recovery of uranium and thorium from graphite-base fuel elements.

Use of fused salt-fluoride volatility process with irradiated urania decayed 15-30 days

A comprehensive study of the neutron activation analysis of uranium by delayed-neutron counting

Recovery of irradiated uranium by a two-stage differential extraction procedure

Off-gases from the reactions of uranium carbides with nitric acid at 90⁰C

Carburization and chemical treatments for recovery of uranium from stainless steel fuel elements

Chemical development of the 25-TBP process / J.R. Flanary, ... [et. al.].

Summary of the Kilorod Project :a semiremote 10-kg/day demonstration of ²³³UO₂-ThO₂ fuel-element fabrication by the ORNL sol-gel vibratory-compaction method

Evidence of the absence of long-lived isotopes of promethium from fission of uranium, and the purification of promethium for the establishment of a primary spectrographic standard

Efficiency and flow capacity of pulsed columns used for the separation of uranium from thorium by solvent extraction with di-sec-butylphenylphosphonate

Status and progress report on separations research and development


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