TRAIL - Technical Report Archive and Image Library

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

Exact relativistic Fokker-Planck coefficients for a plasma

Review and correlation of in-pile zircaloy-2 corrosion data and a model for the effect of irradiation

Effect of energy degradation on the critical current in an OGRA-type device

A phenolic resin ion exchange process for decontaminating low-radioactivity-level process water wastes

Further evaluation of amines as extractants for uranium from sulfate liquors

The corrosion of aluminum alloys in the Oak Ridge Research Reactor

Radioactivity of nuclear reactor cooling fluids

Stability of plasmas against electrostatic perturbations

A preliminary study of the aging behavior of wrought columbium-1% zirconium alloys

The single-scattering approximation to the gamma-ray air-scattering problem

Removal of silica from Darex dissolver solutions

Purification of degraded tributyl phosphate-hydrocarbon diluent solutions by distillation :status summary

The release of Kr⁸⁵ from UO₂ in ORR capsules

Titanium pump loop for aqueous solutions at high temperatures

The calcination in air of beryllium oxalate trihydrate to beryllium oxide

Cerenkov radiation intensity calculations for Sr⁹⁰ and Co⁶⁰ in water

A study of dissolution of reactor fuels containing zirconium in a titanium vessel

Whirlaway :a three-dimensional, two-group neutron diffusion code for the IBM 7090 computer

Structure and use of ALGOL 60

Evaluation of ultimate disposal methods for liquid and solid radioactive wastes.

Use of analog computers for simulating the movement of isotopes in ecological systems

Electrostatic ion-cyclotron plasma instabilities in a two-fluid hydrodynamic theory

A model for fission-gas release from porous fuels in low-permeability containers

Recording equipment for internal friction measurements

Extraction of neptunium from acidic solutions by organic nitrogen and phosphorus compounds

Remotely controlled shearing of pipe and structural members

Ecological sampling and meteorological calculation of fallout on forests near Oak Ridge

Sorption of uranium on zirconium oxide

An investigation of the transfer of uranyl nitrate across the water-tributyl phosphate interface by the method of photographic photometry

A study of fission product transport mechanisms in high temperature gas-cooled reactor fuel elements

Surface preparation of metallographic specimens of zirconium-base alloys containing copper

Photon wavelength and energy conversion tables

INOR-8-graphite-fused salt compatibility test

Plasma stability analysis employing equilibrium constants of motion

Status report no. 1 on Clinch River study

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

Separation of transplutoniums from lanthanides by tertiary amine extraction

Lid tank shielding facility measurements behind the ML-1 mockup

Interdiffusion of helium and argon in speer moderator no. 1 graphite :(a terminal report on large-pore graphites-experimental phase)

A survey of the hazards involved in processing liquid metal bonded fuels

Miscellaneous experiments relating to the processing of CETR fuel by sulfex-thorex and darex-thorex processes

Development of ring-joint flanges for use in the HRE-2

Determinations of the kinetics and mechanisms of deboronization at 1135⁰C

Barytes concrete for radiation shielding :mix criteria and attenuation characteristics

The ORNL badge dosimeter and its personnel monitoring applications

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

Experiment on continuous release of fission gas during irradiation :(an interim report)

Atomic and molecular collision cross sections of interest in controlled thermonuclear research

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