TRAIL - Technical Report Archive and Image Library

Components of the fused-salt and sodium circuits of the aircraft reactor experiment

Two beryllium-moderated critical assemblies

Effective neutron removal cross sections for carbon and oxygen in continuous mediums

A bibliographic file of technical report abstracts useful to reactor control system engineering

Cyclotrons and high-energy accelerators -1958

Bibliography on semiconductor nuclear radiation detectors

Evidence for the uniform radiation life shortening predicted by information theory

Correlation of cavitation inception data for a centrifugal pump operating in water and in sodium patassium alloy (Nak)

Nuclear reaction cross sections from the nitrogen bombardment of sulfur

Status report on waste disposal in natural salt formations

A study of pre-acceleration in beta-ray spectroscopy

Stability effects of surface currents on a pinched plasma containing a uniform volume current

An investigation of hot ductility of inconel and inconel x

HRP blanket processing studies of O₂-H₂ hazards in a loop pressurizer

Deformation textures in uranium-aluminum alloys

A computer for a position indicating system

An investigation of the stresses in a discontinuity region of a pressure vessel

The effect of the "tendency to report injuries" on minor accident statistics

Developments in continuous ion exchange equipment for AEC applications

Calculation of the photoneutron flux in the water near the bulk shielding reactor

An electrolytic procedure for the removal of ruthenium and nitrate from alkaline waste solutions

Determination of oxygen in lithium metal

Methods of remotely removing the bed from a sand filter

The recovery of uranium from sulfate solutions by solvent extraction with tributyl phosphate

The failure of structural metals subjected to strain-cycling conditions

The use of tri-n-octylphosphine oxide in the solvent extraction of thorium from acidic solutions

Tables of the activity coefficient of A 1-1 electrolyte and its derivatives calculated using a modified Debye-H©·uckel equation

Some problems in statistical inference

Review of experimental and theoretical studies concerning the age of fission neutrons in heavy water

Declading of PWR blanket fuel elements with aqueous ammonium fluoride solutions

Equipment decontamination methods for the fused salt-fluoride volatility process

The effect of partially ionized impurities on a DCX device

Loop studies on the behavior of preformed ZrO₂ in uranyl sulfate solution

Analysis of the recent TSF secondary gamma-ray experiment

Application of hindered settling to particle size measurement

Nuclear structure effects in internal conversion coefficients by configuration mixing

The effect of epithermal fission on aqueous homogeneous reactors

The recovery of uranium and plutonium from stainless steel sulfate decladding solutions by ion exchange

On the connection between flux and slowing-down density

Gas cooled, molten salt heat exchanger :design study

An investigation of thermal-transient decay at a fluid-solid interface and in turbulent flow through circular ducts

Molten-salt reactor program status report

The Oak Ridge relativistic isochronous cyclotron

Critical mass studies.

Monte Carlo calculations of fluxes and dose rates resulting from neutrons multiply scattered in air

Guide to the phase diagrams of the fluoride systems

Kinetics of the thermal decomposition of uranyl fluoride.

High-temperature mechanical properties of Hastelloy B amd Hastelloy W

A square-wave cyclotron oscillator

Segregation in uranium-aluminum alloys and its effect on the fuel loading of aluminum-base fuel elements

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