TRAIL - Technical Report Archive and Image Library

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

Dissociation and ionization of H₂⁺ by electrons and protons

Corrosion of Volatility Pilot Plant Mark I Inor-8 hydrofluorinator and Mark III L nickel fluorinator after fourteen dissolution runs

The angular distribution of fission fragments from the fast neutron-induced fission of U-234

Thermodynamic properties of molten-salt solutions

Effects of seismic vibrations on the experimental gas-cooled reactor

Cycling of cesium-134 in white oak trees on sites of contrasting soil type and moisture

An investigation of the corrosion resistance of brazing alloys for austenitic stainless steel fuel elements for service in 565⁰ F pressurized water

Effect of environment on the creep properties of type 304 stainless steel at elevated temperatures

An aerodynamic-thermodynamic study of centrifugal compressors

A generalized least squares program for the IBM 7090 computer

IBM-7090 Gaussian integration package with optional point quadrature

Evaluation of ultimate disposal methods for liquid and solid radioactive wastes :shipment of calcined solids

Low temperature thermoluminescence of gamma irradiated potassium dihydrogen phosphate

Diffusion of Zr⁹⁵ in body-centered cubic iodide zirconium

The preparation, properties, and uses of americium-241, alpha-, gamma-, and neutron sources

The effect of prompt neutrons on the direction and time of flight of fission fragments

Studies of the scintillation process in CsI(Tl)

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

Fabrication and assembly of a teflon dropping-mercury electrode

Proton recoil energy loss distribution in plane geometry

Pulse height calculations for a parallel plate ionization chamber containing electron attaching gases

Effects of fast-neutron irradiation and high temperature on beryllium oxide

Nightmare :an IBM 7090 code for the calculation of gamma heating in cylindrical geometry

In-pile-autoclave test of zircaloy-2 corrosion in UO₂(NO₃)₂ solution and of solution stability

Calculation of the pulse-height response of NaI(Tℓ) scintillation counters

Numerical analysis of neutron resonances

Equipoise-3 :a two-dimensional, two-group, neutron diffusion code for the IBM-7090 computer

An evaluation of the uranium contamination on the surfaces of alclad uranium-aluminum alloy research reactor fuel plates

Recovery of strontium and rare earths from PUREX wastes by solvent extraction

The twenty grand program for the numerical solution of few-group neutron diffusion equations in two dimensions

Status report on evaluation of solid waste disposal at ORNL.

Optical emission from irradiated thin metallic foils

The experimental design for BeO irradiation experiments ORNL 41-8 and ORNL 41-9

The preparation of high-purity beryllium oxide through the acetylacetone-EDTA solvent extraction process

Feasibility studies :nondestructive testing of the Enrico Fermi Reactor Core B fuel element

Dissolution of BeO- and Al₂O₃-base reactor fuel elements.

Soluble neutron poisons as a primary criticality control in shielded and contained radiochemical facilities

Aqueous processing of thorium fuels

Production of tritium by contained nuclear explosions in salt.

Studies of the longitudinal development of high-energy electron-photon cascade showers in copper

A remark on the second fundamental theorem in one-velocity transport theory

The Plasma Eater :a device to measure the rate of flow of a plasma

Evaluation of the boron content in fuel plates fabricated for the first core loading of the Army SM-1 Reactor, formerly APPR-1

Molten-Salt Reactor Program Semiannual Progress Report: for Period Ending August 31, 1962

Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962

Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1962

Nuclear Safety Program Semiannual Progress Report: for Period Ending June 30, 1962

Reactor Chemistry Division Annual Progress Report for Period Ending January 31, 1962

Maritime Reactor Project Annual Progress Report, November 30, 1961

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