Browse TRAIL Inventories

A three-region, two-group, two-dimensional reactor code for the Oracle

Critical experiments and nuclear safety at Oak Ridge National Laboratory

A Monte Carlo method of calculating the response of a point detector at an arbitrary position inside a cyldrical shield

The organization, administration, and operation of a radiochemical pilot plant

The sampling of alkali metal systems with the modified MSA sampler

A survey of plutonium spectrum data

The action of sodium hydroxide melts on alloys of nickel, molybdenum, and iron at 815⁰ C

Uranium raw materials process cost estimates one through ten, November 15, 1955

Study in activation analysis

Kinetic calculations for homogeneous reactors

Radiation induced nitrite formation from concentrated nitrate solutions

Determinations of free acid in solutions of uranyl sulfate

Neutron scattering

Temperature distribution in flat plate with exponential heat source

Decontamination of the homogeneous reactor experiment

Narrative status report, November 11, 1955

Development and testing of vacuum melted nickel :Molybdenum alloys with minor alloying additions

Optical properties and X-ray diffraction data for some inorganic fluoride and chloride compounds

Progress report of pilot plant section :raw materials process testing, January 1955

Determination of boron in fluoride salts

Improved techniques for the isotopic analysis of boron on the mass spectrometer

Neutron absorption by fissionable materials in the 5 to 50 Kev energy range

The effect of simulated weld thermal cycles on the properties of hastelloy B

X-ray diffraction data for some uranium compounds

Absolute determination of power produced in a nominally zero power reactor

Oxidation characteristics of the alkali metals.

Progress report of process test section for ...

Activities in the KCl-FeCl₂ and LiCl-FeCl₂ systems

The Production of C¹⁴ by the Be₃N₂ process

Use of the Higgins continuous ion exchange contactor in recovering uranium from aqueous slurries

Raw materials process testing program semiannual progress report

Homogeneous reactor project :quarterly progress report for period ending

Determination of dissolved oxygen in lubricating fluids

Iterative methods for the approximate solution of linear algebraic systems. :Self-adjointness in one-group multi-region diffusion problems.

A BEV high current accelerator :an invited paper presented at the Southeastern Section Meeting of the APS at Nashville, Tennessee, March 30, 1956

Impact behavior of thorium

Solid State Division Semiannual Progress Report, February 29, 1956

Health Physics Division Annual Progress Report, January 31, 1955

Instrumentation and Controls Division Semiannual Progress Report, January 31, 1955

Pressure rise in TBR following rapid addition of reactivity

Health Physics Division Annual Progress Report, July 31, 1970

Separation of fission products from aluminum waste solutions by ion exchange

The buildup of heavy isotopes during thermal neutron irradiation of uranium reactor fuels

Army package power reactor critical experiment

Two-phase product formed in the reaction between fused sodium hydroxide and inconel

Corrosion products formed in the reaction between fused sodium hydroxide and iron-rich alloys of iron, chromium, and nickel

Progress report on separation and recovery of uranium and thorium from sulfate liquors by the Amex process

Uranium-235 fission-product production as a function of thermal neutron flux, irradiation time, and decay time.

Analysis and design of the frozen seal

Pulse pumping :a means transfer of pulse column fluids


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