Browse TRAIL Inventories

Coulometric determination of uranium in power-reactor-fuel-dissolver solutions

Three-minute irradiation at variable power density of prototype CETR fuel pellets

Preparation of americium dioxide by thermal decomposition of americium oxalate in air

Group-theoretical treatment of time- and energy-dependent multiple scattering, with aplication to the slowing-down of neutrons

Corrosion resistance of various ceramics and cermets to liquid metals

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

Fused salt heat transfer.

Relaxation characteristics of Inconel at elevated temperatures

Standard operating procedure for the pool critical assembly

Radiation transmission through boral and similar heterogenous materials consisting of randomly distributed absorbing chunks

Dissociation of H₂⁺ by hydrogen

Equipoise :an IBM-704 code for the solution of two-group, two-dimensional, neutron diffusion equations in cylindrical geometry

Low-temperature thermoluminescence of the gamma-irradiated amino acids and proteins

Molten-salt reactor program quarterly progress report for periods ending ...

The stability of europium oxide in silicon-bearing stainless steel

Pseudoscalar interaction in nuclear beta decay

Design and scaleup of mixer-settlers for the dapex solvent extraction process

An empirical study of the sampling distributions of some disease incidence estimates

Crunch :an IBM-704 code for calculating N successive first-order reactions

A generalized sorting subroutine for the oracle

On the convergence of steady state multiregion diffusion calculations

A study of spectrophotometric methods for the determination of osmium

Maritime reactor project annual progress report for period ending ...

Army package power reactor project annual progress report for period ending ...

Some X-ray and fast neutron response characteristics of silver metaphosphate glass dosimeters

The angular distribution of alpha particles emitted by oriented Np²³⁷ nuclei

Thermonuclear project semiannual report for period ending ...

Purification of kilocurie quantities of promethium-147 by ion exchange

Molecular association in alkali halide vapors

Articles published in technical journals, reports issued, papers presented at scientific meetings, theses completed, and inventions disclosed during 1959 by ORNL staff members.

Testing the uniformity of variance in arithmetic and logarithmic units of a Y-variable for classes of an X-variable

Determination of thorium in rock samples by gamma spectrometry

Instrumentation and Controls Division Annual Progress Report, July 1, 1960

Molten-Salt Reactor Program Quarterly Progress Report: July 1960

Gas-Cooled Reactor Project Quarterly Progress Report: September 1960

Homogeneous Reactor Project Quarterly Progress Report: May-July 1960

Chemical Technology Division Annual Progress Report, August 31, 1960

Neutron Physics Division Annual Progress Report, September 1, 1960

Metallurgy Division Annual Progress Report, July 1, 1960

Table of electron wave functions at the nuclear surface

Mathematics Panel annual progress report for period ending ...

Experimental Evaluation of the Radiation Protection Afforded by Typical Oak Ridge Homes Against Distributed Sources

Phase equilibria in molten salt breeder reactor fuels.

Thermocouple research to 1000⁰C :final report November 1, 1957, through June 30, 1959

Adsorption of krypton and xenon by various materials

Corrosion associated with fluorination in the Oak Ridge National Laboratory fluoride volatility process

Effect of heat flux on the corrosion of aluminum by water.

Production of uranium metal from UF₆ by direct reduction with lithium or sodium amalgam

Corrosion associated with hydrofluorination in the Oak Ridge National Laboratory fluoride volatility process

The mechanical properties of INOR-8


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