Browse TRAIL Inventories

Chemistry of the intercycle evaporator incident of November 20, 1959

Waste disposal in salt.

HFIR preliminary physics report

Slurry feed-pump development

Nonnuclear uses for depleted uranium

Milne problem with capture

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

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

Determination of thorium in rock samples by gamma spectrometry

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

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

A study of the kinetics of uranyl sulfate exchange with a strong base anion resin

Radiation accidents :medical aspects of neutron and gamma-ray exposures

Measurement of the vapor pressure of TBP

Publications, reports, and papers for 1961- from Oak Ridge National Laboratory

Thermonuclear Division semiannual progress report for period ending ...

Laboratory development of the acid thorex process for recovery of Consolidated Edison Throium Reactor fuel

Metallurgy of zircaloy-2 :

Multikilocurie production of krypton-85

Preparation of high-density oxides and vibratory compaction in fuel tubes

The cosine-cubed neutron spectrometer

Survey of potential vapor-phase explosions in darex and sulfex processes

Calculations of neutron age in H₂O and other materials

Processing of uranium carbide reactor fuels.


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