Browse TRAIL Inventories

Solids separation by a hydraulic cyclone with a batch underflow receiver

Solubilities of selected metals in mercury :Hermex process

Gas-cooled reactor program quarterly progress report for period ending ...

Controlled pH stripping of uranium from amines

In-pile corrosion test loops for aqueous homogeneous reactor solutions

Effect of plasma potential on DCX steady state

Oak Ridge National Laboratory 1963

Heat transfer, burnout, and pressure drop for water in swirl flow through tubes with internal twisted tapes

Organic compounds in fission reactors :

Corrosion of materials by lithium at elevated temperatures

Adsorption of xenon and argon on graphite

Getting multichannel analyzer data in and out of the IBM-7090 for processing

Manganese bath measurements of [Eta] of U²³³ and U²³⁵

Effect of temperature on radiator weight for space vehicle power plants

Procedure for testing reactor controls pulse amplifier and preamplifier

Annual progress report civil defense research project.

Purification of beryllium compounds :a literature survey

Zirflex process for PWR blanket fuel :

Investigation of spectrochemical solution-methods of analysis :the use of designed experiments and statistical methods of analysis in the interpretation of data

Controlled potential coulometric titration of plutonium :application to PRFR samples

Recovery of uranium from DI (2-ethylhexyl) phosphoric acid (dapex) extractant with ammonium carbonate

Metallurgy of zircaloy-2 :

Sulfex-thorex and darex-thorex processes for the dissolution of consolidated edison power reactor fuel :laboratory development

Inline instrumentation :gamma monitor, uranium coloimeter

Nuclear data processing on an IBM-704 computer with the Condac program

Development of an electrolytic cell for removal of nickel from HRT fuel solutions

Fused salt fuel processing in the ORNL volatility pilot plant

Purification of promethium by liquid-liquid extraction

Modified zirflex process for dissolution of 1-10% U-Zr alloy fuels in aqueous NH₄F-NH₄NO₃-H₂O₂ :laboratory development

Processing of high-fired uranium dioxide fuels by a reduction - mercury extraction - oxidation process

Mathematics Panel progress report :for period ending September 1, 1958 to December 31, 1959

Some properties of infinite, lumped solenoids

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


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