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- 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