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- Maritime reactor waste disposal studies :solidification of ion-exchange resin with Portland cement for radioactive waste disposal
- Effect of heat flux on the corrosion of aluminum by water :
- Safeguard report on the proposed method of annealing graphite in the X-10 reactor
- Gas-cooled reactor program quarterly progress report for period ending ...
- In-pile corrosion test loops for aqueous homogeneous reactor solutions
- Organic compounds in fission reactors :
- Molten-salt reactor program quarterly progress report for periods ending ...
- Maritime reactor project annual progress report for period ending ...
- Army package power reactor project annual progress report for period ending ...
- HFIR preliminary physics report
- Slurry feed-pump development
- Nonnuclear uses for depleted uranium
- Adsorption of krypton and xenon by various materials
- Effect of heat flux on the corrosion of aluminum by water.
- Measurements at beam hole HB-2 of the Oak Ridge research reactor for south facility movable shield design study
- Aqueous processes for dissolution of uranium-molybdenum alloy reactor fuel elements
- A review of glove box construction and experimentation
- An oxyhydrochlorination process for preparing uranium-molybdenum reactor fuels for solvent extraction :laboratory development
- The release of Kr⁸⁵ from UO₂ in ORR capsules
- Lid tank shielding facility measurements behind the ML-1 mockup
- Zircex and modified zirflex processes for dissolution of 8% U-91% Zr-1% H TRIGA reactor fuel
- Postirradiation examination of 17-4 PH stainless steel control rod drive rack from SM-1 Reactor
- Blankets for thermonuclear reactors
- Isoperimetric and other inequalities in the theory of neutron transport.
- Review of zircaloy-2 and zircaloy-4 properties relevant to N.S. Savannah reactor design
- The strain-fatigue properties of Inconel.
- Effects of seismic vibrations on the experimental gas-cooled reactor
- An evaluation of the uranium contamination on the surfaces of alclad uranium-aluminum alloy research reactor fuel plates
- Dissolution of BeO- and Al₂O₃-base reactor fuel elements.
- Lifetime studies for the N.S. Savannah reactor
- Pilot-plant preparation by flame processes of 1-micron spherical thoria particles for homogeneous reactor slurries
- Experimental determination of corrections to the neutron activation of gold foils exposed in water
- An investigation of the influence of the holdup effect of double containment on reactor hazards
- Fabrication development of U₃O₈-aluminum composite fuel plates for the advanced test reactor
- Pulse-height spectra of gamma rays emitted by the stainless-steel-clad bulk shielding reactor II (BSR-II)
- Diffusion in body-centered cubic metals zirconium, vanadium, niobium, and tantalum
- Characterization of spheroidal UO₂ particles and studies of fabrication variables for core B fuel plates of the Enrico Fermi fast breeder reactor
- Fabrication of ¹³⁷Cs sources
- Techniques for performing in-reactor stress-rupture experiments
- Radioisotope production in power reactors
- Speculations on the interpretation of neutron noise experiments
- Impact resistance of fueled graphite spheres for pebble-bed reactor applications
- Stress-strain measuring system for in-reactor use in high neutron flux
- Analysis of axisymmetrically loaded cylinder-to-sphere attachments
- Determination of thermal-neutron flux distributions in the Bulk Shielding Reactor II by copper wire activation techniques
- Development of nondestructive testing techniques for the high flux isotope reactor fuel element
- Snap-8 corrosion program quarterly progress report for period ending
- Analysis of neutron fluctuation spectra in the Oak Ridge research reactor and the high flux isotope reactor