Browse TRAIL Inventories

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 :

Organic compounds in fission reactors :

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

HFIR preliminary physics report

Slurry feed-pump development

Nonnuclear uses for depleted uranium

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 ...

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


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