Search U.S. government technical reports digitized or harvested by TRAIL.
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.
Aqueous processes for dissolution of uranium-molybdenum alloy reactor fuel elements
A review of glove box construction and experimentation
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
Dissolution of BeO- and Al₂O₃-base reactor fuel elements.
Lifetime studies for the N.S. Savannah reactor
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
Diffusion in body-centered cubic metals zirconium, vanadium, niobium, and tantalum
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
Development of nondestructive testing techniques for the high flux isotope reactor fuel element
Snap-8 corrosion program quarterly progress report for period ending