Search U.S. government technical reports digitized or harvested by TRAIL.
Critical experiments and nuclear safety at Oak Ridge National Laboratory
Boron-aluminum and boron-uranium-aluminum alloys for reactor application
Declading of PWR blanket fuel elements with aqueous ammonium fluoride solutions
Hydrofluoric acid decladding of zirconium-clad power reactor fuel elements
The ORNL gas-cooled reactor :advanced concepts
Dissolution of sintered thorium-uranium oxide fuel in nitric acid-fluoride solutions
Recovery of uranium and plutonium from sulfuric acid decladding solutions
Sulfex process :depassivation of stainless steel
Project Aquarium :laboratory and field corrosion tests for the Geneva Conference Reactor
Fission product distribution in ORR fuel elements
A failure analysis for the low-temperature performance of dispersion fuel elements
Process for dissolution of Borax IV reactor fuel :laboratory development
Surface temperatures of irradiated ORR fuel elements cooled in stagnant air
Operational safety of the ORNL graphite reactor using enriched-uranium fuel
A device to simulate the service thermal conditions in EGCR-type fuel elements
Dissolution of BeO- and Al₂O₃-base reactor fuel elements.
Design and analysis of the Experimental Gas-Cooled Reactor fuel assemblies
Design and thermal analysis of EGCR control rods
Analysis of stress and strain in spherical shells of pyrolytic carbon
Outgassing behavior of EGCR moderator graphite
Carburization and chemical treatments for recovery of uranium from stainless steel fuel elements
Chemical development of the 25-TBP process / J.R. Flanary, ... [et. al.].
Mechanical cladding-fuel interactions during thermal cycling of metal-clad fuel elements
Development of nondestructive testing techniques for the high flux isotope reactor fuel element
Estimates of maximum subcritical dimensions of single fissile metal units
FABC0ST 9 :a computer code for estimating fabrication costs for rod-bundle fuel elements
Measurement and correlation of thermal resistances of UN-metal interfaces