Browse TRAIL Inventories

Critical experiments and nuclear safety at Oak Ridge National Laboratory

Boron-aluminum and boron-uranium-aluminum alloys for reactor application

Investigation of the factors affecting sensitization of army package power reactor (APPR-1) fuel elements

Declading of PWR blanket fuel elements with aqueous ammonium fluoride solutions

Segregation in uranium-aluminum alloys and its effect on the fuel loading of aluminum-base fuel elements

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

A study of problems associated with release of fission products from ceramic fuels in gas-cooled reactors

Development of the Sulfex process for decladding stainless-steel-clad power reactor fuel elements with sulfuric acid

Fission product distribution in ORR fuel elements

A failure analysis for the low-temperature performance of dispersion fuel elements

Decladding of Consolidated Edison Power reactor fuel by Sulfex and Darex processes :cyclic dissolution experiments

Process for dissolution of Borax IV reactor fuel :laboratory development

Surface temperatures of irradiated ORR fuel elements cooled in stagnant air

Sulfex-thorex and darex-thorex processes for the dissolution of consolidated edison power reactor fuel :laboratory development

Operational safety of the ORNL graphite reactor using enriched-uranium fuel

Corrosion associated with fluorination in the Oak Ridge National Laboratory fluoride volatility process

Corrosion associated with hydrofluorination in the Oak Ridge National Laboratory fluoride volatility process

A device to simulate the service thermal conditions in EGCR-type fuel elements

An investigation of the corrosion resistance of brazing alloys for austenitic stainless steel fuel elements for service in 565⁰ F pressurized water

Dissolution of BeO- and Al₂O₃-base reactor fuel elements.

Evaluation of the boron content in fuel plates fabricated for the first core loading of the Army SM-1 Reactor, formerly APPR-1

Summary report :an evaluation of the substitution of zircaloy for stainless steel in N.S. Savannah fuel-element containers

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


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