Browse TRAIL Inventories

Critical experiments for the high flux reactor

Procedure for erection of the materials testing reactor mock-up

The new bulk shielding facility at Oak Ridge National Laboratory

The elements of nuclear reactor theory.

Recoil reactions in the chain reacting pile.

The effects of metallurgical variables on the corrosion of extruded beryllium

Development of hydrogen-oxygen recombiners :progress report

The Tower Shielding Facility safeguard report

Calculations of shielding for burned-out reactor fuel elements

The inhour formula for a circulating-fuel nuclear reactor with slug flow

Analysis of spherical pressure vessel having an energy source within the wall

Oak Ridge National Laboratory reactor controls computer

Determination of the power of the bulk shielding reactor :

Report on design and placement techniques of barytes concrete for reactor biological shields

Fuel let-down heat exchanger.

A stability criterion for reactor systems

Reactivity measurements with the bulk shielding reactor :control rod calibrations; beam hole coefficients; partial reflector coefficients

Some economic aspects of thorium breeder reactor

Cost study of a power increase for the bulk shielding reactor

Operation of the ORNL graphite reactor and the low-intensity test reactor--1954

Temperature distribution in flat plate with exponential heat source

Decontamination of the homogeneous reactor experiment

Aqueous homogeneous research reactor :feasibility study

Low-power criticality experiments on the homogeneous reactor experiement (HRE-1)

Fuel costs in single-region homogeneous power reactors

The reactivity effect of an air tank against one face of the bulk shielding reactor

Radionuclides in reactor cooling water :identification, source and control

A study of the nuclear and physical properties of the ORNL graphite reactor shield

Two beryllium-moderated critical assemblies

Calculation of the photoneutron flux in the water near the bulk shielding reactor

Molten-salt reactor program status report

Solubility relations among some fission product fluorides in NaF-ZrF₄-UF₄ (50-46-4 mole %)

Oxidation of uranium tetrafluoride in a moving-bed reactor

Reactor safety system response

Organic compounds in fission reactors.

Laboratory development of the sulfex process for the dissolution of consolidated Edison power reactor fuel

Project Aquarium :laboratory and field corrosion tests for the Geneva Conference Reactor

Gas-cooled reactor coolant choice

Resonance absorption of neutrons in nuclear reactors

Nuclear characteristics of spherical, homogeneous, two-region, molten-fluoride-salt reactors

Improvement of the high-temperature strength properties of reactor materials after fabrication

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


Published Year

Subject

Author

‹‹ previous 1 2 next ››