Search U.S. government technical reports digitized or harvested by TRAIL.
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
A stability criterion for reactor systems
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.
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