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- 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
- Some economic aspects of thorium breeder reactor
- Reactivity measurements with the bulk shielding reactor :control rod calibrations; beam hole coefficients; partial reflector coefficients
- 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
- Reactor safety system response
- 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
- 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 :
- 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
- Organic compounds in fission reactors :
- 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 ...