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Technical Report Archive and Image Library
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TRAIL Microcard Collection
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Technical Report Archive and Image Library
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TRAIL Microcard Collection
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ORNL (Series)
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Gas-Cooled Reactor Project Progress Report
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Maritime Reactor Project Annual Progress Report
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ORNL Homogenous Reactor Project Progress Report
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Nuclear Safety Program Annual Progress Report for Period Ending December 31, 1967
An Elliptic Integral Computer Package for Magnetic Fields, Forces, and Mutual Inductances of Axisymmetric Systems, and a Versatile Line-Tracing Routine
Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV
Optical Mapping of Oak Ridge Research Reactor Experiment Tubes
Spectra of Gamma Rays Produced by the INteraction of ~160-MeV Protons with Be, C, O, Al, Co, and Bi
An Assessment of Certain Avenues of Improvement for Nuclear Desalination Technology
Mechanical Properties of Some Refractory Metals and their Alloys
Recent Studies of Boiling Burnout
Some Major Fuel-Irradiation Test Facilities of the Oak Ridge National Laboratory
Thorium-Uranium-233 Oxide (Kilorod) Facility : Rod Fabrication Process and Equipment
Army Reactors Program Annual Progress Report: 1962
Fuel Cycle Program Progress Report: Eleventh Quarter, January-March 1963
Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962
Cumulative Bibliography of Literature Examine by the Radiation Shielding Information Center
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Sixth Quarterly Report, January-March 1963
Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution
Gas-Cooled Reactor Project Quarterly Progress Report: December 1961
Polfit II, an IBM 7090 Program for Polynomial Least Squares Fitting
Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor
Mathematics Panel: Annual Progress Report for Period Ending December 31, 1960
Sulfex Process: Engineering-Scale Semicontinuous Decladding of Unirradiated Stainless Steel-Clad UO2 and UO2-ThO2
Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960
Nuclear Superheat Project Fabrication, Irradiation and Evaluation of Superheat Fuel Element SH-1 and SH-2
Air Scattering of Co60 Gamma Rays: Theory Versus Experiment
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