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- Fundamentals of liquid-metal corrosion
- Corrosion of materials in fused hydroxides
- Automatic photometric titration of sulfate
- Determination of copper in solutions of uranyl sulfate by internal electrolysis
- U LI X-ray transition from separated isotopes
- A comparison of one-dimensional critical mass computations with experiments for completely reflected reactors
- Geometrical corrections for anisotropically emitting sources
- The chemistry of uranium(VI) orthophosphate solutions.
- A three-region, two-group, two-dimensional reactor code for the Oracle
- Kinetic calculations for homogeneous reactors
- Radiation induced nitrite formation from concentrated nitrate solutions
- Determinations of free acid in solutions of uranyl sulfate
- Neutron scattering
- Temperature distribution in flat plate with exponential heat source
- Decontamination of the homogeneous reactor experiment
- Narrative status report, November 11, 1955
- Development and testing of vacuum melted nickel :Molybdenum alloys with minor alloying additions
- Optical properties and X-ray diffraction data for some inorganic fluoride and chloride compounds
- Progress report of pilot plant section :raw materials process testing, January 1955
- Determination of boron in fluoride salts
- Improved techniques for the isotopic analysis of boron on the mass spectrometer
- Neutron absorption by fissionable materials in the 5 to 50 Kev energy range
- Progress report of process test section for ...
- Activities in the KCl-FeCl₂ and LiCl-FeCl₂ systems
- The Production of C¹⁴ by the Be₃N₂ process
- Use of the Higgins continuous ion exchange contactor in recovering uranium from aqueous slurries
- Raw materials process testing program semiannual progress report
- Homogeneous reactor project :quarterly progress report for period ending
- The effect of simulated weld thermal cycles on the properties of hastelloy B
- X-ray diffraction data for some uranium compounds
- Absolute determination of power produced in a nominally zero power reactor
- Oxidation characteristics of the alkali metals.
- Impact behavior of thorium
- Pressure rise in TBR following rapid addition of reactivity
- Determination of dissolved oxygen in lubricating fluids
- Iterative methods for the approximate solution of linear algebraic systems. :Self-adjointness in one-group multi-region diffusion problems.
- A BEV high current accelerator :an invited paper presented at the Southeastern Section Meeting of the APS at Nashville, Tennessee, March 30, 1956
- Solid State Division Semiannual Progress Report, February 29, 1956
- Health Physics Division Annual Progress Report, January 31, 1955
- Instrumentation and Controls Division Semiannual Progress Report, January 31, 1955
- Health Physics Division Annual Progress Report, July 31, 1970
- Separation of fission products from aluminum waste solutions by ion exchange
- The buildup of heavy isotopes during thermal neutron irradiation of uranium reactor fuels
- Army package power reactor critical experiment
- Two-phase product formed in the reaction between fused sodium hydroxide and inconel
- Corrosion products formed in the reaction between fused sodium hydroxide and iron-rich alloys of iron, chromium, and nickel
- Progress report on separation and recovery of uranium and thorium from sulfate liquors by the Amex process
- Uranium-235 fission-product production as a function of thermal neutron flux, irradiation time, and decay time.
- Analysis and design of the frozen seal
- Boron-aluminum and boron-uranium-aluminum alloys for reactor application