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- Boron-aluminum and boron-uranium-aluminum alloys for reactor application
- The ORNL gas-cooled reactor :materials and hazards
- High-temperature mechanical properties of Hastelloy B amd Hastelloy W
- The recrystallization and grain growth of Inconel
- Preparation of ThO₂ for homogenous reactor blanket use
- The ORNL gas-cooled reactor :advanced concepts
- Sulfex process :depassivation of stainless steel
- Micro-electrophoretic determination of the zeta potential of thorium oxide
- Laboratory development of the thorex process :progress report, December 1, 1955 to January 1, 1958
- Pilot plant preparation of thorium- and thorium-uranium oxides
- Phase diagrams of nuclear reactor materials
- Decontamination testing of highly contaminated protective coatings
- Chemical feasibility of homogenous neutron poisons for criticality contols in Consolidated Edison fuel processing solutions
- Thorex pilot plant corrosion studies.
- The mechanical properties of INOR-8
- An investigation of the corrosion resistance of brazing alloys for austenitic stainless steel fuel elements for service in 565⁰ F pressurized water
- High density slag concrete
- Summary report :an evaluation of the substitution of zircaloy for stainless steel in N.S. Savannah fuel-element containers
- Peroxide-inhibited decontamination solutions for carbon steel and other metals in the gas-cooled reactor program :progress report, November 1959-July 1962
- X-ray mass attenuation coefficients in the range of 50 to 150 kvp with data for several reactor materials
- Analysis of stress and strain in spherical shells of pyrolytic carbon
- Metallography and aging characteristics of Hastelloy B