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- Fast-flux measurements in the ORR core
- The experimental design for BeO irradiation experiments ORNL 41-8 and ORNL 41-9
- Program STATEST :an application of the method of statistical estimation to the calculation of neutron flux in anisotropically scattering media by Monte Carlo
- Calculation of fission-source thermal-neutron distribution in water by the transfusion method
- Calculations of thermal-neutron flux distributions in concrete-walled ducts using an albedo model with Monte Carlo techniques
- Stress-strain measuring system for in-reactor use in high neutron flux
- Determination of thermal-neutron flux distributions in the Bulk Shielding Reactor II by copper wire activation techniques
- Neutron flux spectra in the experimental facilities of the Oak Ridge Research Reactor
- Reactor yield calculations for 81 radioisotopes produced by (n,[gamma]) reactions at fluxes of 10⁷ to 10¹⁶ n/cm©ʹ²℗·sec for irradiation times of 30 minutes to one year