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- Determination of shield requirements for a 4-inch square straight hole through the ORNL shields
- A diffusion solution for a black thermal neutron pipe duct containing a pure scattering material
- Neutron monitoring by means of nuclear track film (NTA) :(supplementary report)
- Transport parameters for thermal neutrons in water
- Gamma-ray contamination in the thermal neutron exposure facility of the Oak Ridge Reactor
- A thermal neutron survey instrument
- A determination of the diffusion length of thermal neutrons in the x-10 standard graphite pile
- An Estimation of photoneutrons from carbon-13 in an oil shield
- Effective neutron removal cross sections for carbon and oxygen in continuous mediums
- The lid tank shielding facility at Oak Ridge National Laboratory :
- Effective cadmium cutoff energies :supplement
- Radiation transmission through boral and similar heterogenous materials consisting of randomly distributed absorbing chunks
- 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