Browse TRAIL Inventories

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


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