Browse TRAIL Inventories

Critical experiments for the high flux reactor

Neutron monitoring by means of nuclear track film (NTA) :(supplementary report)

Attenuation by water of radiations from a swimming pool type reactor

Neutron slowing down by hydrogen in the consistent P₁ approximation

Some remarks on the slowing down of neutrons in hydrogen

A flux depression experiment in the MTR

On the connection between flux and slowing-down density

Monte Carlo calculations of fluxes and dose rates resulting from neutrons multiply scattered in air

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

Neutron flux spectra in the experimental facilities of the Oak Ridge Research Reactor

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

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


Published Year

Subject

Author