Methods for determining burnup in enriched uranium-235 fuel irradiated by fast reactor neutrons
Discussing monitors for determining burnup rate of enriched uranium 235 fuel in fast neutron environment
Richardson, P. J.↗
Engineering topics
Richardson, P. J.
Publications and source records attributed to Richardson, P. J..
The use of super 184 W as a thermal flux monitor at high temperatures.
Thermal neutron capture cross section at high temperature irradiations determined for W 184, describing radiochemical separation and flux counting techniques
Ball, L. L.↗
Tungsten thermal neutron dosimeter
Tungsten-185 activity, which is produced by neutron activation of tungsten-184, determines thermal neutron flux. Radiochemical separation methods and counting techniques for irradiated tungsten provide accurate determination of the radiation exposure.
Ball, L. L.↗
Nondestructive determination of uranium 235 distribution by fixed position gamma scanning
Nondestructive methods for fuel density determination in uranium dioxide
Berner, D. C.↗
Use of tungsten-184 as a thermal flux monitor at high temperatures
Tungsten-184 used as thermal flux monitor at high temperatures in Plum Brook reactor
Ball, L. L.↗