Year: 1962
Type: report
Abstract: The results of 36 irradiation experiments in the LITR (2.5-3.0 x 10^ n/cm^-sec) with various thoria and thoria-urania slurries at thoria blanket temperatures indicate that at relatively low irradiation exposures there is no gross deterioration of slurry handling characteristics.Particle damage occurred in most cases, but resistance to damage appeared to increase with increasing oxide firing temperatures.With the exception of cesium, strontium, and iodine, fission products were mainly associated with the slurry solids.Of the corrosion products (iron, chromium, nickel), only nickel appeared to a significant extent in the slurry supernatant.During the course of the work a dash-pot-stirred autoclave was developed which permitted fluids and slurries to be stirred while under irradiation.Autoclave operation could be controlled in such a way that the relative viscosity of the auto clave contents could be measured as a function of temperature and while the material was being irradiated.Ability to stir was not impaired by irradiation even at fission power levels equivalent to the average power level of a thoria slurry in a breeder reactor blanket.
DOI: 10.2172/4828424
Author: J McBride
Language: English
Subfield: Materials Chemistry
Field: Materials Science
Domain: Physical Sciences
Open Access status: gold
OpenAlex ID: W4408174742