Browsing by Author Farrell, MS
Showing results 1 to 9 of 9
| Issue Date | Title | Author(s) |
| Nov-1967 | A conceptual design study of a low throughput reprocessing facility for nuclear fuel | Cairns, RC; May, JR; Baillie, MG; Farrell, MS |
| Jan-1968 | Development of solvent extraction processes for the H.T.G.C.R. fuel cycle, Part 3 - chemical data for the extraction of actinides and fission products from aqueous beryllium sulphate solutions using amines. | Fardy, JJ; Farrell, MS |
| Sep-1958 | Diluents for the solvent extraction of thorium using tributyl phosphate: general consideration and the third phase problem. | Farrell, MS; Goldrick, JD |
| Nov-1959 | Dissolution of sintered thoria. | Farrell, MS |
| Sep-1965 | Laboratory development of the grind-leach process for the H.T.G.C.R. fuel cycle, Part 1 - dissolution of urania-thoria fuel particles in nitric acid solutions. | Farrell, MS; Isaacs, SR |
| Jul-1967 | Laboratory development of the grind-leach process for the H.T.G.C.R. fuel cycle, Part 4 - leaching and dissolution of beryllia-based fuels. | Shying, ME; Lee, EJ; Farrell, MS |
| Jun-1966 | Laboratory development of the grind-leach process for the H.T.G.C.R. fuel cycle, Part II - dissolution of beryllia in nitric acid solutions | Farrell, MS; Isaacs, SR; Shying, ME |
| Jul-1965 | The recovery of beryllium from beryllium oxide matrix fuels through its oxyacetate | Farrell, MS; Szego, LE; Yates, PB |
| Aug-1962 | Reprocessing of homogeneous beryllium-based reactor fuel - a suggested scheme for the selective aqueous dissolution of the matrix | Farrell, MS; Temple, RB |
