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Issue DateTitleAuthor(s)
Aug-1962Reprocessing of homogeneous beryllium-based reactor fuel - a suggested scheme for the selective aqueous dissolution of the matrixFarrell, MS; Temple, RB
Sep-1965Laboratory 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
Jun-1966Laboratory development of the grind-leach process for the H.T.G.C.R. fuel cycle, Part II - dissolution of beryllia in nitric acid solutionsFarrell, MS; Isaacs, SR; Shying, ME
Jan-1968Development 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
Jul-1965The recovery of beryllium from beryllium oxide matrix fuels through its oxyacetateFarrell, MS; Szego, LE; Yates, PB
Jul-1967Laboratory 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
Nov-1967A conceptual design study of a low throughput reprocessing facility for nuclear fuelCairns, RC; May, JR; Baillie, MG; Farrell, MS

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