Call Number (LC) Title Results
E 1.99:dp-1632 Determination of free acid by standard addition method in potassium thiocyanate 1
E 1.99:dp-1633 Component failure-rate data with potential applicability to a nuclear fuel reprocessing plant 1
E 1.99:dp-1643 Hydrogen compatibility handbook for stainless steels 1
E 1.99:dp-1649 Applicability of hydroxylamine nitrate reductant in pulse-column contactors 1
E 1.99:dp-1655 Neptunium (IV) oxalate solubility. [22, 45, 60°C] 1
E 1.99:dp-1656 Plutonium-uranium separation in the Purex process using mixtures of hydroxylamine nitrate and ferrous sulfamate 1
E 1.99:dp-1657 Reprocessing RERTR silicide fuels 1
E 1.99:dp-1658 Two-stage precipitation of neptunium (IV) oxalate 1
E 1.99:dp-1662 DEVELOPMENT OF A SLURRY-FED IN-CAN MELTER FOR NUCLEAR DEFENSE WASTE 1
E 1.99:dp-1664 Trioxane-initiated formic acid denitration 1
E 1.99:dp-1665 Study of the U₃O₈-Al thermite reaction and strength of reactor fuel tubes 1
E 1.99:dp-1666 Dissolution of plutonium metal in HNO/sub 3/-N/sub 2/H/sub 4/-KF 1
E 1.99:dp-1689 Controlled PuO₂ particle size from Pu(III) oxalate precipitation 1
E 1.99:dp-1690 Process control for a continuous uranyl nitrate evaporator 1
E 1.99:dp-1704 Adaptation of U(IV) reductant to Savannah River Plant Purex processes 1
E 1.99:dp-1723 Cerium oxalate precipitation 1
E 1.99:dp-1732 Recovery of plutonium from electrorefining anode heels at Savannah River 1
E 1.99:dp-1740 Weldability of tritium-charged 304L stainless steel 1
E 1.99:dp-1744 Analysis of residual organic materials in aqueous radioactive streams from the Purex process 1
E 1.99:dp-1751 An automated instrument for controlled-potential coulometry System documentation. 1