Call Number (LC) Title Results
E 1.99:ornl/tm-8657 Evaluation of NEPA-based environmental commitments at four geopressure design wells 1
E 1.99:ornl/tm-8659 Fourier-Motzkin elimination for mixed systems 1
E 1.99:ornl/tm-8662 Studies of the effect of selected nondonor solvents on coal liquefaction yields 1
E 1.99:ornl/tm--8665 Rate of Pu(IV) polymer formation in nitric acid solutions. A parametric study 1
E 1.99:ornl/tm-8668 Solvent extraction of heptavalent technetium and rhenium by tributyl phosphate. Consolidated Fuel Reprocessing Program and Basic Energy Sciences Programs 1
E 1.99:ornl/tm-8669 Preliminary study of possible ORELA replacement options 1
E 1.99:ornl/tm-8671 Investigation of edge neutral flux on the ISX-B tokamak using a low-energy charge-exchange analyzer 1
E 1.99:ornl/tm-8676 User's guide for ALEX uncertainty propagation from raw data to final results for ORELA transmission measurements. 1
E 1.99:ornl/tm-8681 Bulk Shielding Facility quarterly report, July, August, and September 1982 1
E 1.99:ornl/tm-8682 Investigation of the concentration, distribution, and inventory of radionuclides in the sediment of Process Waste System Basin 3524 1
E 1.99:ornl/tm-8686 Benefit-cost aspects of long-term isolation of uranium mill tailings 1
E 1.99:ornl/tm-8694 Provisional monitoring program for SWSA 7 1
E 1.99:ornl/tm-8695 Evaluation of the ORNL area for future waste burial facilities 1
E 1.99:ornl/tm-8697 1982 US-CEC neutron personnel dosimetry intercomparison study 1
E 1.99:ornl/tm-8698 Nineteenth nuclear accident dosimetry intercomparison study, August 9-13, 1982 1
E 1.99:ornl/tm-8699 Simulation of inertial and beam-driven effects on impurities in tokamak plasmas 1
E 1.99:ornl/tm-8704 Stable-isotope customer list and summary of shipments, FY 1982 1
E 1.99:ornl/tm-8707 Monte Carlo calculations of neutron and gamm-ray energy spectra for fusion-reactor shield design comparison with experiment. 1
E 1.99:ornl/tm-8711 Use of Gd-loaded scintillation-detector systems for inverse beta-decay reactions 1
E 1.99:ornl/tm-8712 EBT reactor analysis 1