Call Number (LC) Title Results
E 1.28:ORNL/TM-6459 Evaluation of the potential of ozone as a power plant biocide / 1
E 1.28:ORNL/TM-6461 GCFR 1/15-scale PCRV steam generator cavity closure half-thickness model test / 1
E 1.28:ORNL/TM-6462 Conversion between cold plasma modes in an inhomogeneous plasma / 1
E 1.28:ORNL/TM-6465 The corrosion of several alloys in superheated steam at 482 and 538̊C / 1
E 1.28:ORNL/TM-6466 Detection of hydrogen buildup in initially pure nonhydrogenous liquids / 1
E 1.28:ORNL/TM-6467 A procedure for estimating nonfuel operation and maintenance costs for large steam-electric power plants / 1
E 1.28:ORNL/TM-6470 Hartsville data and analysis book : phase I / 1
E 1.28:ORNL/TM-6471 The Chemical Technology Division quality assurance program for radioactive material packagings / 1
E 1.28:ORNL/TM-6472 Fish protection at steam-electric power plants : alternative screening devices / 1
E 1.28:ORNL/TM-6475 Stability criteria for multi-species ecological communities / 1
E 1.28:ORNL/TM-6476 Analysis of the chemical composition of streamflow components / 1
E 1.28:ORNL/TM-6477- A user's guide to the CALVEC software library : a computer program for emulation of CALCOMP graphics on a versatec printer/plotter / 1
E 1.28:ORNL/TM-6478 Structural model testing for prestressed concrete pressure vessels : a study of grouted vs nongrouted posttensioned prestressing tendon systems / 1
E 1.28:ORNL/TM-6479 An evaluation of the effectiveness of selected corrosion inhibitors for protection of prestressing steels in PCPVs / 1
E 1.28:ORNL/TM-6485 Mass and emission spectrometry in the Analytical Chemistry Division of Oak Ridge National Laboratory / 1
E 1.28:ORNL/TM-6486 Neutron-photon multigroup cross sections for neutron energies <̲ 600 meV / 1
E 1.28:ORNL/TM-6487 Design calculations for a 14-MeV neutron collimator / 1
E 1.28:ORNL/TM-6491 Density, acidity and conductivity measurements of uranyl nitrate/nitric acid solutions / 1
E 1.28:ORNL/TM-6492 Alpha-driven, steady-state tokamak / 1
E 1.28:ORNL/TM-6496 Hydrogen pellet fueling experiment on the ISX-A tokamak / 1