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Ionic Equilibria and Anion Exchange of Uranyl Sulfate Solutions
Theoretical investigation on the nature of ion exchange of acidified uranyl sulfate solutions with Dowex 21K, a strong base ion exchange resin.
Date:
September 28, 1962
Creator:
Stein, P. E.
System:
The UNT Digital Library
The Flora of Healthy Dogs: [Part] 1. Bacteria and Fungi of the Nose, Throat, and Lower Intestine
Report documenting the isolation and identification of microorganisms found in the noses, throats, and lower intestines of twenty two dogs. The most frequently observed organisms were E. coli and S. viridans.
Date:
September 1962
Creator:
Clapper, W. E. & Meade, G. H.
System:
The UNT Digital Library
Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant
From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
Date:
September 30, 1959
Creator:
Linenberger, G. A.
System:
The UNT Digital Library
Full Power and Limited Endurance Test of the ML-1 Nuclear Power Plant (ANSOP 16625A)
Report presenting "[t]he results of performance analyses of the ML-1 nuclear power plant based on the test data obtained during ANSOP 16625A" (p. v).
Date:
September 1964
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962
Report issued by Oak Ridge National Laboratory that discusses progress and work performed by the Chemical Technology Division.
Date:
September 21, 1962
Creator:
Oak Ridge National Laboratory. Chemical Technology Division.
System:
The UNT Digital Library
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1963
Report issued by Oak Ridge National Laboratory that describes research and progress at the Chemical Technology Division.
Date:
September 20, 1963
Creator:
Oak Ridge National Laboratory. Chemical Technology Division.
System:
The UNT Digital Library
Metallurgy Division Annual Progress Report, July 1, 1960
Report documenting ongoing research and development undertaken by the Metallurgy Division of the Oak Ridge National Laboratory.
Date:
September 30, 1960
Creator:
Oak Ridge National Laboratory. Metallurgy Division.
System:
The UNT Digital Library
Experimental Breeder Reactor-II (EBR-II) Shield Design
Report describing the EBR-II shield and the methods employed in arriving at the final design. The major shield design problems for that reactor are enumerated and discussed.
Date:
September 1962
Creator:
Grotenhuis, M.; McArthy, A. E. & Rossin, A. D.
System:
The UNT Digital Library
The Graetz Problem in Cocurrent-Flow, Double-Pipe, Heat Exchangers
Report showing "that the Graetz Problem pertaining to the cocurrent-flow, double-pipe, heat exchanger can be studied analytically by extensions of familiar mathematical techniques" (p. 7).
Date:
September 1964
Creator:
Stein, Ralph P.
System:
The UNT Digital Library
Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model
Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
Date:
September 1, 1964
Creator:
Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
System:
The UNT Digital Library
6144-Channel Time-of-Flight Analyzer
Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Date:
September 1964
Creator:
Walker, R. A. & Russell, J. T.
System:
The UNT Digital Library
Analog Computer Simulation of a Pulsed Extraction Column
Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).
Date:
September 1964
Creator:
Benham, R. D. & Wilburn, N. P.
System:
The UNT Digital Library
Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies
Report regarding the calcination of full level Purex and Redox waste carried out "in a remotely operated pilot plant consisting of a radiant-heat spray calciner and a pot calciner and their associated off-gas equipment" (p. 4). This contains details of the calcination, effects on the waste, and difficulties encountered.
Date:
September 1964
Creator:
Allemann, R. T.; Roberts, F. P. & Upson, U. L.
System:
The UNT Digital Library
Chemical Technology Division Annual Progress Report, May 31, 1961
Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.
Date:
September 21, 1961
Creator:
Oak Ridge National Laboratory. Chemical Technology Division.
System:
The UNT Digital Library
Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: September, 1959 Through August, 1960
Report documenting experience gained by operating the spare PRTR Primary Process Pump. This includes descriptions of equipment used, testing procedures, and operating history.
Date:
September 16, 1960
Creator:
Scott, P. A.
System:
The UNT Digital Library
Failure Test of a Double Chambered NaK-Filled Irradiation Capsule
Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.
Date:
September 1961
Creator:
Kosut, B. S.; Leggett, R. D. & Marshall, R. K.
System:
The UNT Digital Library
Thermal Conductivity of UO2
Report discussing the thermal conductivity of uranium dioxide. The first part of the report includes the thermal effects on the substance's physical form, while the second part describes the experimental details.
Date:
September 1962
Creator:
Daniel, J. L.; Matolich, J., Jr. & Deem, H. W.
System:
The UNT Digital Library
Portable Radiation Survey Instrument
Report describing a portable radiation survey instrument, its design, and usage.
Date:
September 1963
Creator:
Sheen, E. M. & Spear, W. G.
System:
The UNT Digital Library
A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments
Report issued by the Argonne National Laboratory discussing a computer program used for fast reactor safety experiments. As stated in the summary, "this report gives a detailed description of a hybrid-computer program for calculating temperatures in a multi-region, axisymmetric, cylindrical configuration consisting of solid materials bounded by flowing coolant. Included is an explanation of the mathematical methods, together with a discussion of special features, input-output descriptions, and several sample problems" (p. 7). This report includes tables, and illustrations.
Date:
September 1967
Creator:
Bryant, Lawrence T.; Amiot, Lawrence W.; Dickerman, Charles E. & Stephany, William P.
System:
The UNT Digital Library
Standard Practices for Design of MTR and ETR Safety Circuits
Report containing notes for designing safety circuits for the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR).
Date:
September 15, 1957
Creator:
Jones, L. H.
System:
The UNT Digital Library
Startup Operation of a Production Facility for Separating Barium-140 from MTR Fuel
Report describing "the startup operation of a batch production facility for separating and purifying barium-140 from short-cooled MTR fuel" (p. 3).
Date:
September 1, 1957
Creator:
Legler, Billy Mason; Fairbourne, S. F.; Kelly, P. N. & Robinson, R. A.
System:
The UNT Digital Library
Chemical Processing Instrumentation and Control Research Program
Report regarding the chemical processing instrumentation designs and problems at the Idaho Chemical Processing Plant.
Date:
September 18, 1957
Creator:
Schneider, Harry
System:
The UNT Digital Library
The Design, Installation, and Testing of the Gas-Cooled Reactor UO₂ Irradiation Experiment at the NRTS
Report regarding sixteen experiments performed with a miniature re-entrant gas loop. Includes design problems and difficulties encountered, as well as their solutions.
Date:
September 8, 1961
Creator:
Porter, E. H.
System:
The UNT Digital Library
Gas-Cooled Fast Reactor Concepts
Report describing the performance characteristics of gas-cooled fast reactors, which compare well with those of sodium-cooled fast reactors. With oxide fuel and helium, CO2, and SO2 coolant at pressures of 1000 to 1500 psia, the reactors have slightly higher breeding ratios than comparable sodium-cooled reactors.
Date:
September 1964
Creator:
Oak Ridge National Laboratory. Reactor Division. Gas-Cooled Reactor Project.
System:
The UNT Digital Library