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Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies

Description: 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.
Partner: UNT Libraries Government Documents Department
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Uranium Concentration Meter

Description: From abstract; "Two basic instruments were developed for determining the concentration of uranium in solutions. Both instruments detect the gamma activity present in a sample solution, and interpret this analysis into direct presentation as parts per million."
Date: September 24, 1956
Creator: Arnett, Orville
Partner: UNT Libraries Government Documents Department
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Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow

Description: Two-phase flow-regime transitions at elevated pressures for a single-component, trichloromonofluoromethane, were investigated for forced-circulation, upward flow in a vertical, rectangular conduit with internal dimensions of 0.380 by 1.050 inches.
Date: September 1965
Creator: Baker, James L. L.
Partner: UNT Libraries Government Documents Department
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Analog Computer Simulation of a Pulsed Extraction Column

Description: 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.
Partner: UNT Libraries Government Documents Department
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A Compendium of Information for Use in Controlling Radiation Emergencies: Including Lecture Notes from a Training Session at Idaho Falls, Idaho, February 12-14, 1958 (Revised)

Description: From introduction: This report is a summary of the lecture material in the training course held at Idaho Falls, Idaho, to familiarize members of radiological assistance teams with information helpful in the response to an unusual accident including release of radioactive materials to a populated environment.
Date: September 1960
Creator: Brodsky, Allen & Beard, G. Victor
Partner: UNT Libraries Government Documents Department
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A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments

Description: 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 … more
Date: September 1967
Creator: Bryant, Lawrence T.; Amiot, Lawrence W.; Dickerman, Charles E. & Stephany, William P.
Partner: UNT Libraries Government Documents Department
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Thermal Conductivity of UO2

Description: 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.
Partner: UNT Libraries Government Documents Department
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Experimental Breeder Reactor-II (EBR-II) Shield Design

Description: 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.
Partner: UNT Libraries Government Documents Department
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The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

Description: Report documenting "the long-term irradiation stability of the graphite used as the moderator in the Experimental Gas Cooled Reactor (EGCR) at Oak Ridge" (p. 1) by irradiating capsules at the General Electric Test Reactor. This includes the design and construction of the experiment, experiment procedures, and results of irradiation. Appendices begin on page 83.
Date: September 1964
Creator: Helm, J. W.
Partner: UNT Libraries Government Documents Department
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Standard Practices for Design of MTR and ETR Safety Circuits

Description: 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.
Partner: UNT Libraries Government Documents Department
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Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Description: 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.
Partner: UNT Libraries Government Documents Department
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Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant

Description: 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.
Partner: UNT Libraries Government Documents Department
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The Environment of Amchitka Island, Alaska

Description: Report on ecological investigations sponsored by U.S. Atomic Energy Commission.
Date: September 1977
Creator: Merritt, Melvin Leroy & Fuller, Rueben Glen
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Annual Progress Report, May 31, 1961

Description: 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.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Annual Progress Report, July 1, 1960

Description: 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.
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Fast Reactor Concepts

Description: 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.
Partner: UNT Libraries Government Documents Department
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Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report

Description: This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees.
Date: September 12, 1958
Creator: Patton, F. S.; Bailey, J. C.; Callihan, A. D.; Googin, J. M.; Jasny, G. R.; McAlduff, H. J. et al.
Partner: UNT Libraries Government Documents Department
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