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Evolution of Halides from Halogenated Plastics Exposed to Gamma Radiation

Description: Abstract: "The purpose of the investigation was to study the effects of gamma radiation from a cobalt-60 source on the physical properties and halogen evolution from the plastics polyvinyl chloride and polymonochlorotrifluoroethylene. Samples exposed for 2 to 28 days to a source of approximately 25,000 Roentgens per minute showed an appreciable evolution of both fluorine and chlorine. Tests on polymonochlorotrifluoroethylene for tensile, impact, and shear strength showed rapidly decreasing valu… more
Date: November 15, 1952
Creator: Byrne, J. & Mann, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Numerical Calculation of Blast Waves in Non-Uniform Atmosphere

Description: The problem of a blast wave propagating through an inhomogeneous atmosphere is set up for computation by the CRC LORA. Previous treatments of this problem have used various simplifying assumptions such as that of purely radial flow. Since, however, pressure gradients in this situation will not in general be in the direction of rays from the blast center, non-radial flow will exist, and there is reason to believe that for large distances this effect will play a prominent role. Therefore, a progr… more
Date: November 15, 1954
Creator: Fife, Paul C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Organic Moderated Reactor Experiment Progress Report: August-October 1956

Description: Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the second report of the series, and covers the period from August 1, 1956 through October 31, 1956" (p. 3).
Date: November 15, 1957
Creator: Trilling, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plating Thickness Tester

Description: An electromagnetic eddy current instrument is described that is capable of measuring copper and nickel plating 1 to 8 mils thick plated on bismuth mandrils of various sizes and shapes.
Date: November 15, 1957
Creator: Fitch, C. E., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Physics Primer

Description: Report that describes the reactor physics of the processes used to produce plutonium at Hanford Laboratories. This includes a basic explanation of nuclear physics and the principles of the reactor process.
Date: November 15, 1957
Creator: Lockwood, E. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hot-Pressure Bonding of OMR Fuel Plates

Description: Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date: November 15, 1959
Creator: Alm, G. V.; Binstock, M. H. & Garrett, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Terminal Status Report for the Processing Refabrication Experiment

Description: Introduction: A low-capacity, low-decontamination plant can be built, as part of a power reactor complex, to avoid long distance transfer of fuel to a high-capacity aqueous processing plant. Activation of such a complex, with the processing plant adjacent to the reactor it serves, could decrease the cost of the integrated fuel cycle. The study of this concept is a major objective of the Processing Refabrication Experiment (PRE).
Date: November 15, 1959
Creator: Sinizer, D. I.; Mattern, K. L. & Kendall, E. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Algorithm for Construction Feasible Schedules and Computing Their Schedule Times

Description: "An algorithm for the generation of feasible schedules and the computation of the completion times of the job operations of feasible schedule is presented. Using this algorithm, the distribution of schedule times over the set of feasible schedule—or a subset of feasible schedules—was determined for technological orderings that could occur in a general machine shop. These distributions are found to be approximately normal. Biasing techniques corresponding to “first come first serve,” random choi… more
Date: November 15, 1960
Creator: Heller, Jack & Logemann, George
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak

Description: Review of previous work is presented in addition to the results of recent studies concerning loss of primary coolant when the system is cold and pressurized and the problem of supplying adequate cooling following the injection of light water.
Date: November 15, 1960
Creator: Wittenbrock, N. G. & Muraoka, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Theory of Cusped Geometries

Description: "The loss of particles through a cusp of a particular containment geometry utilizing cusped magnetic field lies is considered. A velocity space loss criterion analogous to the loss cone in the mirror machine is derived. The effect of a uniform longitudinal magnetic field perpendicular to the containing field is considered and a loss criterion is derived. The effect of the longitudinal field is to decrease cusp losses.
Date: November 15, 1960
Creator: Kileen, John
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Utilization of Radiactive Isotpoes in Coal Process Research

Description: "With careful attention to details, tritium assays of satisfactory accuracy have been achieved on low activity standard samples by dry combustion and liquid scintillations counting of the product water.This method is faster, more accurate and dependable than the zinc fusion-ion chamber method fro low level tritium assays. At 380 degrees C, tritium loses from hydrocarbon tracers by isotopic exchange is significant and must be corrected for in tracer measurements at this elevated temperature."
Date: November 15, 1960
Creator: Yavorsky, P. M. & Gorin, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Studies of Transient Effects in Fast Reactor Fuels

Description: An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO₂ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F.… more
Date: November 15, 1962
Creator: Field, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Beta Radiation Processing at Rigorous Conditions

Description: Introduction: The literature reflects ever expansive studies of radiation chemistry over the past twenty years However, in the application of radiation processing to chemical reactions, in general and excepting a few isolated cases, the yield of useful products have been so low as to preclude practical utilization. Thus, for many reactions,radiation alone at ambient conditions is not a sufficient agent for economical production. Hence, we are led to the investigation of radiation effects on … more
Date: November 15, 1963
Creator: Yavorsky, P. M. & Gorin, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Seventeenth Quarter, August-October 1963

Description: From introduction: "This is the seventeenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Date: November 15, 1963
Creator: Flock, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Uranium Dioxide Fuel Rod Center Melting Test in the Vallecitos Boiling Water Reactor

Description: Technical report describing that as part of the AEC Fuel Cycle Program, tests are being conducted to evaluate the significance of current fuel design limitations that do not permit the maximum fuel temperature to exceed the melting point of UO2. The reliability of prediction of the fuel rod operating conditions that will cause melting of the UO2 was evaluated by means of a calibration test conducted in the Vallecitos Boiling Water Reactor. Conclusions: (a) The central portion of the 3.15-cm dia… more
Date: November 15, 1963
Creator: Williamson, H. E. & Hoffmann, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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