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Irradiation Performance of Thoria-Urania Fuel Materials: Quarterly Technical Report, Number 2, October - December 1964

Description: From introduction: "Complete exploitation of the advantages of thorium as a fertile material in thermal and particular resonant spectrum reactors has been inhibited by the lack of quantitative physical property data for thoria and thoria-urania fuels."
Date: October 1964
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plant Transient Analysis of the APPR-1 by Analog Computer Methods ; Task No. IV

Description: Phase I - Plant Transient Analysis. Behavior of the basic and refined kinetic models differs only slightly. It is therefore suggested that the basic model be used in any studies where the improvement in fidelity attainable fro the refined model is not warranted by the complexities introduced by the addition of function generator to the analog circuitry and derivation of the function to be programmed. The parameter responses of both kinetic models appear to be essentially similar to those of t… more
Date: October 1, 1958
Creator: Brondel, J. O. & Tomonto, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Construction Completion Report: CAI-816, 100-N Reactor Plant

Description: Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.
Date: October 15, 1964
Creator: Buckner, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps

Description: Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Report for SM-1 Core II Without the SM-1 Core I High Burnup Elements and With the PM-1-M-2 Element

Description: Abstract: The removal of both SM-1 Core I high burnup elements from SM-1 Core II and the insertion of the PM-1-M-2 element and the SM-1 Core I spare element in SM-1 Core II is discussed. Nuclear and thermal characteristics of Core II with these changes are presented and conclusions related to the changes in the hazard potential are made. If the core change indicated by this report is made, local peaking factors will be decreased and burnout ratios will be increased. This, of course, in itself… more
Date: October 7, 1961
Creator: Coombe, J. R.; Lee, D. H. & Mathews, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Report for SM-1 Core II With the SM-1 Core II High Burnup Elements Replaced with SM-1 Core I Spare Elements

Description: Abstract: The removal of both SM-1 Core I high burnup elements from the SM-1 Core II and the insertion of two SM-1 Core I spare elements i their places are discussed. Nuclear and thermal characteristics of Core II with the change are presented and conclusion related to the change in hazard potential are made. If the core change indicated by this report is made, local peaking factors will be decreased and burnout ratios will be increased. This, of course, in itself leads to a more conservative… more
Date: October 9, 1961
Creator: Coombe, J. R.; Lee, D. H. & Matthews, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Separation of Azeotropes by Means of Diffusion through Porous Membranes

Description: Thesis discussing experiments to separate azeotropes into pure components testing eleven minimum boiling point azeotropic systems: (1) acetone-methanol, (2) carbon tetrachloride-ethyl acetate, (3) cyclohexane-ethanol, (4) benzene-isopropanol, (5) benzene-n-propanol, (6) benzene-cyclohexane, (7) benzene-methanol, (8) benzene-ethanol, (9) acetone-carbon, (10) isopropoanol-water, and (11) ethanol-water.
Date: October 1953
Creator: Hagerbaumer, Donald H. & Kammermeyer, Karl
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EOCR Control Rod and Driver Fuel Hydraulic Tests

Description: Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.
Date: October 19, 1962
Creator: Harrison, L. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Radiation Damage on SM-1, SM-1A and PM-2A Reactor Vessels

Description: Report describing the status of the SM-1, SM-1A, and PM-2A reactors, specifically regarding the effects "of irradiation on nil-ductility transition temperature and the associated problem of brittle fracture." (p. iii)
Date: October 14, 1961
Creator: McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A.; Coombe, J. R.; Kelleman, R. W.; Bobe, P. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant

Description: Cycle study performed on a closed loop Brayton cycle incorporating a gas-cooled nuclear reactor, regeneration, and compressor intercooling. The purpose of the study was to determine the effect of various cycle parameters on efficiency and cost.
Date: October 5, 1962
Creator: Miskell, R. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Zero Power Experiments on SM-1 Core II and SM-1A Core I

Description: Abstract: An analysis of SM-1 Core II and SM-1A Core I zero power experiments was made by comparing these cores to each other and to AM-1 Core I on the basis of critical bank positions, bank calibrations and available chemical analyses of the fuel plate compositions. The effects of replacing boron absorbers by europium absorbers upon rod worth and stuck rod conditions were studied. Comparisons of measured and calculated power distributions were made. It was concluded that both SM-1 Core II an… more
Date: October 5, 1960
Creator: Paluszkiewicz, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fundamentals in the Operation of Nuclear Test Reactors: Volume 2, Materials Testing Reactor Design and Operation

Description: Second volume of reports on the operation of nuclear test reactors. It includes six chapters: engineering description fo the materials testing reactor, reactor control components and instrumentation, reactor control circuitry, reactor operation, reactor shutdown and tank work, and supplemental facilities at the materials testing reactor.
Date: October 1963
Creator: Phillips Petroleum Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SM-1 Research and Development. Task XV, Zero Power Experiments for SM-1 Core II and SM-1A Core I

Description: Abstract: A zero power experiment on the SM-1 Core II included an element by element reactivity check of fuel elements and control rod absorber sections, and an estimate of burnable nuclear poison loading in stationary fuel elements. An approach to criticality was made by the inverse multiplication method, and critical rod bank position obtained as a function fuel loading up to full core loading. Minimum and maximum core reactivity measurements were obtained by selective loading of stationary f… more
Date: October 12, 1960
Creator: Robinson, R. A.; Weiss, S. H.; McCool, W. J. & Schrader, E. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Criteria for Evaluating Hazards Involved in Proposed Tests On and/or Modifications To the SM-1

Description: Abstract: This technical report elucidates principles of hazards evaluation. The concept of hazards potential is introduced and utilized to show how a reactor system perturbation will influence its nuclear safety. Literature relating to reactor safety is referenced to provide the sources of information required for hazards analysis and show how they influence a hazards evaluation. A checklist of items which should be considered in evaluating a change, test, or modification is presented.
Date: October 18, 1961
Creator: Scoles, J. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements

Description: Report containing supplementary material for "Plutonium Recycle Critical Facility, Final Safeguards Analyses." This material expands upon previously supplied safety information and resolves previously unreviewed safety questions. Appendix begins on page A.1.
Date: October 1964
Creator: Swanberg, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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