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Laboratory determination of normal operating flow rates with the 105-F rear face floating nozzle

Description: A new rear nozzle has been developed by Mechanical Development (A), IPD to alleviate the stuck gun barrel problem on the process tubes at F reactor. This nozzle is called the 105-F rear face floating nozzle (RFFN) and is shown in Figure 4. The purpose of this study was to determine the hydraulic operating characteristics of this nozzle and to compare these characteristics with those of the standard nozzle assemblies. This report is essentially an addendum to EW-63756 1 which presented energy lo… more
Date: February 17, 1960
Creator: Findlay, J. A.
Partner: UNT Libraries Government Documents Department
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Scintillation Counter [gamma]-Spectra Unfolding Code for the IBM-650 Computer

Description: Abstract. An IBM-650 computer code for the detailed unfolding of [gamma]-ray spectra obtained from NaI scintillation counters has been developed. The procedure is set up to remove analyzer scale dependence and to largely remove energy dependences. Computer time is about 1 minute per [gamma]-ray.
Date: February 17, 1960
Creator: West, Harry I., Jr. & Johnston, Bradley.
Partner: UNT Libraries Government Documents Department
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Transistor Counting Systems for Scintillation Detectors

Description: The requirements for multiple-coincidence counting systems with 10{sup -8}- to 10{sup -9}-sec time resolution can be met economically with presently available high-frequency transistors. The design of solid-state coincidence circuits, amplitude discriminators, and decade scalers is considered and their operation discussed. Several systems have been designed utilizing up to 180 channels from scintillation detectors.
Date: February 17, 1960
Creator: Baker, Stanley C.; Jackson, Horace G. & Mack, Dick A.
Partner: UNT Libraries Government Documents Department
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Contamination of Shipping Cask and Storage Canal Water By Fuels Irradiated In Pressurized Water Reactors - A Review Of Pertinent Subjects

Description: The subjects of fuel element failures, rates of release and re-deposition of radioactive materials from ruptured and intact fuel elements in pressurized water reactors, corrosion rates of fuels in canal water and in contact with pressurized water, activity in storage canal water, fuel meltdown studies, and decontamination are reviewed and evaluated in relation to the shipment and storage of irradiated fuel elements.
Date: March 17, 1960
Creator: King, L. J.
Partner: UNT Libraries Government Documents Department
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Development Testing And Performance Evaluation Of Liquid Metal And Molten Salt Heat Exchangers

Description: This memo contains two companion papers presented at the 1959 winter meeting of the American Nuclear Society in Washington, D.C. The papers cover work performed on development testing and performance evaluation of liquid metal and molten salt heat exchangers in support of the Aircraft Nuclear Propulsion program at the Oak Ridge National Laboratory.
Date: March 17, 1960
Creator: MacPherson, R. E.; Yarosh, Marvin M.; Amos, J. C. & Savage, H. Wesley
Partner: UNT Libraries Government Documents Department
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Proposal for an Advanced Engineering Test Reactor : ETR II

Description: Report containing "the results of a study which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR or in existing commercial test reactors" (p. 5).
Date: March 17, 1960
Creator: deBoisblanc, D. R.
Partner: UNT Libraries Government Documents Department
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PROPOSAL FOR AN ADVANCED ENGINEERING TEST REACTOR-ETR II

Description: The results of a study are presented which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR, or in existing commercial test reactors. To accomplish the design objectives called for, a reactor producing perturbed neutron fluxes exceeding 10/sup 15/ thermal neutrons per square centimeter per second and 1.5 x 10/sup 15/ e… more
Date: March 17, 1960
Creator: deBoisblanc, D R
Partner: UNT Libraries Government Documents Department
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Reamed Rear Face Parker Fitting

Description: A study and tests of the feasibility and best method of reaming rear face Parker fittings has been made. Flow increase of 8 percent, based on maintaining the same front header pressure, can be obtained at B, D, and F reactors by reaming the rear Parker fittings to .610 inch and using existing rear face hardware. Tests indicate mechanical strength will not be significantly reduced, high frequency vibration will not be increased, and that methods of reaming are available.
Date: March 17, 1960
Creator: McCarthy, P. B.
Partner: UNT Libraries Government Documents Department
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Reprocessing Uranium-Molybdenum Alloy Fuels-Dissolution in Concentrated Nitric Acid

Description: Dissolution of U--3 wt.% Mo alloys in 12 to 14 M HNO/sub 3/ solutions is discussed. Under these conditions 80 to 95% of the molybdenum content is precipitated as white hydrated molybdic oxide. Molybdic oxide precipitates are bulky; centrifuged volumes range from 6 to 17 vol.% for dissolver solutions 1.0 to 1.5:(M U. The precipitates retain some plutonium and uranium even after thorough washing with water and 1 M HNO/sub 3/. Plutonium and uranium values in washed precipitates can be recovered by… more
Date: March 17, 1960
Creator: Schulz, W. W.
Partner: UNT Libraries Government Documents Department
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THE SOLUBILITY OF NITROGEN AND OXYGEN IN LITHIUM AND METHODS OF LITHIUM PURIFICATION

Description: Experiments were conducted to determine the solubility of N and O in Li at 250 to 450 ction prod- C and to determine which of several possible purification methods is most effective in reducing the N and O content of Li. The solubility of N in Li increased from 0.04 wt.% at 250 ction prod- C to 1.31 wt.% at 450 ction prod- C. The solubility of O was found to be 0.010 wt.% at 250 ction prod- C and increased to 0.066 wt.% at 400 ction prod- C. Vacuum distillation, lowtemperature filtration. cold-… more
Date: March 17, 1960
Creator: Hoffman, E. E.
Partner: UNT Libraries Government Documents Department
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The 1958 He4 Scale of Temperatures: Part 1. Introduction, Part 2. Tables for the 1958 Temperature Scale

Description: Report containing information regarding He4 vapor pressure measurement as of 1958, the recent history of the vapor pressure temperature scale, and a series of tables containing these measurements.
Date: June 17, 1960
Creator: Brickwedde, F. G. (Ferdinand Graft), 1903-; van Dijk, H.; Durieux, M.; Clement, J. R. & Logan, J. K.
Partner: UNT Libraries Government Documents Department
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LOSS-OF-PRESSURE ACCIDENT--HOT LEG PIPING FAILURE--QUICK-OPENING VALVES IN REACTOR BYPASS LINES

Description: Activities in a study to determine the differential pressure across the EGCR core following a pipe rupture in of quick-opening valves in bypass lines around the reactor are evaluated, and recommendations concerning these valves and other components are included. (J.R.D.)
Date: June 17, 1960
Creator: Landoni, J. A.
Partner: UNT Libraries Government Documents Department
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PERIODIC RADIATION SURVEY. CORE I, SEED 1. Section 3. Test Results T- 612394

Description: Radiation levels inside the concrete enclosures but outside the reactor plant containers after shutdown were determined. Radiation levels in the 1AC, 1BC boiler chamber enclosures and in the reactor chamber enclosure were on the average higher than in previous tests. The highest reading obtained was 7.5 mr/ hr and the lowest reading was 0.03 mr/hr; the mean level was 3.76 mr/hr as compared to 1.37 mr/hr in previous tests. (W.L.H.)
Date: June 17, 1960
Partner: UNT Libraries Government Documents Department
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Rare earth analysis on a composite reactor effluent water sample

Description: This report documents analysis of radionuclides from reactor effluent water samples. Separation from the sample matrix is accomplished by successive carbonate, hydroxide and fluoride precipitations. Experimental data is provided.
Date: June 17, 1960
Partner: UNT Libraries Government Documents Department
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Steam Water Pressure Drop and Critical Discharge Flow - A Digital Computer Program

Description: It is the purpose of this report to explain the bands and uses of a digital computer program for the calculation of steady state steam-water pressure drop and critical flow in pipes. The program has been coded for the IBM 709 computer. While so attempt has been made to obtain improved models of two-phase flow, it is believed that the numerical integration technique used in the code will permit more accurate calculation where pressure drops are large compared to the upstream pressure. The techni… more
Date: June 17, 1960
Creator: Massena, W. A.
Partner: UNT Libraries Government Documents Department
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High temperature allotropy and thermal expansion of the rare-earth metals

Description: By means of high temperature X-ray techniques the crystal structure of lanthanum, cerium, praseodymium, neodymium, ytterbium, and possibly gadolinium was found to be body-centered cubic at temperatures near their respective melting points. For ytterbium a hexagonal close-packed structure was also observed, which was shown to be stabilized by atmospheric impurities. Evidence for possible high temperature crystalline transformations in gadolinium, terbium, dysprosium, holmium, and lutetium was ob… more
Date: August 17, 1960
Creator: Spedding, F. H.; Hanak, J. J. & Daane, A. H.
Partner: UNT Libraries Government Documents Department
open access

INERTIAL PRESSURE CALCULATIONS FOR KEWB

Description: Inertial pressure of the KEWB (Reactor Safety Experiments) is calculated assuming that the inertial pressure rise is attributable to fission-nucleated bubbles. (C.J.G.)
Date: August 17, 1960
Creator: Warner, C.
Partner: UNT Libraries Government Documents Department
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