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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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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 obtained by means of electrical resistance measurements; erbium gave no such evidence. X-ray data were used to derive empirical equations which describe thermal expansions coefficients of scandium, yttrium and the rare-earth metals. Europium exhibits a rapidly decreasing coefficient of expansion with increasing temperature, which may be a consequence of a gradual promotion of one of the 4f electrons into the conduction band. The hexagonal rare-earth metals were found to have nearly the same axial ratio at their respective transformation temperatures.
Date: August 17, 1960
Creator: Spedding, F. H.; Hanak, J. J. & Daane, A. H.
Partner: UNT Libraries Government Documents Department
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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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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 loss data for various outlet fitting assemblies for possible use on the BDF type reactors The experimental data for this study were obtained with the use of the hydraulics mockup in the 189-D Thermal Hydraulics Laboratory.
Date: February 17, 1960
Creator: Findlay, J. A.
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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Measurements of Dissolved Hydrogen Concentration. Core I, Seed 1. Test Results T-612395-A

Description: Measurements were undertaken to compare the performance of a hydrogen- palladium diffusion coil to a palladium resistance wire assembly in measuring hydrogen concentration and to obtain data to evaluate a Swartout Palladium Resistance Gage electronic readout unit. No comparison could be made since the instruments were never in satisfactory service at the same time. The data taken with each instrument are compared with data determined by laboratory analysis. A review of the data indicated that the units were unreliable. (B.O.G.)
Date: October 17, 1960
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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Periodic Radiation Survey of Reactor Plant Container and Components After Shutdown "F" Survey. Core I, Seed 1. Test Results (T-612076). Section 4

Description: An investigation was conducted to obtain measurements of radiation levels inside the hemispherical heads of the 1-B heat exchanger. The radiation levels were measured at the handholes on two occasions with an interval of 640 hrs between them. A very large increase was noted and could be explained only by the possibility that the measurement survey points were not identical. (J.R.D.)
Date: October 17, 1960
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey of Reactor Plant Container and Components After Shutdown, "I" Survey. Core 1, Seed 1. Section 2. Test Results T-612076

Description: The radiation level and its decay were measured at expected hot-spots in the reactor container, 1AC and 1BD boiler containers, and pressurizer cubicle after plant shutdown for refueling. Initial measurements indicated rela tively high radiation levels in certain areas. Maximum initial readings were 500 mr/hr, 400 mr/hr, 530 mr/hr, and 195 mr/hr in the reactor container, 1AC boiler container, 1BD boiler container, and purification cubicle, respectively. (W.L.H.)
Date: October 17, 1960
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/ epithermal neutrons per square centimeter per second. To accommodate the experimental samples, the reactor fuel core is four feet long in the direction of experimental loops. The vertical arrangement of reactor and experiments permits the use of straight and vertical loops penetrating the top cap of the reactor vessel. The design offers a high degree of accessibility of the exterior portions of the experiments and offers very convenient handling and discharge of experiments. Since the loops are to be integrated into the reactor design and the in-pile portions installed before reactor startup, it is felt that many of the problems encountered in MTR and ETR experience will cease to exist. Installation of the loops prior to startup will have an added advantage in that the flux variations experienced in experiments in ETR every time a new loop is installed will be absent. ETR II (formerly called ETR IV) has a core configuration which provides essentially nine flux-trap regions in a geometry which is almost optimum for cylindrical experiments. The geometry is similar to that of a four-leaf clover with one flux trap in each leaf, one at the intersection of the leaves, and one between each pair of leaves. The nominal power level is 250 Mw. The study was carried out in enough detail to permit the establishment of the design parameters …
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: 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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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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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 successive treatment of solid residues with caustic and nitric acid. Removal of nitric acid from uranium-molybdenum alloy dissolver solutions by boil-down procedures and by reaction with formaldehyde is discussed. Solutions obtained after removal of nitric acid constitute satisfactory low-acid Redox process feedstocks. (auth)
Date: March 17, 1960
Creator: Schulz, W. W.
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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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-trapping, and gettering with active metals were investigated as possible purification methods to reduce the N and O content of Li. Of the techniques studied, gettering with active metals was found to be the most effective method of reducing the N concentration, while cold-trapping and low-temperature filtration were most effective in reducing the O concentration. (auth)
Date: March 17, 1960
Creator: Hoffman, E. E.
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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