Search Results

open access

Amine Extraction of Plutonium From Nitric Acid Solutions Loading and Stripping Experiments

Description: Information is presented on a suitable amine processing system for plutonium nitrate. Experiments with concentrated plutonium nitrate solutions show that trilaurylamine (TLA) - xylene solvent systems did not form a second organic phase. Experiments are also reported with tri-noctylamine (TnOA)-xylene and TLA-Amsco - octyl alcohol. Two organic phases appear in both these systems at high plutonium nitrate concentrations. Data are tabulated from loading and stripping experiments. (J.R.D.)
Date: January 19, 1961
Creator: Wilson, A. S.
Partner: UNT Libraries Government Documents Department
open access

VARIATIONS IN THE URANIUM-235 CONTENT OF FIFTEEN ORES

Description: The uranium isotope compositions of samples from l5 ores were compared to a standard. Variations of about O.l% of the U/sup 235/ content were observed. (auth)
Date: January 19, 1961
Creator: Smith, L.A.
Partner: UNT Libraries Government Documents Department
open access

40-tube overbore facility location, C Reactor

Description: Possible locations of the projected 40-tube overbore facility at the C Reactor are discussed from the standpoint of obtaining conversion ratio data applicable to a full-reactor overbore program.
Date: April 19, 1961
Creator: Nilson, R.: Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
open access

The Attenuation of Natural Environmental Radiation by an Automobile

Description: Report presenting a large number of measurements of natural environmental radiation in various parts of the United States using a 20-liter air filled polyethylene-walled ionization chamber at atmospheric pressure. The ionization current was measured with a vibrating reed electrometer connected as a continuously reading voltmeter driving a pen recorder" (p. 1).
Date: April 19, 1961
Creator: Shambon, Arthur; Lowder, Wayne M. & Solon, Leonard R.
Partner: UNT Libraries Government Documents Department
open access

Hazards Report for the SM-1 Core II Without Special Components

Description: Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II without special components. The SM-1 Core II components were made to specifications very nearly identical to those of SM-1 Core I. The differences consist of europium absorber sections, internal europium flux suppressors in the control rod fuel elements, and low impurity cladding. Each of the SM-1 Core II components with the exception of the five absorber sections new in SM-1 Core I were subjected to a Zero Power Experiment at the Alco Critical Facility. The results of this experiment indicate that the SM-1 Core II will have nuclear characteristics very similar to that of the SM-1 Core I. Since SM-1 Core II will be operated with the same mode of rod control, in the same core support structure, and with the same primary coolant flow conditions, the thermal characteristics should be essentially identical to that of SM-1 Core I. Also, all kinetic characteristics of SM-1 Core II should be identical to those of SM-1 Core I. This report demonstrates that there is no increase in potential for a hazardous situation at SM-1 due to the replacement of SM-1 Core I by SM-1 Core II.
Date: April 19, 1961
Creator: Gallagher, J. G.
Partner: UNT Libraries Government Documents Department
open access

Processing data for NIE and NIN KER Loop charges (PT 377)

Description: The following data represents processing conditions used in fabricating prototypic (except for supports) natural and enriched NPR inner fuel elements for Production Test 377. The prototypic NPR inner fuel elements were inserted into zircaloy-sleeves prior to charging. In this way it was possible to simulate, in the KER loops, the conditions under which NPR fuel elements would be subjected under irradiation. The purpose in documenting the data is to provide a permanent record of processing conditions and dimensions which may be referred to for post irradiation analysis and possible future process development work. Post irradiation results will be issued by the Fuels Development Operation, Hanford Laboratories Operation, and the test loop operating conditions will be issued by Process and Reactor Development Operation, Irradiation Processing Department, as outlined in the Production Test Procedure.
Date: April 19, 1961
Creator: Kusler, L. E. & Hays, D. D.
Partner: UNT Libraries Government Documents Department
open access

Analysis of the stored energy distribution in D-reactor

Description: The purpose of this document is to characterize, as completely as possible, the stored energy distribution in D Reactor as of March 1958, the date of the last stored energy survey and to estimate the temperature rises which can be expected to occur during a stored energy release. D Reactor was chosen for this study only because it represents one of the oldest operating Hanford reactors and not because of any circumstances peculiar to this reactor. 14 refs., 13 figs.
Date: May 19, 1961
Creator: Morgan, W. C.
Partner: UNT Libraries Government Documents Department
open access

CORE REMOVAL COOLING SYSTEM-SECTION II. CORE I, SEED I. Test Results T- 641113. Section 2

Description: A test was performed on June 19, 1959 to determine the capacity of the Core Removal Cooling System for removing reactor decay heat under split-flow'' conditions. The system operated satisfactorily during this test; the pumps developed a flow of approximates 73 gpm at a total head of 254 ft water, as compared with their rated capacity of 75 gpm at a total head of 250 ft water. (D.L.C.)
Date: May 19, 1961
Partner: UNT Libraries Government Documents Department
open access

Research and Development Studies on Waste Storage Process

Description: The basic objectives of this program were the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide. To accomplish these objectives, a literature survey was flrst made of available physical and chemical data for the oxides and nitrates of Cs, Sr, Ru, Zr, Nb, and Ce. The data were supplemented by a calculation of thermodynamic functions for RuO/sub 4/ vapor from the experimentally determined infrared spectrum and the theoretically calculated raman-active fundamentals. Data are presented graphically. (C.H.)
Date: May 19, 1961
Creator: Ortner, M. H.; Anderson, C. J. & Campbell, P. F.
Partner: UNT Libraries Government Documents Department
open access

Research and Development Studies on Waste Storage Process

Description: Report documenting "the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide" (p. 4).
Date: May 19, 1961
Creator: Ortner, M. H.; Anderson, C. J. & Campbell, P. F.
Partner: UNT Libraries Government Documents Department
open access

Safety review of Nuclear Fuel Manufacturing Operations: Fuels Preparation Department

Description: Subsequent to a recent comprehensive review of the safety of Hanford`s reactor operations, a request was received from the Hanford Operations Office for a similar review of manufacturing processes within the 200 and 300 areas. Of particular concern were the non-reactor-oriented nuclear and radiological hazards involved in these operations, as well as the administrative procedures by which they were controlled. This report, which reviews these elements of safety of operations within the Fuels Preparation Department was accordingly prepared. Many individuals throughout the Department and Hanford Laboratories Operation contributed to this study.
Date: May 19, 1961
Creator: Worlton, D. C.
Partner: UNT Libraries Government Documents Department
open access

SOME PROPERTIES OF BERYLLIUM OXIDE

Description: S>The primary objective of the literature search was to determine the best values for the properties involved in the thermal stress parameter. Comparison of data from various investigators indicates that thermal expansion of beryllia is independent of density. A wide variation was found in the thermal conductivity values of beryllia. Graphs and tables are presented which summarize and compare data from various sources. A bibliography of 53 references for some of the major items of the stress parameter (thermal expansion, thermal conductivity, and modulus of elasticity) as well as for general properties of beryllia is given to books, journals, and reports published from 1914 to 1960. (auth)
Date: May 19, 1961
Creator: Lillie, J.
Partner: UNT Libraries Government Documents Department
open access

Thermal Expansion of Technical Solids at Low Temperatures: A Compilation From the Literature

Description: Report giving tables of the linear contraction relative to 293 ºK, (L293ºLT)/L293, and the linear expansion coefficient, dL/L293dT, of thirty elements, forty-five alloys, twenty-two other inorganic substances and twenty plastics and elastomers in the temperature range, 0 to 300 ºK.
Date: May 19, 1961
Creator: Corruccini, Robert J. & Gniewek, John J.
Partner: UNT Libraries Government Documents Department
open access

Thermal Stability of Gadolinum Nitrate Solution at High Temperature

Description: During a feasibility study of auxiliary shutdown systems for the Spert II and Spert III reactor facilities, salts possessing high neutron absorption cross sections were considered for use in water soluble poison injection systems, and gadolinium nitrate appeared promising. Tests were carried out in a high pressure static autoclave to determine the stability of gadolinium nitrate solution at elevated temperature. At temperatures of 300 deg F and above, the solution decomposed with formation of a white precipitate. It was concluded that gadolinium nitrate is unsuitable for use as a soluble poison in high temperature, watermoderated reactor systems. (auth)
Date: May 19, 1961
Creator: Koenig, J. F.
Partner: UNT Libraries Government Documents Department
open access

CORROSION ASSOCIATED WITH FLUORINATION IN THE OAK RIDGE NATIONAL LABORATORY FLUORIDE VOLATILITY PROCESS

Description: : : 9 7 7 8 6 9 : = 7 9 9used during the fluorination of fused-salt fuels and subsequent associated operations in the Oak Ridge National Laboratory (ORNL) Fluoride Volatility Process was evaluated. Corrosive attack is reported as mils per month based on molten salt residence time or mils per hour based on fluorine exposure time. Two fluorinators were used in the VPP to carry out the fluorination reactions. These vessels, Mark I and Mark II, were fabricated into right cylinders, approx 4 1/2 ft in height, from the same heat of L (low carbon nickel. The first vessel contained equimolar NaF- ZrF/sub 4/ or NaF-ZrF/sub 4/-UF/sub 4/ (48-48-4 mole%) for approx 1250 hr at 600 to 725 deg C. Over a period of 61 hr, 57,500 standard liters of F/sub 2/ were sparged into the slats. This constituted a F/sub 2/:U mole ratio of 3:1 beyond theoretical requirements. The Mark II fluorinator contained fluoride salts of approxi-mately the same compositions plus small additions of PuF/sub 4/ during three runs. The salts were kept molten at 540 to 730 deg C for approx 1950 hr and about sixty 500 standard liters of F/sub 2/ were sparged into the Mark II melts in 92 hr. Both fluorinators sustained large corrosion losses consisting of extensive wall thinning, severe interior inter- granular attack, and a moderate exterior oxidation attack. Maximum deterioration on the Mark I vessel occurred in the middle vapor region at a calculated rate of 1.2 mils/hr, based on fluorine sparge time, or 46 mils/month, based on time of exposure to molten salts. The second vessel showed maximum attack in the salt-containing region at similarly calculated rates of 1.1 mils/hr and 60 mils/month. Some evidence was found to indicate that the intergranular attack may have resulted from sulfur in …
Date: June 19, 1961
Creator: Litman, A.P. & Goldman, A.E.
Partner: UNT Libraries Government Documents Department
open access

HFIR HEAT-TRANSFER STUDIES OF TURBULENT WATER FLOW IN THIN RECTANGULAR CHANNELS

Description: In support of the High Flux Isotope Reactor program, experimental determinations were made of friction factors, burnout heat fluxes, and average and local nonboiling heattransfer coefficients for forced-convection flow of water through this aluminum and nickel rectangular channels under the following conditions: heat flux = 0.1 x 10/sup 6/ to 7.4 x 10/sup 6/ Btu/hr - ft/sup 2/, velocity = 10 to 85 fps, Reynolds number = 9,000 to 270,000, pressure = 1 to 39 atmospheres absolute, flow gap = 0.043 to 0.057 in., and heated length = 12 and 18 in. A few tests were made to ascertain the effect of an axially oriented cylindrical spacer strip on surface temperature distribution and burnout heat flux. The results of these studies, are in reasonably good agreement with accepted ccrrelations. The friction factors are in satisfactory agreement with the Moody chart for the relative roughness of the test sections used, the burnout heat fluxes are well reproduced by the Soviet Zenkevich-Subbotin correlation, and the local and average heat-transfer coefficients are slightly larger than values predicted by the Hausen and Sieder-Tate equations. Miscellaneous experimental and analytical HFIR heat-transfer studies are included. (auth)
Date: June 19, 1961
Creator: Gambill, W.R. & Bundy, R.D.
Partner: UNT Libraries Government Documents Department
open access

AN INVESTIGATION OF SOME OF THE CAUSES FOR THE SPALLING OF IMPREGNATED GRAPHITE

Description: The impregnation process of the graphite used for investigations of spalling is described. Polished graphite specimens were examined at room temperature using bright field metallographic techniques. The gas evolution characteristics of impregnated graphite were also determined. Results indicated that the amount of impregnant introduced during the fourth impregnation cycle could be a critical factor in causing spalls in the manufacturing process. The permeability of the impregnated graphite was found to increase with the temperature to which the impregnated graphite was heated. Studies showed that the most significant changes in the impregnant and in the gas evolution occurred in the temperature range of 100 to 600 deg C. These results suggested that a slower heating rate during carbonization is likely to reduce spalling. A tentative mechanism for spalling is offered. (M.C.G.)
Date: June 19, 1961
Creator: Kosiba, W.L.; Tully, G.R. Jr. & Turovlin, B.
Partner: UNT Libraries Government Documents Department
open access

Production test-IP-409-A-FP pilot test of self-supported fuel elements in K size smooth-bore zirconium process tubes

Description: This test authorizes installation of up to ten non-overbore size zirconium smooth-bore process tubes into KW Reactor and continued charging of these tubes with KVNS fuel elements until authorized by other means (Process Standards or PITA) or until this test is terminated. While the test authorizes up to 10 tubes, only two process tubes are immediately available and are all that will be planned for in the initial installation and charging. Goal exposure will be set at 800 MWD/T.
Date: June 19, 1961
Creator: Clinton, M. A. & Curtiss, D. H.
Partner: UNT Libraries Government Documents Department
open access

Reduction of the amount of dichromate added to reactor cooling water: Interim report, Production Test-IP-321-A

Description: Reduced process water treatment costs and incidental benefits of smaller hexavalent chromium discharge to the Columbia River provided incentives to conduct a half-reactor production test. The sodium dichromate (Na{sub 2} Cr{sub 2} O{sub 7}2H{sub 2}O) concentration in process water supplied to the far side of 105-C was lowered from a nominal value of 1.8 to 1.0 parts per million (ppM). This test was started September 26, 1960 and is still in progress. However, a sufficient amount of data is available now to permit an interim evaluation of the corrosion effects noted as a result of the change inhibitor concentration.
Date: June 19, 1961
Creator: Nesselson, E. J.
Partner: UNT Libraries Government Documents Department
open access

CHARACTERIZATION OF UO$sup 2$ POWDERS. Progress Report No. 8, May and June 1961

Description: Correlation of a number of physical and chemical properties of 12 different UO/sub 2/ powders was continued. The UO/sub 2/ powders were studied by means of infrared absorption measurements, oxidation temperatures as determined by hot stage microscopy techniques, and B. E. T. surface area measurements. Additional pellets were prepared to study ceramic performance. (M.C.G.)
Date: July 19, 1961
Creator: Carpenter, J.F.
Partner: UNT Libraries Government Documents Department
open access

DETERMINATION OF LIFE-TIME OF THE B$sub 4$C-IN-TUBES CONTROL ROD

Description: The lifetime of a B/sub 4/C-in-tubes'' control rod may be limited by either nuclear worth depreciation or internal gas pressure buildup as helium is formed and released from the B/sub 4/C particles. Nuclear life is enhanced by thin tube walls for any given O.D. of tubing and by high B/sub 4/C density, but the time to failure from gas pressure buildup is increased by the opposite. The optimum B/sub 4/C density and tube wall thickness were calculated for maximum control rod life, using several release fractions of generated helium and a number of allowable cladding stress values. It was estimated that lifetimes of l0 or more years for B/sub 4/C-in-tubes control systems are achievable through the proper selection of tubing material and B/sub 4/C density values. The B/sub 4/C densities required for maximum lifetimes are in a range that can be obtained by vibratory compaction followed by swaging. (auth)
Date: July 19, 1961
Creator: Megerth, F.H.
Partner: UNT Libraries Government Documents Department
open access

INLINE DENSIMETER FOR PULSED COLUMN LIQUID DENSITY, PULSE AMPLITUDE, AND PULSE FREQUENCY MEASUREMENTS

Description: S>An inline densimeter was fabricated and tested in the laboratory. When operated in a range of 1.000 to 1.200 g/cc, an accuracy of plus or minus 0.2% in the mid-point of the range was easily achieved. The instrument also measures pulse amplitude and pulse frequency when used on a pulsating flow. A long life with high reliability is expected because of the simple all-welded construction and highly reliable electronic system. (auth)
Date: July 19, 1961
Creator: Mackey, T.S.
Partner: UNT Libraries Government Documents Department
open access

Photon Wavelength and Energy Conversion Tables

Description: Tables are presented for conversions from photon vacuum wavelength to photon energy and vice versa. The ranges covered are 500 to 12,000 angstroms and 1.000 to 26 electron volts. (D.L.C.)
Date: July 19, 1961
Creator: Butler, C. T. & Robinson, M. T.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen