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Design Studies on Cesium-137 as a Source for High Level Gamma Irradiators: Quarterly Progress Report Number 2, September - December 1959

Description: Quarterly progress report describing work related to a study of radiation physics problems involved in the design of high-level cesium-137 gamma sources. It outlines work completed and ongoing goals for the project.
Date: February 29, 1960
Creator: Voyvodic, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Magnetic Recorder for Nuclear Pulse Application : Covering the Period from December 6, 1959 to February 5, 1960

Description: "Abstract: An evaluation of a modulator flux sensitive playback head to be used with an analog magnetic recorder for nuclear pulse information storage was made. The modulator head was found unsultable. A pulse stretching unit was constructed which takes pulses from a standard linear pulse amplifier and provides an output signal suitable for driving a recording head."
Date: February 24, 1960
Creator: Burgwald, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor hazards review zirconium retubing of Hanford reactors

Description: This report examines the pertinent features in the hazards analyses of the Hanford Reactors which may be affected by the substitution of zirconium tubes for the present aluminum process tubes. Resized I & E slugs, designed to preserve present pressure drops across the active zones and to minimize corrosion, are used as examples to compare the characteristics of the zirconium tubes reactor with the present.
Date: February 15, 1960
Creator: Nilson, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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100-K Area electrical power system load and voltage study for project CG-775. Revision

Description: The proposed increased water capacity for 100-K plants will increase the electrical load to be supplied. The load study showed that the capacity of the existing 13.8 kV system is adequate to carry the increased loads proposed for Project CG-775, while for the 5 kV system, an expanded power system is proposed. Likewise, the voltage regulation on the kV system bus will be excessive, and voltage regulators should be added.
Date: February 22, 1960
Creator: Thorson, W. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel element handling before irradiation

Description: This report on fuel element handling presents in some detail the current status of an engineering study which has been underway for some time, and which is continuing. The study was undertaken to determine if it is feasible, and if it is practicable, to revise the method and equipment used for fuel element handling with existing charging machines.
Date: February 1, 1960
Creator: Gilbert, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recommendations to apply the ``square pile`` total control concept

Description: It is recommended that the ``square pile`` concept be adopted for all disaster total control calculations, and that the basic reactor constants listed in HW-62884, except for Ball 3X local strength at the DR Reactor, be used in applying this method. Curves are included for each reactor type, indicating allowable enrichment based on appropriate local control strengths. (The reactors whose operating methods are affected by disaster total control requirements are B, D, F, and DR Reactors; the rema… more
Date: February 25, 1960
Creator: Bowers, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Rear crossheader fitting inspection B, D, and F Reactors

Description: Cavitational flow has been known to exist in-rear crossheader ``Parker`` fittings at B, D, and F Reactors for the last five or six years. Calculations showing initiation of cavitational flow as a result of high flow rates in the present fittings were verified by experimental data in 1954. A study is currently being conducted to determine the required plant modifications to obtain flow increases on the order of fifty percent above existing flows. This study and the results of preliminary tests t… more
Date: February 10, 1960
Creator: Kempf, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production of cobalt-60

Description: Cobalt samples frequently are irradiated in nuclear reactors to produce gamma sources and can be irradiated as integral flux monitors because of the long half-life of the isotope produced. At the present time a small cobalt sample is being irradiated within the KW Reactor Snout facility for future use as a radiographic source for inspection of finished product in the Chemical Processing Department. Analysis was made to estimate the buildup of activity in this sample; the general equation may be… more
Date: February 29, 1960
Creator: Bunch, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Energy release per fission in the Hanford reactors

Description: The average energy release per fission event in a reactor is dependent on the composition and arrangement of the lattice materials. In a study of heat generation in the NPR, Nilson developed expressions for calculating the average energy released in each material per fission event. These relationships have been used in the present calculations to obtain the energy release per fission in existing Hanford reactors.
Date: February 12, 1960
Creator: Morgan, W. C. & Bunch, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Irradiation Processing Department monthly record report, January 1960

Description: This document details activities of the irradiation processing department during the month of January 1960. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: February 19, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Expansion task force: Old reactors speed of control for no overbore cases

Description: The Criteria for Speed of Control must be met for all cases being considered in the Expansion Studies. These Criteria are dependent upon the ratio Volume of water/volume of uranium in the process channel, the reactor power level, and the rate at which the vertical rods are released and inserted into the reactor. For those cases wherein the graphite channel is overbored by 0.200 inch., the criteria can generally be met for the power levels under consideration since the ratio of Vw/Vu is maintain… more
Date: February 22, 1960
Creator: Gilbert, W. D.; Carlson, P. A. & Nechodom, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Circuit Dynamics of the Pinch

Description: The following document aims to analyze the dynamics of a pinch tube, including the reaction back on the energy source.
Date: February 1960
Creator: Killeen, John & Lippmann, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Use of poison splines to reduce non-equilibrium losses, KE Reactor

Description: A significant reduction in non-equilibrium losses is possible through the use of poison splines for reactivity and heat distribution control during reactor startups. The curves presented show the results of an analysis of recent KE Reactor poison spline startup usage. These curves demonstrate the magnitude of gains possible at other reactors through the use of poison splines for turnaround control.
Date: February 5, 1960
Creator: Franklin, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Rezoning of fringe at 105-KE Reactor

Description: A study was made to determine the optimum arrangement of the fringe flow zones at KE Reactor. Also considered, was the possibility of converting part or all of the existing fringe zone (actually three flow zones) from solid metal to I & E metal to decrease rupture potential in these low flow zones. The necessity for this study was indicated by high tube outlet temperatures in the fringe flow zones and the recent occurrence of two solid metal ruptures in process tubes located in the fringe zone … more
Date: February 26, 1960
Creator: Leitz, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Extended hydraulic demand curves for K geometry tubes with I&E fuel elements

Description: Steady state hydraulic demand curves were obtained for tube powers of 500, 1000, 1500 and 2000 KW with an inlet water temperature of 20C and a rear header pressure of 25 psig. These curves are shown in figures. The point of initial unstable flow for various tube powers is shown for a front header pressure of 325 psig. The flow rate that would lead to the initial point of unstable flow as a result of a sudden plug upstream of the Panellit tap is shown in a figure.
Date: February 25, 1960
Creator: Hesson, G. M.; Fitzsimmons, D. E. & Kanninen, M. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effect of increased nickel content in canning baths

Description: Canning bath Al-Si, supplied from offsite vendors and reclaimed lathe turnings in the 313 building, is used in the production of I & E fuel elements. A study was made of the effect of increasing the Ni content to over 0.5% in the canning baths, in order that all of the X-8001 scrap could be reclaimed. Effect on bond quality, weld integrity, and canning bath operation was studied. Based on adverse weld quality, slight loss in reactivity, and potential for furnace channel plugging, it is recommen… more
Date: February 2, 1960
Creator: Strand, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Interim evaluation of nickel plate on aluminum-jacketed fuel elements

Description: Nickel plating on the coolant contacting surfaces of aluminum-jacketed fuel elements is highly attractive for increasing resistance. Potential benefits include a highly corrosion-resistant coating for severe localized conditions, reduction of mechanical damage to fuel element jackets, improved fuel element alignment (by reducing friction between fuel element and process tube ribs) and probably lower overfall surface temperatures to reduction in corrosion product film with improved corrosion res… more
Date: February 8, 1960
Creator: Jacky, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hazards survey 1706-KER Recirculating Test Facility

Description: This report presents the results, conclusions and recommendations of a comprehensive study of the hazards potential of the 1706-KER in-pile recirculation loops, Although more data are needed to verify or refute certain tentative conclusions, the general conclusion of this report is: with the exception of severe coolant loop rupture incidents, especially process tube ruptures, the loops will not possess serious hazards potential when they are operated within the limits specified in the Process S… more
Date: February 4, 1960
Creator: Norwood, K. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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