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Effects of 100-K water plant expansion on Panellits and orifices

Description: The information reported here was requested by M.H. Schack, Facilities Engineering Operation. It pertains to the 100-K water plant expansion Project CG-775. In this project, cooling water pumping capacity will be increased from 178,000 GPM existing to 188,000 GPM and 200,000 GPM for five and six modified pumps respectively. Effects of increased through-put on process tube flow metering elements and on the reactor Panellit gauges have been examined. This information was required to determine cos… more
Date: December 2, 1959
Creator: Stepnewski, D. D.
Partner: UNT Libraries Government Documents Department
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Application of Rare Earths to Ferrous and Non-Ferrous Alloys

Description: The applications for rare earths as mixed metals or their oxides in the steel industry have multiplied rapidly in the past decade and are now providing a variety of alloys with markedly improved properties.
Date: November 2, 1959
Creator: Collins, J. F.; Calkins, V. P. & McGurty, J. A.
Partner: UNT Libraries Government Documents Department
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Decontamination of the KER Rupture Experiment Loop Test Series B - Tests No. 1 and 2

Description: The first series tests in the KER-REP-1 loop proved that a fisssion product contaminated loop could be decontaminated to a safe level for contact maintenance. The second series of tests ere scheduled for a more thorough evaluation of these processes includes specific decontamination factors, process corrosion rates, loop activity reduction factors (loop decontamination factors), and any preferential decontamination which may be present.
Date: November 2, 1959
Creator: Weed, R. D.
Partner: UNT Libraries Government Documents Department
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GEH-4-42, 47; Hot pressed, I and E cooled fuel element irradiation

Description: In our continual effort to improve the present fuel elements which are irradiated in the numerous Hanford reactors, we have made what we believe to be a significant improvement in the hot pressing process for jacketing uranium fuel slugs. We are proposing a large scale evaluation testing program in the Hanford reactors but need the vital and basic information on the operating characteristics of this type slug under known and controlled operating conditions. We, therefore, have prepared two typi… more
Date: November 2, 1959
Creator: Neidner, R.
Partner: UNT Libraries Government Documents Department
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Instrumentation and Controls Division Annual Progress Report, July 1, 1959

Description: Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.
Date: November 2, 1959
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
Partner: UNT Libraries Government Documents Department
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PT-IP-269-A-FP, evaluation of the stability of cores from extruded tubes

Description: If material received under this program is deemed acceptable for reactor charging, this test will authorize irradiation of fourteen monitor columns which shall be discharged at 200, 400 and 800 MWD/T to observe the performance of this material. This test shall run concurrently with irradiation of quantities up to 60 tons/month to be authorized separately.
Date: November 2, 1959
Creator: Hall, R. E.
Partner: UNT Libraries Government Documents Department
open access

A Simple Telephone Telemeter

Description: When following the performance of automatic and semi-automatic equipment that is left unattended for extended periods of time, it is often desirable to be able to check this equipment by remote means. A convenient vehicle for such a check is the telephone since nearly all locations have or can have a telephone extension installed. The check of the equipment may be made as simple or extensive as desired, with the outcome of the check represented by a relay condition, for example. The condition o… more
Date: November 2, 1959
Creator: Ratcliffe, C. A.
Partner: UNT Libraries Government Documents Department
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Power Reactor Fuel Reprocessing: Mechanical Phase

Description: The major events of the Mechanical Phase of the Power Reactor Fuel Reprocessing program during August 1959 are summarized here.
Date: September 2, 1959
Creator: Klima, B. B.
Partner: UNT Libraries Government Documents Department
open access

Rubber Ring Dosimeter Calibrations with the Plutonium Radiation Spectrum

Description: This work was initiated as an evaluation of the application pf rubber finger ring dosimeters to the control of extremity radiation exposure. The use of film dosimeters is a well known general practice throughout the radiation protection profession, however, film radiation exposure measurements associated with plutonium metal handling present a unique problem. The practical measurement of extremity dose depends upon the accuracy and reproducibility of results under the most severe conditions usi… more
Date: September 2, 1959
Creator: Swanberg, F., Jr & Andersen, B. V.
Partner: UNT Libraries Government Documents Department
open access

Specific Gravity of Aluminum Nitrate Solutions

Description: Aluminum nitrate solutions are used as salting agents in the redox process and frequently in organic-aqueous extractions in the laboratory. Determination of specific gravity is a convenient means of estimating the concentration of such solutions. However, where an aluminum nitrate solution has been prepared by dissolving aluminum hydrate in nitric acid, the ratio of nitrate to aluminum may intentionally be other than stoichiometric, the solutions being described as acid, neutral, or acid defic… more
Date: September 2, 1959
Creator: Case, A. H. & Pollock, C. W.
Partner: UNT Libraries Government Documents Department
open access

105-N charge-discharge rates

Description: Figures have and can be generated that indicate a higher charge-discharge rate if required before 105-N will be comparable with existing reactors. Also, these figures show an apparent operating cost incentive to increase the charge-discharge rates proposed for 105-N. Although these figures may be true by themselves, other figures developed from the same information and stated on a basis that affords a true comparison, show that the proposed rates for 105-N are compatible with those in existing … more
Date: July 2, 1959
Creator: Nesbitt, J. F.
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)

Description: Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.
Date: July 2, 1959
Creator: Nakazato, S.; Williams, P. M. & Wilson, W. D.
Partner: UNT Libraries Government Documents Department
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PRTR Single Tube Prototype Mockup (STPM) Operational Characteristics

Description: The Single Tube Prototype Mockup (STPM) was constructed to be used as a tool to evaluate the mechanical problems involved in operating and maintaining many components of the Plutonium Recycle Test Reactor (PRTR). This report has been written to acquaint interested HAPO components with the capability of the STPM and for use as an aid in scheduling tests and/or to properly evaluate testing results obtained from the mockup.
Date: July 2, 1959
Creator: Scott, P. A.
Partner: UNT Libraries Government Documents Department
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Quarterly Report of Non-Production Reactor Fuels Reprocessing Budget Activity 3790

Description: This report summarizes the research and development work carried out during March, April and May, 1959, for Budget Activity 2790 - Separations Development for Non-Production Reactors, The effort on Activity 2790 will enable Hanford to begin reprocessing in January, 1962, the fuel elements from power reactors which employ depleted or slightly enriched uranium fuels.
Date: July 2, 1959
Creator: Cooper, V. R.
Partner: UNT Libraries Government Documents Department
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Run 300A-B Slurry Run of 300A Pump and Loop

Description: The 300A and loop were operated for 2862 hr with thorium oxide slurry at 1500 psi and 280ºC to determine the effects vane inlet and exit geometries on impeller wear, the wear rate of aluminum oxide bearings in this size pump, and the operating characteristics of the loop. The thoris, a 1600*C-fired oxide, had a mean particle size of approximately 2 u. Average circulating slurry concentration was approximately 450 grams of thorium per kilogram of water and average flow rate was approximately 300… more
Date: July 2, 1959
Creator: Moyers, J. C.
Partner: UNT Libraries Government Documents Department
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Some Research on the Lift and Stability of Wing-Body Combinations

Description: The present paper summarizes and correlates broadly some of the research results applicable to fin-stabilized ammunition. The discussion and correlation are intended to be comprehensive, rather than detailed, in order to show general trends over the Mach number range up to 7.0. Some discussion of wings, bodies, and wing-body interference is presented, and a list of 179 papers containing further information is included. The present paper is intended to serve more as a bibliography and source of … more
Date: July 2, 1959
Creator: Purser, Paul E. & Fields, E. M.
Partner: UNT Libraries Government Documents Department
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Supplement No. 1. Projections of Costs, 1959-1975 for Nuclear-Conventional Power Plant Cost Study. Conventional Coal Fired Power Plants : 25,000 KW to 325,000 KW for Argonne National Laboratory, Lemont, Illinois

Description: In order to establish a basis for comparing the estimated cost of nuclear power plant designs, a set of general and detailed design considerations for conventional coal-fired power plants was established. Five preliminary designs of conventional coal-fired power plants ranging in size from 25to 325 mw were selected, and cost estimates were prepared. Supplement 1 shows a year by year projection of costs for the period 1959-1975.
Date: July 2, 1959
Creator: Chittenden, W. A.
Partner: UNT Libraries Government Documents Department
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Xenon calculations for I and E fuel element

Description: This document describes in detail the calculations that are basic to the xenon problem. While much of this work appears elsewhere, herein an attempt has been made to bring it together and make it as understandable as possible. The principle purpose of this document is to calculate the equilibrium xenon poisoning for the I and E geometry fuel element and compare the results to the equilibrium xenon poisoning for the solid geometry fuel element. Further objectives are to provide an understandable… more
Date: July 2, 1959
Creator: Chitwood, R. A.
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Cost for Aqueous Homogeneous Reactors

Description: By using a large central fuel and blanket reprocessing facility, slurry-fueled aqueous homogeneous reactors can attain an estimated minimum fuel cycle cost of 1.4-1.6 mills/kwh; with solution-fueled two-region reactors, a doubling time of 14 years may be obtained at a fuel cycle cost of 2.0 mills/kwh. On-site processing appears desirable only for large power stations made up of reactors designed for short doubling times. For instance, a solution-fueled two-region reactor can attain a 12-year do… more
Date: June 2, 1959
Creator: Culler, F. L.
Partner: UNT Libraries Government Documents Department
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ORIC R-F Model III Progress Report

Description: The ORIC (Oak Ridge Relativistic Isochronous Cyclotron) radiofrequency system for which Model III represents the resonator is the third system which has received enough consideration to warrant construction of a model. The purpose of the model is to check the calculations for the frequency range and excitation power of the resonator. After an introductory description of the r-f system and model, the detailed calculations of the properties of the model will be given followed by the data from me… more
Date: June 2, 1959
Creator: Worsham, R. E. & Mosko, S. W.
Partner: UNT Libraries Government Documents Department
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Spectrophotometric Determination of Microgram Quantities of Osmium With Diphenylcarbazide by G. Goldstein

Description: A method was developed for the spectrophotometric determination of 30 to 100 ug of osmium as OSO4 is extracted with CHCl3 and diphenylcarbazide is then added to the organic extract. A blue-violet reaction product is formed, the absorbancy of which is measured at 560 mu. A suitable reagent concentration is from 3 to 5 ml of 0.2% diphenylcarbazide in a volume of 25 ml and the preferred solvent for the reagent is ethanol. Beer's law is followed over a range of 8 to 130 ug of osmium with a coeffic… more
Date: June 2, 1959
Creator: Menis, Oscar
Partner: UNT Libraries Government Documents Department
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Status Report- Application of Electroless-Nickel Brazing to Tabular Fuel Elements for the N. S. Savannah

Description: The feasibility of using electroless nickel, a chemical deposit containing about 10 wt% phosphorous in nickel, as the brazing alloy for assembling tubular stainless steel fuel elements of the type specified in Core I of the N. S. Savannah was investigated. This material was nelected primarily because of the case of braze-metal preplacement by chemical deposition of the alloy on type 304 stainless steel ferrule spacers, prior to fuel-bundle assembly. Brazed joints produced by this method were ge… more
Date: June 2, 1959
Creator: Lamartine, J. T. & Thurber, W. C.
Partner: UNT Libraries Government Documents Department
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Exploration of Radiometric Methods

Description: The compilation of possible analyses in aqueous solution is nearly complete. A chart has been constructed showing the elements which may be determined radiometrically. The radiometric general scheme of analysis has been roughly blocked out. The next-planned phase is to select specific reagents and determine the details of such analysis.
Date: April 2, 1959
Creator: Driscoll, William J. & Scott, Benjamin F.
Partner: UNT Libraries Government Documents Department
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