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General Flattening and Power Curves

Description: Introduction: "In the evaluation of pile designs it is necessary to know how the production varies with the number of tubes. It has been possible to solve the problem in terms of some general parameters whose values may be quickly computed for any specific design when the pertinent information is available."
Date: March 30, 1953
Creator: Gast, Paul F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design Notes and Component Recommendations for Gamma-Scintillation Monitoring Systems

Description: The design notes contained herein may assist in preliminary studies concerning feasibility of any proposed gamma monitor system. The minimum and maximum solution concentrations for each type of system are listed. The data is based on 32 ml liquid sample.
Date: September 2, 1955
Creator: Connally, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development, Research and Development Programs Quarterly Progress Report: April - June 1964

Description: The programs sponsored by the Division of Reactor Development at Hanford include studies on basic properties of fuel materials and fabrication methods, physics, chemical processing of reactor fuels and radioactive waste, material development, irradiation effects on materials, fuel cycle analysis and advanced concepts, instrumentation, and nondestructive testing techniques. The results of these programs are broadly applicable to the Civilian Application Program.
Date: November 1964
Creator: Pacific Northwest Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgical Examination of K-Loop Fuel Elements Resulting from Rupture Incident

Description: The first and third slugs downstream from the H-Loop ruptured and a piece of can wall from the ruptured slug were received from Pile Materials Sub-Section for metallurgical examination. The examination has been completed and the extent and type off aluminum corrosion which occurred on these samples has been determined.
Date: August 13, 1956
Creator: Mallett, G. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radioactivity Levels of the Columbia River Below Richland, Washington for the Period January, February, March 1956

Description: In the Columbia River downstream from Richland, Washington there is a gradual decrease in the concentration of radioactive isotopes. At any one location there are fluctuations due to factors such as ditution and decay time. During this period at all locations the concentration of alpha particle emitters in water averaged below the detection limit of 3 x 10⁻⁹ μ c/gm. Beta particle emitters in water upstream of McNary Dam increased by a factor of 1.5 to 2, with averages at various locations rangi… more
Date: unknown
Creator: Clukey, H. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Elastic Solution for the Thermal Stresses in a Finite Solid Cylinder Fuel Element

Description: The heat generated by reactor fuel elements create thermal gradiants which cause thermal stresses of considerable magnitude. An elastic solution for these thermal stresses can be calculated with the equations given in Timoshenko's and Goodier's book (1) on elasticity if the fuel element is assumed infinite in length. An exact elastic solution for a finite cylindrical fuel element is given in this report in order to evaluate the effects of fuel element length on the thermal stresses and the effe… more
Date: October 12, 1956
Creator: Cadwell, J. J. & Merckx, K. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Summary of the History of Hanford Redox Plant Solvent

Description: The Redox solvent extraction process for the separation of uranium and plutonium from their fission products and from each other has operated on an over-all basis very successfully for more than four and one-half years. During this time, there have been occasional periods of high product losses and/or poor separation of fission products from uranium or plutonium as well as periods of poor operability due, among other things, to emulsification and entrainment. The search for the cause of these v… more
Date: October 4, 1956
Creator: {{{name}}}
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Design and Application of A Heat Transfer Analogue for Radially Symmetrical Problems

Description: This report describes the design, construction, and application of an electrical analogue for solution of the steady state problem. Teledeltos paper (an electrically conductive paper) was used to construct this analogue, and although this and other sheet materials has been used for heat transfer analogues in several previous investigations, it is believed that the present work is unique in the application of Teledeltos paper to three dimensional problems of radial symmetry.
Date: January 30, 1957
Creator: Cook, M. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRPR Control Requirements. Part I.

Description: The following remarks are intended primarily to assist in the orientation of the PRP reactor control development program in a direction consistent with the basic objectives of the program as a whole, and to discuss certain aspects of particular control systems which have a bearing on the capabilities of the reactor with respect to these objectives.
Date: November 14, 1956
Creator: Triplett, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Note on Power Recovery From Warm Water

Description: Several studies of power recovery from Hanford pile effluents have been made, from which the conclusion can be drawn that, while recovery of power is feasible, it is costly because of the large volume of vapor which must be handled per kilowatt-hour of energy provided. This note is to call attention to the possibility of developing cheaper machinery than the conventional low-pressure turbine stages considered in previous studies through use of a water expansion cycle.
Date: November 15, 1956
Creator: Wood, E. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Peerless Magnetic Drive Process Pump

Description: The desirability of employing leakproof process pumps for handling the corrosive and radioactive process solutions in the H.A.P.O. separations plants has led to the establishment of a program for the development and testing of packless pumps with particular emphasis on evaluation of commercially available units. One such pump, its operating characteristics and behavior, are described in this report.
Date: November 19, 1956
Creator: Dunn, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion of Stainless Steel, Titanium, and Tantalum in Plutonium - Nitric Acid Solutions

Description: The letter E. R. Irish/W. H. Swift to R.E. Burns and H. H. Hopkins, dated August 15, 1956, subject Plutonium Concentration Problems, requested information on corrosion of stainless steel, titanium, and tantalum in plutonium nitrate-nitric acid solution, with and without sulfate ion. Experimental conditions and results of tests designed to yield the requested information are given below.
Date: November 27, 1956
Creator: Brunstad, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Centrifugal Casting for Plutonium and Plutonium-Uranium Plates

Description: The objective of this investigation was to determine the feasibility of centrifugal casting to produce fuel element plates suitable for use in a power reactor. Preliminary investigations involving the centrifugal casting of metal plates suitable for use in a power reactor proved to be successful. Lead plates cast at medium speeds contained very few voids and exhibited a surface which conformed very closely to that of the mold.
Date: November 28, 1956
Creator: Quinlan, F. B. & Tverberg, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Use of Experimental Water Filter Plant

Description: An improved method of water plant control has been developed at Hanford which employs a sensitive turbidiy measuring microphorometer and a model water filtration plant. The microphotometer operates on a light scattering principle and is accurate in the range of 0.0 to 0.1 parts per million turbidity. The model filter plant used is a five gallon per minute plant which can simulate the conditions normally occurring in the large water plants. It is the purpose of this report to describe the model … more
Date: August 20, 1956
Creator: Conley, W.R.; Botsford, C. W. & Pitman, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mechanical Features of a Continuous Ion Exchange Unit

Description: This review covers: (a) The continuous countercurrent ion exchangers which have been described in the patent and/or technical literature. (b) Some of the other moving bed processes which are similar in mechanical arrangement to a continuous countercurrent ion exchange and which might have certain features adaptable to an ion exchange unit. (c) The auxiliary mechanical devices which are or may be used in an ion exchange apparatus.
Date: August 7, 1956
Creator: Lauer, B. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Demonstration of D₂O Moderated Demonatration Reactor

Description: The objective of this report is to analyze the basic engineering problems involved in the design of a pressurized demonatration reactor to be moderated and cooled with heavy water. Two fundamental concepts of this reactor, here referred to as the HWER, are as follows: (1) a tank-type reactor, in which the moderator pressure is maintained at or near atmospheric conditions, and (2) a pressurized vessel-type reactor in which the moderator pressure is maintained at 1000 to 1300 psi. The fuel and pr… more
Date: September 13, 1956
Creator: Davis, Harold S.; Marinos, D. & Newell, Glen A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Alternating Current and Square-Wave Polarography

Description: A exploratory study was made of a polarographic technique in which an alternating sine or square-wave potential is superimposed upon the applied d.c. potential of the polarographic scan. Recording of the a.c. component of the polarographic current results in derivative-type waves. It was shown that the technique yields greater sensitivity and greater selectivity than normal polarographic technique.
Date: September 11, 1956
Creator: Hamm, Randall E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Graphite Diffusion Length Measurements at Hanford

Description: A series of diffusion length measurements were carried out on graphite stacks of various constructions in an attempt to resolve the discrepancies between the graphite diffusion lengths measured in the Hanford reactors and that value measured in the Hanford Standard Pile. It was found that the diffusion length of the graphite in the Hanford reactors is in good agreement with the value for the Hanford Standard Pile when corrections are made for the absorption and scattering of neutrons by the alu… more
Date: September 10, 1956
Creator: Richey, C. R. & Block, E.Z.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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