Technical Report Archive & Image Library (TRAIL) - 132 Matching Results

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100-N Decontamination Facility Design Guide.

Description: Space has been reserved near the southeast corner of the 100-N Area for the 122-N Decontamination Facility. Previous correspondence between Burns and Roe, Inc and General Electric bae discussed various facilities which might be needed in the building. The concepts of the decontamination processes are under active development by research groups at Hanford. At present, there are several workable processes known; each one has one or more fairly serious drawbacks.
Date: March 8, 1960
Creator: Bainard, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aluminum Alloy Work at Hanford

Description: Investigation of aqueous and steam corrosion at elevated temperature has been carried on at Hanford for several tears. A number of reports have been published on various phases of the corrosion program but, except for monthly reports, little has been written on the progress of the Corrosion and Coatings Operation alloy development program. This interim report will outline the more important current phases of the aluminum alloy program.
Date: May 6, 1960
Creator: Bowen, H. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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APDAC-I, A PCTR Data Analysis Code for the IBM 709

Description: A flexible foil data processing program is described. Raw data on foil radioactivity are the basic input information required. Output may consists of relative activities, saturated activities, and/or cadmium ratio and flux spectrum data. A statistical analysis of the data is executed with the direct calculation, and errors estimated for the output data.
Date: September 7, 1960
Creator: Lilley, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Blast Cleaning Process as an Aid to Visual Weld Inspection

Description: Late in 1958 it became apparent that some fuel elements were failing in the Hanford reactors as a result of water entering through the weld. The mode of entry appeared to be first through a void in the weld, then through a non-wet area or a train of voids in the braze, and finally to the uranium core. Defective closures of a similar nature were also typical of many fuel elements which have failed in the autoclaving operation as shown in Figure 1.
Date: March 9, 1960
Creator: Hanson, G. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Classification of PuO2 Particles

Description: The Biology Operation, Hanford Laboratories, required plutonium dioxide particles in five different micron and sub-micron size ranges. These were to be supplied as a water suspension in small containers. It was necessary to design equipment, suitable for hood operation, which would give a satisfactory separation of these particles.
Date: January 6, 1960
Creator: Burnham, J. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Coagulant Aids as Filter Aids

Description: The Hanford water treatment plants were operated for a number of years with alum as a coagulant and activated silica as a coagulant and a polyacrylamide as a filter conditioning agent. (other polyelectrolytes may be used.) Sufficient time has elapsed to make a comparison of the two methods of operation valid and useful. Such a comparison is the purpose of this paper.
Date: July 21, 1960
Creator: Conley, W. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Completion Report An Automatic Fuel Element Stamping Machine

Description: This document will be concerned with the design, operation and maintenance of an automatic fuel element stamping machine. In order to take advantage of automatic unloading and length checking at the Acme-Gridley lathes in the 313 Building, automatic stamping of fuel elements is desirable. This, along with the need for a permanent canning line identification, resulted in a request for a machine to automatically stamp HAPO fuel elements on a production basis.
Date: January 12, 1960
Creator: Allen, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Construction Completion Report: CAI-816, 100-N Reactor Plant

Description: Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.
Date: October 15, 1964
Creator: Buckner, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Contraction Losses and High Temperature Pressure Drop Determinations for Tube Bundles

Description: In some engineering applications it has become necessary to operate equipment containing small diameter rods or tubes oriented parallel to flow stream. In the case of several nuclear reactors such as the Plutonium Recycle Test Reactor and the S. S. Savannah Maritime Reactor, bundles of small diameter rods are used as the fuel elements. The situation also has application to heat exchangers. A method for accurately predicting the pressure drop characteristics of various bundle configurations woul… more
Date: January 25, 1960
Creator: Gartin, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Critical Pressure Ratio for a Nozzle with Two-Phase Fog Flow

Description: In many cases of analysis of two-phase flow in systems, considerable computation or program time could be saved if the critical pressures ratio were known. If a reservoir or plenum pressure is fixed, the usual computational procedure involves the assumption of several critical pressures and the generation of several momentum terms to find the applicable critical pressure ratio and thereby the critical flow. The formulation of an equation of state make it possible to compute critical pressure ra… more
Date: March 8, 1960
Creator: Love, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Critical Tests for PRT Reactor

Description: This document authorizes the performance in accordance with the specifications noted, the PRTR Critical Tests described herein. The experiments described have the following objectives:
Date: July 1, 1960
Creator: Triplett, J. R.; Anderson, J. K.; Peterson, R. E.; Regimball, J. J.; Russell, J. T.; Schmid, L. C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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"Crud" Scrubbing with a Purex-Type Zebra Cartridge

Description: Entrained solids have in the past been one of the major factors limiting solvent extraction fission product decontamination. These solids are known to be surface active, to absorb fission products, and to form interfacial films or "cruds". A major step in eliminating these cruds was taken when the Purex columns were modified to operate with the interfaces at the waste ends of the columns rather than the product ends. This type of operation tended to flush the solids out with the waste rather th… more
Date: October 17, 1961
Creator: Richardson, G. L
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination of the Irradiated Rupture Prototype with Peroxide-Carbonate and Apace

Description: Considerable work has been done on decontamination procedures for both corrosion products and fission products. Testing of promising procedures under typical rupture conditions is an important phase of this work. The Irradiated Rupture Prototype (IRP) has been used since August in this evaluation work. This document is one of a series reporting these data.
Date: January 13, 1960
Creator: Neibaur, G. E. & Weed, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Density and Hydrogen Content of Uranium Oxide Cakes and Slurries

Description: The work described was undertaken to provide data for nuclear safety studies concerning NPF reprocessing equipment. The original objective was to determine the uranium density and water (hydrogen) content of UO2-H2O mixtures ranging from compact centrifuge cakes to dilute slurries. The scope was later expanded to include mixtures of UO2 with hydrocarbon oil and mixtures of UO3-H2O.
Date: March 22, 1960
Creator: Amos, L. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Depassivation of 304-L Stainless Steel in Sulfex Decladding Solutions

Description: In the Sulfex process, stainless steel cladding, generally 304-L, is removed from fuel elements by dissolution in boiling four to six molar sulfuric acid. When cladding removal is complete, the decladding solution is removed is removed to waste. The exposed fuel cores are rinsed and dissolved in nitric acid.
Date: June 30, 1960
Creator: Duke, E. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of a Welding Process for End Closures on NPR and KER Fuel Element

Description: With the development of the zircaloy-2 clad uranium fuel element, it was necessary to develop a method of closing the end of the element after the extruded tubes were cut to the desired length. Regardless of the ultimate design of the closure, a satisfactory zircaloy-2 fusion welding technique had to be worked out. The first fully successful welding was performed with electron beam welding in a vacuum chamber. To make satisfactory welds, the electron beam welding involved time and equipment, pl… more
Date: February 22, 1960
Creator: Corey, T. B.; DeWitt, D. E. & Nelson, I. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of a Welding Process for Spire-Can Fuel Elements

Description: The components for the present aluminum clad, Al-Si bonded, internally and externally cooled (I & E), uranium fuel elements are composed of impact extruded cans and spire caps as shown in Figure 1. This type of component requires two impact extrusions; however, in December, 1957, J. E. Ruffin proposed another design of component in which there was only one impact extrusion. For this component, Figure 2, the spire was impact extruded as a part of the can.
Date: March 11, 1960
Creator: Hanson, G. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of Pressures Tubing for the Plutonium Recycle Test Reactor

Description: Pressurized water nuclear reactors may be designed based upon either of two concepts: (1) pressure vessel, wherein the entire core is placed in a large, high strength fuel channels within a low pressure container. The Plutonium Recycle Test Reactor is a pressure tube type reactor. Selection of this basic type of pressurized water reactor depended to an appreciable extent upon the availability of suitable pressure tubing.
Date: April 28, 1960
Creator: Riches, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Disposition of Contaminated Processing Equipment at Hanford Atomic Products Operation 1958-1959

Description: Operating plant experiences in restoring to useful service failed equipment contaminated through exposures to radioactive processes is of international interest to the nuclear industry. In accordance with a request from the Hanford Operations Office of the United States Atomic Energy Commission this report of the various measures taken in rehabilitating for re-use expensive engineered equipment has been compiled by the General Electric Company. This report is a review and summary of the dispos… more
Date: February 12, 1960
Creator: Kingsley, P. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Gamma Radiation on the Physical Properties of Elastics

Description: This article presents data on the effects of gamma radiation on the physical properties of a number of different classes of plastics materials of construction which were screened to determine their capabilities and limitations for service in applications where ionizing radiation exists. The irradiations were carried out in air at ambient temperature at normal atmospheric pressure to various gamma radiation doses up to 1*10^9 r depending upon the stability of the materials to radiation exposure.… more
Date: January 20, 1961
Creator: Harrington, Robert
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of the PRTR Fuel Elemental Rupture Test Facility on Plutonium Recycle Program Objectives.

Description: To insure a full evaluation of the effects of in-reactor loops with respect to all phases of the Plutonium Recycle Program, a separate study of each loop has been undertaken. An initial study was carried out which analyzed the effects of in-reactor loops using the design criteria for the gas loop as a basis. As soon as the design criteria for the H2O high pressure loop became available, a more detailed evaluation was completed for that loop. Recent completion of the scope description of the PRT… more
Date: January 29, 1960
Creator: Peterson, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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