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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.
Partner: UNT Libraries Government Documents Department
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1706 KE Water Treatment for Out-of-Reactor Test Facilities.

Description: Water treatment systems for preparing and maintaining high purity water in out-of-reactor or in-reactor test oops are becoming increasingly important. In out0of-reactor experiments the presence of ionic impurities in the water has a marked influence on film formation and corrosion rates. It is therefore , imperative that these impurities be maintained at the lower practical concentration.
Date: March 30, 1959
Creator: Demmitt, Thomas F.
Partner: UNT Libraries Government Documents Department
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An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept

Description: From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."
Date: March 1, 1958
Creator: Hanford Works
Partner: UNT Libraries Government Documents Department
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Application and Operation of the 325 Building Well Counter

Description: Well-type scintillation counters have found use in many radiochemical laboratories. A gamma scintillation well counter has been used to measure the gamma activity of liquid samples in the 325 Building counting room for about a year. This well counter has been built and calibrated so that gamma activity measurements made with it can be easily compared with measurements made with the gamma scintillation counter (GSC). The well counter is electronically identical to the present GSC and differs onl… more
Date: March 8, 1956
Creator: Brauer, F. P.
Partner: UNT Libraries Government Documents Department
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Applied Potential Corrosion of Aluminum and 18-8 Stainless Steel Alloys

Description: Introduction: In anticipation of the design of equipment for heat transfer tests, a series of short exposure corrosion tests was initiated in an effort to determine the order of magnitude of the corrosion involved. Information was required on the effect on corrosion rates of applying a potential between two concentric tubes, the annulus between them containing condensate water.
Date: March 13, 1930
Creator: Sanborn, Kenneth L.
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.
Partner: UNT Libraries Government Documents Department
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Calcium Uranium(IV) Fluoride; Precipitation and Reduction to Metal

Description: Using ferrous ion in the presence of fluoride for reducing uranium(VI) to the four state, the salt calcium uranium (IV) fluoride can be precipitated from uranyl nitrate solutions. X-ray studies have shown that the precipitate is a true double salt and not a mixture of the two insoluble fluorides of calcium and uranium. The salt settles rapidly and can be either filtered or centrifuged. Waste losses during precipitation and washing were on the order of 2.0 and 0.4 per cent, respectively. These w… more
Date: March 17, 1955
Creator: Tolley, W. B.
Partner: UNT Libraries Government Documents Department
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Canning depleted uranium : production test 313-110-M, final report

Description: From summary: "Uranium billets deficient in U235 were subjected to the normal successive steps in the slug fabrication process; viz., rolling, machining, and canning. No unusual behavior was observed at any point in the process, thus indicating that the depleted metal from the standpoint of mechanical properties can be considered equivalent to normal uranium."
Date: March 27, 1951
Creator: Jones, T. S.
Partner: UNT Libraries Government Documents Department
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Chemical Stability of Purex and Uranium Recovery Process Solvent

Description: The desirability of operating many of the Purex columns at elevated temperatures, ca. 50-70 C, has made it necessary to obtain data on the stability of the solvent at these higher temperatures. Since the present diluent, Shell Spray Base, will not be entirely safe at the upper temperature limit, a number of diluents with higher flash point have been investigated concurrently with Shell Spray Base. This report presents data covering the first phases of this investigation, namely, the effect of n… more
Date: March 2, 1955
Creator: Moore, R. H.
Partner: UNT Libraries Government Documents Department
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Chemistry of the "Silver Reactor"

Description: The use of a reactor charged with silver nitrate coated packing for removal of radio-iodine from the waste gases of Hanford chemical processing plants has been successful in removing approximately 99.5 percent of this activity. Studies by the Radiological Sciences Department indicated the desirability of further reducing the amount of radio-iodine released to the atmosphere. Therefore, this study was undertaken with the objectives of better understanding the inherent limitations to iodine remov… more
Date: March 5, 1956
Creator: Barton, G. B. & McClanahan, Jr., E. D.
Partner: UNT Libraries Government Documents Department
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Concrete Cone Anchor Tests

Description: This study was initiated to determine the minimum safety requirements for safe anchorage of electric pole lines. The objectives were to investigate the suitability of manufactured concrete pole line anchors for use at the Hanford Atomic Products Operation, to design a concrete anchor slug of optimum shape and size for manufacture, to determine by field tests the resistance pullout of the concrete anchor when buried at various depths under the most favorable condition, and to develop a safe desi… more
Date: March 18, 1955
Creator: Buchols, C. S.
Partner: UNT Libraries Government Documents Department
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Continuous Electrochemical Determination of Oxygen in Gases

Description: To forestall the oxidation of graphite in HAPO reactors, a process specification provides that the oxygen concentration in pile gas should be kept to a minimum. Close control in maintaining this limit is difficult when only periodic samples are taken because laboratory results are always obtained long after any required corrections should have been made. A continuous-type analyzer that provides immediate knowledge of the oxygen concentration eliminates these time delays.
Date: March 28, 1956
Creator: Koyama, K.
Partner: UNT Libraries Government Documents Department
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Corrosion of Stellite in MJ-1 Streams

Description: The following report provides data from completed tests for corrosion testing of stellite-T347 stainless steel test cylinders.
Date: March 8, 1950
Creator: Koenig, W. W.
Partner: UNT Libraries Government Documents Department
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Corrosion resistance and magnetic susceptibility

Description: From summary: "On the basis of the tests described herein, the corrosion characteristics of T-347 welded stainless steel are found not to be affected by the magnetic properties of the welds even though these properties are likely the result of the presence of the ferritic structure."
Date: March 7, 1949
Creator: Koenig, W. W. & Heckman, R. L.
Partner: UNT Libraries Government Documents Department
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Corrosive Effects of Heavy Metal Ions on Aluminum

Description: From summary: The object of the study was to determine if the heavy metal ions within the concentration ranges normally found in pile cooling water were responsible for corrosion of aluminum.
Date: March 17, 1953
Creator: Fujioka, G. S.
Partner: UNT Libraries Government Documents Department
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The Coulometric Determination of Acid

Description: Introduction: "The need for a method of acid determination which could be used for small samples and easily adapted to remote control led to the investigation of the use of electrolytically generated base for the titration of acid in certain solutions. The use of electrolytically generated base for the titration of acetic acid in the presence of nitric acid has been reported (1)."
Date: March 1, 1950
Creator: Carson, W. N. & Ko, Roy
Partner: UNT Libraries Government Documents Department
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Crack Sensitivity of Type 308L & 347 Metal Arc Weld Deposits

Description: The tendency for Austenitic Stainless Steels to develop cracks may be considered to be a function of several variables. Chemical composition of the electrode and base metal, are variables which have been reported to greatly influence the final behavior of the weld. Two types of electrodes, Type 308L and Type 347, were compared with respect to their respective crack sensitivities. Also, comparative results were desired between the 308L-15 (DC) and 308L-15 (AC-DC) type electrodes. At present, no … more
Date: March 19, 1956
Creator: Smith, W. R.; Lemon, L. C. & Sako, J. H.
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.
Partner: UNT Libraries Government Documents Department
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Criticality Considerations in Final Cycle Processing of Enriched Uranium Fuels

Description: It is the purpose of this report to show the effect of irradiation on initial U-235 enrichment. This data should prove helpful for making studies of the processing costs for slightly-enriched power reactor fuels.
Date: March 5, 1957
Creator: Katalach, N.
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.
Partner: UNT Libraries Government Documents Department
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Design, Development and Research Contract DDR-33

Description: This report summarizes experimental results obtained for the General Electric Company under terms of Design, Development and Research Contrast DDR-33. A discussion of the results, the manner in which they were obtained and their probable accuracy are included. Suggested improvements or modifications of properties of this nature be contemplated.
Date: March 13, 1958
Creator: Johanson, L. M.; Campbell, Robert J. & Mueller, Edward E
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.
Partner: UNT Libraries Government Documents Department
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The Development of Plutonium Electrodeposition Methods : Interim Report

Description: From introduction: "The following report presents a body of information obtained in the Health Instrument Development Laboratory from September, 1948, to the present, and is intended to be a preliminary review of [the study of electrodeposition of plutonium]. Many improvements in technique and methods and investigations along lines not explored are suggested by the present work. These will be undertaken as time permits, and reported at a later time."
Date: March 1, 1950
Creator: Schwendiman, L. C.
Partner: UNT Libraries Government Documents Department
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