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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.
Item Type: Refine your search to only Report
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Advantages of palmolive alternate

Description: It has been proposed that Pu-238 be produced by irradiating neptunium solution in one or more loops in a reactor and then recovering the Pu-238 in a close-coupled separations plant. Such a scheme could replace the more conventional scheme of solid element fabrication, irradiation, and reprocessing for plutonium and neptunium recovery. This document presents the advantages of such a scheme from the standpoint of product purity and Pu-238 production.
Date: March 17, 1959
Creator: Coppinger, E. A. & Merrill, E. T.
Item Type: Refine your search to only Report
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The Agglomeration of Solid Aerosol Particles. Technical Report No. 16

Description: The variations of size and density of aerosol particles were examined. Experiments were made with a wide variety of substances using a modification of Whytlaw-Gray and Patterson's methods in which freefall velocity was determined. The mass was estimated both by balancing the gravitational and electrostatic forces and from rising velocities under constant field strength. The results were compared with the shape and structure of the aerosols shown by electron microscopy. The variation of the Stok… more
Date: March 1, 1959
Creator: Johnstone, H. F.
Item Type: Refine your search to only Report
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THE ANALYSIS OF REFRACTORY BORIDES, CARBIDES, NITRIDES, AND SILICIDES

Description: Methods are presented for the analysis of 41 refractory materials. An evaluation of the accuracy and the precision of these techniques are also given The materials studied are the borides of hafnium, molybdenum, niobiumL rhenium, tantalum, thorium, titanium, tungsten, uranium vanadium, and zirconium; the carbides of hafnium molybdenum, miobium, silicon, tantalum, thorium, titanium, tungsten, uranium, vanadium, and zircomium; the nitrides of boron, hafnium, niobium, silicon, tantalum, titanium, … more
Date: March 1, 1959
Creator: Kriege, O.H.
Item Type: Refine your search to only Report
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Analysis of Tapered Circular Plates

Description: Tables of numerical values of all necessary functions and instructions on their use in the stress analysis of circular plates which have a linear thickness-radius relationship, and which are loaded axisymmetrically, are presented. The analysis is based on the classical smalldeflection theory. Emphasis is placed on plates whose thickness at the inner radius is greater than the thickness at the outer radius. However, a limited number of plates for which the opposite is true may also be analyzed b… more
Date: March 18, 1959
Creator: Stanek, F. J.
Item Type: Refine your search to only Report
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Analysis of the Heat Generation in the Primary Sodium Pipe Tunnels, Intermediate Heat Exchanger Cells, and the Primary Sodium Fill Tank Vault for the Hallam Nuclear Power Facility (Hnpf)

Description: I. An adequate and conservative calculational method for evaluation of the heat generation distribution in the primary sodium system substructural areas was developed. The method was programed for the IBM 704 and the IBM 709. The results obtained from analysis of the gamma heat generation in the primary sodium pipe tunnels and in the intermediate heat exchanger cells are presented. Calculations are outlined, and gamma attenuation coefficients for concrete, sodium, and steel are given. II. Resul… more
Date: March 27, 1959
Creator: Legendre, P. J.
Item Type: Refine your search to only Report
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ANSWERS TO QUESTIONS ON OFF-GAS TREATMENT. Eurochemic Assistance Program: Comments by HAPO, dated March 12, 1959, on Questions by E.L. Nicholson

Description: Information relative to the performance and operation of silver reactors is presented. The information is given as answers to questions submitted in the USAECEurochemic Company cooperative program. The answers to 8 questions are presented along with the basis for comments. (J.R.D.)
Date: March 26, 1959
Creator: Bupp, L. P.
Item Type: Refine your search to only Report
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Appendix to Preliminary Design 30,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission Idaho Operations Office Contract No. AT(10-1)-925

Description: Report containing outlines of operating procedures, costs, construction, safety analysis, studies, and design specifications of a 30,000 kilowatt prototype partially enriched uranium nuclear power plant.
Date: March 1959
Creator: Kaiser Engineers
Item Type: Refine your search to only Report
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APPLICATION OF ULTRAHIGH-PRESSURE HIGH-TEMPERATURE EQUIPMENT TO STUDY OF UO$sub 2$ REACTIONS

Description: Equipment and techniques for high-pressure high temperature solid-state studies were developed, and some preliminary results for the reaction of uranium oxides with other oxidcs were obtaincd. A new die design was evolved which appears suitable for any work currently contemplated. The maximum capabilities of this new die are as yet undetermined, but its theoretical pressure limit is in excess of 200,000 atm. The die differs from similar equipment in that internal heating of the sample is employ… more
Date: March 18, 1959
Creator: Wilson, Wendell B.
Item Type: Refine your search to only Report
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ATBAC CHECK CALCULATION ON THE IBM 650, PROGRAM NO. 303

Description: This program, using the lBM 650 electronic data processing machine, is used primarily as a tool in order to prepare input data for an lBM 704 code ATBAC. The code calculates steady state thermal characteris tics of a plate type fuel element for both a nominal and adverse chanael. (auth)
Date: March 13, 1959
Creator: Beretsky, I. & Oby, P.V.
Item Type: Refine your search to only Report
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Calculational models of pot calcination

Description: A simplified model for solids deposition in the pot calcination of waste was analyzed, and numerical calculations were made. In long calcination pots of 10 to 12 in. diameter, calcination times should not exceed 24 hours and might be as low as three hours if the pot is kept full. If the pots are fed at a constant rate, the cake might form with a steady state V'' when viewed in vertical section which would progress from bottom to top. Cake deposition rates appear to be independent of pot radius.… more
Date: March 23, 1959
Creator: Whatley, M. E. & Perona, J. J.
Item Type: Refine your search to only Report
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Calibration of Omre Fuel-Element Surface Thermocouple Assembly

Description: Studies were made to determine the actual surface temperature of OMRE fuel elements if the thermocouple were not present. Chromel-alumel thermocouples are being attached to the fuel plate cladding of Type 304 stainless steel. These wires are in contact with the coolant stream. Heat transfer from the thermocouple junction, by conduction along the lead-wires and by forced convection to the coolant, produces a lowering of the surface temperature in the region of the junction which results in an er… more
Date: March 12, 1959
Creator: Sudar, S.
Item Type: Refine your search to only Report
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR OCTOBER, NOVEMBER, DECEMBER 1958

Description: Fluoride Volatilization Separations Process. Work has continued on the development of fluoride volatilization processes for recovery of U and Pu from spent power-reactor fuels. Results are reported on the fluorination rates of U and Pu oxides and fluorides. The conversion rate of UO/sub 2/F/sub 2/ to UF/sub 6/ by elemental fluorine was determined as a function of temperature. Uranium trioxide is fiuorinated at a slower rate than the other U compounds investigated. On exposure to fluorine PuO/su… more
Date: March 1, 1959
Item Type: Refine your search to only Report
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Chemical Processing Department Monthly Report: February 1959

Description: This report for February 1959, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance: Financial operations; facilities engineering; research; and employee relations.
Date: March 20, 1959
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Item Type: Refine your search to only Report
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Comparison of Two Colorimetric Methods for Uranium

Description: In order to establish the feasibility of using two colorimetric met;iods for the determination of uranium interchangeably, according to the interferences encountered in a particular sampte. results were obtained by each of the methods and compared. The dibenzoyl methane method and the ethyl acetate-ammonium thiocyanate procedure were compared on the basis of values secured on the same day. on different days, on an analysis of the variance. and on an analysis of the residual error for the method… more
Date: March 25, 1959
Creator: McCutchen, R.L.
Item Type: Refine your search to only Report
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Corrosion Resistance and Mechanical Properties of Aluminum Powder Products

Description: Experimental extrusions were prepared from mixtures of atomized aluminum alloy and several powdered additives, including SiO/sub 2/, AlPO/sub 4/, and Al/ sub 2/O/sub 3/. Some of the extrusions failed during corrosion testing in water at 290 and 350 C. Others corroded in approximately the same fashion as wrought X8001 alloy. The ultimate tensile strengths of these extrusions at 316 C were approximately two and one-half times greater than that of wrought X8001 alloy. (auth)
Date: March 1, 1959
Creator: Draley, J. E. & Ruther, W. E.
Item Type: Refine your search to only Report
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Critical Assemblies of Uranium Metal

Description: Data on critical assemblies of fissionable uranium metals are summarized. Empirical studies are made for spccific reflectors and gcometrics to determine the fcasibility of extrapolating these data for conditions concerning nuclcear safcty problems. Also included are the influencs on critical systems by various reficctors, U-235 isotopic enrichment, density, and small metal pieces homogcncously distributed in water. (auth)
Date: March 26, 1959
Creator: Gwin, R. & Mee, W. T.
Item Type: Refine your search to only Report
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Design of Production test IP-243-A-6-FP, evaluation of X-8001 alloy aluminum components fabricated from cast blanks

Description: The objective of this test is to determine the quality and erosion resistance of cape and cans produced from cast X-8001 alloy blanks through fabrication and irradiation of limited quantities in accordance with the testing procedure herein defined. Components which were fabricated from X-8001 alloy cast blanks have been subjected to rigorous out-of-reactor tests and have indicated equivalence or possible superiority to standard X-8001 alloy components. It is, therefore, proposed that; (1) six e… more
Date: March 17, 1959
Creator: Hodgson, W. H. & Hall, R. E.
Item Type: Refine your search to only Report
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Development of Silicon-Modified 48 Wt. % U-Al Alloys for Aluminum Plate-Type Fuel Elements

Description: The casting procedures, mechanical working characteristics, composite fuel plate fabrication, and fuel element assembly methods for a nominal 48 wt.% U- 3 wt.% Si -AP alloy are examined. It was found that localized clad thinning, resulting from dogboning'' of the fuel alloy, is essentially eliminated in composite Plates when this alloy is used in combination with 5154 Al frames and 1100 Al covers. However, fuel component dimensions are difficult to maintain within commonly accepted tolersnces i… more
Date: March 23, 1959
Creator: Thurber, W. C. & Beaver, R. J.
Item Type: Refine your search to only Report
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Division of Reactor Development Programs Monthly Report - February 1959

Description: Plutonium Oxide Fuels. Mixtures of PWR grade UO2 containing 10, 20, 30, 40, 50, and 60 w/o PuO2 were sintered in hydrogen for 44 hours at 1600 C to get additional data on solubility in this system. Densities of all the pieces were low, approximately 80 percent of theoretical; however, solid solution formation was complete in every case. The low density material should not affect lattice parameter values, but it did slightly reduce the intensity of the reflections.
Date: March 15, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
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