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Comments on Equipment for a PRTR Water Quality Control Laboratory

Description: This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating… more
Date: December 1, 1959
Creator: Anderson, H. J. & Peray, R. E.
Item Type: Refine your search to only Report
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Comparative Costs Of Sea Disposal And Land Burial For The Radioactive Wastes Of The Lawrence Radiation Laboratory

Description: This report is a comparative cost study of radioactive waste disposal for the Lawrence Radiation Laboratory (UCRL). In particular, it compares the costs of sea disposal in depths of 1000 fathoms and of 2000 fathoms off the California coast with land burial of the wastes at the Hanford Atomic Products Operation (HAPO), Richland, Washington, at the National Reactor Testing Station (NRTS), Idaho Falls, Idaho, or at the Nevada Test Site (NTS), Nevada. In the comparison, the cost of utilizing a comm… more
Date: January 21, 1959
Creator: Nielsen, Elmer
Item Type: Refine your search to only Report
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Comparison of BEO Versus Graphite as a Moderator for MGCR

Description: The comparison is made on the basis of nuclear requirements, properties, cost, and performance under irradiation. Results of published work were reviewed on the effects of irradiation on beryllium oxide and beryllium oxide - uranium dioxide dispersions. A research proposal for a Maritime Gas-cooled Reaotor Moderator is included. (J.R.D.)
Date: September 11, 1959
Creator: Wallace, W. P. & Simnad, M. T.
Item Type: Refine your search to only Report
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A COMPARISON OF ELEMENTARY CRITICALITY CALCULATIONS WITH EXPERIMENTAL RESULTS

Description: Several experiments have been performed at ORNL with light water solutions of uranyl nitrate (highly enriched in either U/sup 233/ or U/sup 235/) in an essentially bare sphere 27 inches in diameter. Results are presented of several calculations with elementary bare reactor theory and a discussion of the observed discrepancies between the calculated and experimental results. If the observed critical concentration is used in the calculations, the calculated effective multiplication constant is le… more
Date: June 11, 1959
Creator: Nestor, C. W. Jr.
Item Type: Refine your search to only Report
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A Comparison of Elementary Criticality Calculations with Experimental Results

Description: Several experiments have been performed at ORNL with light water solutions of uranyl nitrate (highly enriched in either U^233 or U^235) in an essentially bare sphere 27 inches in diameter. This report presents the results of several calculations with elementary bare reactor theory and a discussion of the observed discrepancies between the calculated and experimental results. If the observed critical concentration is used in the calculations, the calculated effective multiplication constant is l… more
Date: June 11, 1959
Creator: Nestor, C. W., Jr
Item Type: Refine your search to only Report
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Comparison of Thickness, Grade, and Depth of Radioactive Layers as Determined by Gamma-Ray Logging and by Core Sampling

Description: Abstract: "Thickness, grade, and depth data were obtained by analyzing gamma-ray logs and core samples from 56 diamond drill holes penetrating uranium deposits in the Colorado Plateau. The data from the two methods were compared to determine variations found in gamma-ray log interpretation and chemical and radiometric analyses of the drill core. Correlations within each parameter varied among the drilling areas analyzed. Gamma-ray interpretations of grade compared to chemical analyses were with… more
Date: August 1959
Creator: Bunker, Carl M.
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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COMPARISONS OF ORGANIC EXTRACTANTS FOR IRRADIATED URANIUM: TRIBUTYLPHOSPHATE VS DI-SEC-BUTYL PHENYLPHOSPHONATE, DI-N-BUTYL PHENYLPHOSPHONATE, TRI-CAPRYL-PHOSPHATE AND TRI-SEC-BUTYLPHOSPHATE

Description: Batch extraction scouting tests were performed to establish comparisons of distribution coefficients for uranium, thorium, fission product, and/or plutonium in systems involving several classes of organic phosphorus compounds (diluted in Amsco 125-82 and/or xylene) and aqueous nitrate or nitric acid solutions. Results have substantiated previous conclusions which suggested (1) that the branched secondary alkylphosphates and alkylphenylphosphonates would generally afford uranium separation facto… more
Date: June 1, 1959
Creator: Gresky, A.T. & Mansfield, R.G.
Item Type: Refine your search to only Report
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COMPATIBILITY OF ZIRCONIUM HYDRIDE AND CARBON DIOXIDE

Description: The stability of unclad zirconium hydride was investigated as a reactor moderator in carbon dioxide coolant. Two ranges of hydride were tested, an alpha- plus deltaphase hydride (ZrH/sub 0.9 plus or minus 0.2/) and a delta-phase hydride (ZrH/sub 1.5/). The delta-phase hydride exhibited excellent dimensional stability, but suffered as great as 20% hydrogen loss at 1200 deg F, together with severe corrosion. The alphaplus delta-phase hydride swelled and warped in a temperature gradient but did no… more
Date: July 1, 1959
Creator: Shoemaker, H.E.
Item Type: Refine your search to only Report
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Complete Determination of Polarization for a High-Energy Deuteron Beam

Description: please delete the no. 17076<><DSN>13:017077<ABS>The P/sub 1/ multigroup code was written for the IBM-704 in order to determine the accuracy of the few- group diffusion scheme with various imposed conditions and also to provide an alternate computational method when this scheme fails to be sufficiently accurate. The code solves for the spatially dependent multigroup flux, taking into account such nuclear phenomena is slowing down of neutrons resulting from elastic and inelastic scattering, the r… more
Date: May 1, 1959
Creator: Button, J.
Item Type: Refine your search to only Thesis or Dissertation
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Composition of Solids from Purex LWW

Description: The solids in Purex lww were first observed during flowsheet tests for recovery of fission products from plant wastes. Since the nature of this solid was not apparent from the flowsheet composition of lww, some work was performed to characterize this material. Although this work has been conducted over a period of about one year, it has been subordinate to the main one of testing flowsheets for fission product recovery. The solids have been observed in each of about six samples of plant lww tha… more
Date: January 22, 1959
Creator: Van Tuyl, H.H.
Item Type: Refine your search to only Report
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Computational Aids for Estimating Performance of Liquid to Boiling Water Heat Exchangers

Description: The computation of liquid-boiling heat exchanger performance under a wide variety of operating conditions is a cumbersome, time-consuming procedure. Rapid evaluation of a design requires the use of some form of computational aid. Exchanger equations covering the case of liquid-boiling heat transfer have been derived and evaluated for a specific correlation of local boiling condition. Examination of various data as presented by Bonilla and McAdams indicates that the boiling coefficients are not … more
Date: September 1, 1959
Creator: Love, W. J.
Item Type: Refine your search to only Report
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CONCENTRATION AND FINAL PURIFICATION OF NEPTUNIUM BY ANION EXCHANGE

Description: It was demonstrated that neptunium(IV) can be readily absorbed onto anion exchange resins from 6 M HNOsub 3/ containing ferrous sulfamate and hydrazine or semicarbazide, separated from plutonium, uranium, and common metallic impurities by washing the resin at 25 deg C with 6 M HNO/sub 3/ containing ferrous sulfamate and hydrazine or semicarbazide, separated from fission products and thorium by washing the resin at 60 deg C with S M HNO/sub 3/- 0.01 M HF containing hydrazine or semicarbazide, an… more
Date: February 10, 1959
Creator: Ryan, J. L.
Item Type: Refine your search to only Report
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Concentration and Final Purification of Neptunium by Anion Exchange

Description: It is anticipated that neptunium will be recovered in the Purex process by solvent extraction or ion exchange methods as a nitric acid solution of greater than 0.1 g. Np/1 and containing varying amounts of fission products, plutonium, uranium, and thorium, including Th234 (UX1). At the present time this solution is thermally concentrated in the Purex L-cell package to several grams of neptunium per liter. In this operation the solution is contaminated rather badly with plutonium and stainless s… more
Date: February 10, 1959
Creator: Ryan, J.L.
Item Type: Refine your search to only Report
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Concentration of Plutonium by Cation Exchange--Stabilization of Pu(III) in Nitric Acid

Description: A study to define the effectiveness limits of sulfamic acid and to discover other better stabilizers for Pu(III) is described. Ascorbic and isoascorbic acids, used in conjunction with sulfamic acid reduced Pu(IV) to stable Pu(III) in nitric acid. Aminoguanidine sulfate also retarded the oxidation of Pu(III) but did not reduce Pu(IV). (J.R.D.)
Date: February 1, 1959
Creator: Tober, F. W. & Russel, E. R.
Item Type: Refine your search to only Report
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Concentration of Plutonium by Cation Exchange -- Stabilization of Pu(Ill) in Nitric Acid

Description: Technical report. From Abstract : "Ascorbic and isoascorbic acids, used in conjunction with sulfamic acid, reduced Pu(IV) rapidly and completely to Pu(III) in solutions of nitric acid. The solutions of Pu(III) were stable. Aminoguanidine sulfate also retarded the oxidation of Pu(III) but did not reduce Pu(IV)."
Date: February 1959
Creator: Tober, Frank W., 1919-1995 & Russell, Edwin R.
Item Type: Refine your search to only Report
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Condensate System. Section II. Fifth Core I, Seed 1. Test Results DL-S-105

Description: The purpose of the test was to fill the condensate storage tank and the Condensate System and obtain satisfactory preliminary operation. The components of the Condensate System performed adequately and satisfactorily with the exception of fill control valve (M9-VI). This valve (M9-VI) is not used in the current operation procedure.
Date: December 8, 1959
Item Type: Refine your search to only Report
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Confinement System Instrumentation

Description: Instrumentation shall be provided as shown on the attached drawing, SK-1-26835 for Confinement System Control. The Primary objective of the confinement system shall be to provide maximum possible confinement of contamination, consistent with building limitations, in the event of any contamination, consistent with building limitations, in the event of any credible reactor accident resulting from equipment failure or reactor mis operation.
Date: November 6, 1959
Creator: Richards, W. A.
Item Type: Refine your search to only Report
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CONSTITUTION OF LOW CARBON U-C ALLOYS

Description: (((Abstract unscannable)))<><DSN>13:014503<ABS>Thc Nb-O equilibrium system was determined by metallographic examination of arc-cast alloys made ot electron-gun-refined Nb metal and special purity Nb/sub 2/O/sub 5/. Two intermediate oxides. NbO and NbO/sub 2/, melt without decomposition at 1945 C and 1915 C, respectively. Eutectic reactions exist between Nb and NbO at 1915 C and between NbO and NbO/sub 2/ at 1810 C . Experimental evidence supports a peritectic reaction between NbO/sub 2/ and Nb/… more
Date: February 1, 1959
Creator: Blumenthal, B.
Item Type: Refine your search to only Report
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Construction Materials for the Hydrofluorinator of the Fluoride-Volatility Process

Description: Fuel elements clad with Zr or containing Zr as a diluent can be recovered by a fluoride-volatility process. The first step consists of hydrofluorination of the elements in a bath of molten fluoride salts using an HF sparge. In this case the two salt systems considered were NaF-ZrF/sub 4/ and NaF- LiF. Materials evaluated at Battelle for possible use in the construction of this hydrofluorinator include Inconel, A'' Nickel, copper, silver, Monel, Hastelloy B, Hastelloy W, INOR-1, and INOR-8. The … more
Date: June 1, 1959
Creator: Miller, P. D.; Peterson, C. L.; Stewart, O. M.; Stephan, E. F. & Fink, F. W.
Item Type: Refine your search to only Report
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