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Analytical Chemistry Division Semiannual Progress Report for Period Ending April 20, 1954

Description: Progress report of the Oak Ridge National Laboratory Analytical Chemistry Division providing updates on various projects, experiments, and other work in ionic analyses, analytical instrumentation, radiochemical analyses, activation analyses, spectrochemical analyses, inorganic preparations, optical and electron microscopy.
Date: July 5, 1956
Creator: Kelley, M. T.; Susano, C. D. & Raaen, H. P.
Partner: UNT Libraries Government Documents Department
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Fabrication of Heat Exchangers and Radiators for High Temperature Reactor Applications

Description: Two 500-kw fused-fluoride-to-Nak heat exchangers, two 500-kw NaK-to-air radiators, and a 20-tube high-velocity heat exchanger were fabricated for a heat-exchanger development program. A construction procedure, utilizing both inert-arc-welding and high temperature dry-hydrogen brazing, was used successfully on all of the units. The tube-to-header joints were welded and back-brazed; the manifold joints were inert-arc-welded with full penetration; and the tube-to-fin joints were brazed. A detailed… more
Date: July 5, 1955
Creator: Patriarca, P; Slaughter, G. M.; Manly, W. D.; Heestand, R. L.; Clausing, R. K.; Conner, O. K. et al.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report For Period Ending June 10, 1955

Description: The development of the reactor layout is continuing. New features that have been incorporated because of stress, fluid flow, or fabricability considerations include an elliptical fuel expansion tank, a rounded dome to enclose the top of the reactor, a newly designed sodium pump impeller, and other related items. Recently completed heat exchanger tests yielded consistent data from which a series of heat exchangers is being designed. The most promising of these will be chosen for the ART.
Date: July 28, 1955
Creator: Jordan, W. H.; Cromer, S. J.; Strough, R. I.; Miller, A. J. & Savolainen, A. W.
Partner: UNT Libraries Government Documents Department
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Homogenous Reactor Project Quarterly Progress Report For Period Ending April 30, 1955

Description: Part I. Experimental Reactors: The effect of prompt-neutron lifetime upon reactor safety was investigated for the HRT. It was found that for a given pressure rise the allowable rate of reactivity addition was relatively insensitive to the average prompt-neutron lifetime, although the rate de creased somewhat with decreasing lifetime for the higher pressure rises. With only source neutrons present and the reactor initially subcritical, the allowable rate was practically independent of the initia… more
Date: July 14, 1955
Creator: McDuffie, H. F. & Kelly, D. C.
Partner: UNT Libraries Government Documents Department
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Diffusion of Ions in a Plasma Across a Magnetic Field

Description: A theoretical and experimental investigation of the coefficient for diffusion of ions across a magnetic field Is described. The resultant diffusion coefficient is found to vary inversely as the square of the magnetic field strength, in accord with the usual collison-diffusion theory. The magnitude of the coefficient is much larger (x700) than the coefficient predicted by the usual ambipolar diffusion theory. This discrepancy is resolved by showing that diffusion across a magnetic field is not a… more
Date: July 1955
Creator: Simon, Albert & Neidign, Rodger V.
Partner: UNT Libraries Government Documents Department
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Determination of Plutonium and Uranium in Scrup Dissolver Solutions

Description: Methods for the determination of plutonium and uranium in highly radioactive scrup dissolver solutions have been developed. Plutonium was separated from the dissolver solutions by solvent-extraction and ion-exchange techniques and determined by potentiometric titration. Uranium was separated by ion exchange and determined by potentiometric titration. Solutions that were similar to the actual dissolver solutions and that contained known amounts of plutonium and uranium were analyzed by these met… more
Date: July 14, 1955
Creator: Foster, R. W.; Cooper, J. H. & Raaen, H. P.
Partner: UNT Libraries Government Documents Department
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Solid State Division Semiannual Progress Report For Period Ending February 28, 1955

Description: This semiannual progress report and future reports will be published as two documents to permit a wider distribution of the unclassified material. The report numbers are assigned in sequence so that the two reports will fall together when filed by report number.
Date: July 12, 1960
Creator: Billington, D. S. & Crawford, J. H., Jr.
Partner: UNT Libraries Government Documents Department
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Suggested Major Equipment for NPR Water Quality Control Labs

Description: Two water quality control labs are being provided for the the NPR. One, a "cold" lab, is located in the183 Building adjacent to the control room. Its primary purpose is to provide facilities for quality control of the output of the filter plant and the demineralizer plant. The other, a "hot" lab, is located in the 190 Building. Its primary purpose is to provide facilities for the quality control of the primary and secondary coolants, and the moderator coolant.
Date: July 30, 1959
Creator: Bainard, W. D.
Partner: UNT Libraries Government Documents Department
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PRTR Total Energy Distribution Calculations

Description: Since the calculation of the PRTR energy distribution was first carried out by J. R. Triplett, the design has become sufficiently fixed to allow a refinement of his values. The present analysis, also, includes a calculation of the fraction of energy which is released in the shroud and process tubers that flows to the primary coolant to the top and bottom shield coolant is taken into consideration. Nuclear data used in the original calculations still appears satisfactory and is, therefore, util… more
Date: July 31, 1959
Creator: Peterson, R. E.
Partner: UNT Libraries Government Documents Department
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DC Bridge NPR Horizontal Rod Counting

Description: This report is a summary of work done for system development on the NPR ball safety backup for the horizontal rods. This phase of the system development is limited to discussion of the horizontal rod counting circuitry utilizing a direct current bridge network.
Date: July 24, 1959
Creator: {{{name}}}
Partner: UNT Libraries Government Documents Department
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Stack Effluent Monitor Operation and Maintenance

Description: The Stack Effluent Radioisotope Monitor is an instrument which continuously measures and records the amounts of each of several different radioactive isotopes in the stack effluent of the Redox Facility. An informal report, HW-56151, describing the theory of operation and the circuits was prepared and is available to Hanford personnel from the technical files. The formal report, HW-56151 Rev, containing essentially the same information, is available from the Office of Technical Services, Depar… more
Date: July 21, 1959
Creator: Harvey, R. A.
Partner: UNT Libraries Government Documents Department
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A Microspark Apparatus for the Study of Inclusions in Metals

Description: A study of metallurgical problems resulting from variation in grain boundaries, bonding layers, and inclusions in metals and alloys has become increasingly important over the past several years. To keep pace with and aid in these studies, several new techniques have been developed in emission and X-ray spectroscopy. In X-ray, areas as smalls as one square micron can be studied by making them targets for a focused electron beam and observing the X-rays emitted (5,2). Such an instrument would be … more
Date: July 22, 1959
Creator: Smith, F. M.
Partner: UNT Libraries Government Documents Department
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A Remote Phase Separation Bulb for Highly Radioactive Sample Analyses

Description: Extraction systems involving chelating agents are widely used in radiochemical separations on a control basis due to the economy in time and equipment. In the case of waste streams, the element of interest is, by definition, at a very low concentration in the presence of gross fission product activities. The resultant large sample size necessary for a reliable analytical results creates a marked radiation hazard to laboratory personnel.
Date: July 21, 1959
Creator: Campbell, M. H.
Partner: UNT Libraries Government Documents Department
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Recovery of Plutonium and Neptunium from Purex IWW by Anion Exchange

Description: The recovery of plutonium and neptunium by anion exchange has been well demonstrated on a laboratory scale. (1, 2,3,4) The specific adsorbed by the resin is the tetravalent hexanitrate complex of either element. With plutonium (IV) and neptunium(V) in IWW, the plutonium is adsorbed but the neptunium is not. If nitrite is used as the reductant in strong (preferably 8 M or over) nitric acid, both plutonium and neptunium are obtained in the tetravalent state, and both are adsorbed on the resin. Wi… more
Date: July 16, 1959
Creator: Van Tuyl, H. H.
Partner: UNT Libraries Government Documents Department
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Preliminary Chemical Flowsheets for the Decladding and Dissolution of Non-Production Fuels

Description: This document presents preliminary chemical flowsheets for cladding and core dissolution of zircaloy-clad uranium dioxide and stainless steel-clad uranium-molybdenum non-production fuels. These preliminary flowsheets together with existing process flowsheets should be adequate for process development in the currently forecast non-production fuels dissolution facility.
Date: July 24, 1959
Creator: Harmon, M. K.
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Reports-June 1959

Description: Basic Studies. Sinterability experiments in the system UO2-PuO2 have continued, and data are available at one hour hold times across the UO2-PuO2 composition limits. Sintered densities appear to be markedly dependent on pressed densities with densification occurring very rapidly at higher pressing pressures. The following table illustrates the effect of one hour at temperature on final density for pure plutonium dioxide pressed to both 40 and 60 percent of theoretical density.
Date: July 15, 1959
Creator: Lewis, M.
Partner: UNT Libraries Government Documents Department
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An Aqua Recia Flowsheet for Uranium Dissolution

Description: Relatively long time cycles are required for the standard nitric acid dissolution of enriched uranium using safe batch size techniques for criticality control. Upwards of forty eight hours are required for the total dissolution of solid of I and E enriched slugs in nitric acid. The dissolution capacity may be increased by: (1) using a dissolver critically safe by virtue of its geometry or, (2)increasing the rate of uranium dissolution. Dilute agua regia -- a mixture of hydrochloric and nitric a… more
Date: July 21, 1959
Creator: Shefcik, J. J.
Partner: UNT Libraries Government Documents Department
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Neutron Age Calculations. (Homogeneous Systems)

Description: In an earlier study on criticality conditions for homogenous mixtures, 2/cm^2 was used as the neutron age for all mixtures of water and uranium. At the higher H/U ratios (low uranium concentration), the calculated critical parameters were in good agreement were in good agreement with experimental data. At the low H/U ratios (high uranium concentrations) the calculated critical parameters were smaller than the experimental ones (more conservative from a nuclear safety point view). These results … more
Date: July 10, 1959
Creator: Ketzlach, N.
Partner: UNT Libraries Government Documents Department
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Heat Transfer Testing

Description: Several tests are being performed and others being planned to investigate the role of heat transfer in corrosion processes. These tests are measuring both corrosion rates of metals (Zr-2 and X-8001 aluminum) under heat transfer, and the temperature rise associated with the buildup of the corrosion product. A brief description of these tests is given in this report.
Date: July 7, 1959
Creator: Doman, D. R.; Hokenson, J.F. & Lobsinger, R. J.
Partner: UNT Libraries Government Documents Department
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PRTR Hazard Analysis For Various Mechanical Failures

Description: The hazards associated with several possible mechanical failures were analyzed for the PRTR. The consequences of these failures were evaluated for inclusion in the Final Hazards Summary Report.
Date: July 6, 1959
Creator: Muraoka, J.
Partner: UNT Libraries Government Documents Department
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The Operation and Maintenance of an Alpha Energy Analyzing System

Description: The measurement of a alpha-particle energy has been used by many radiochemical laboratories for the identification and analysis of alpha-active radio nuclides. The use of the total-ionization method for alpha-active radio-nuclides. The use of the total-ionization method for alpha energy in ionization chamber in which the alpha particle loses all its energy in ionization of the chamber gas. Collection of the electrons thus formed generates a voltage pulse across the chamber capacity which is pro… more
Date: July 10, 1959
Creator: Brauer, F. P. & Connally, R. E.
Partner: UNT Libraries Government Documents Department
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PRTR Single Tube Prototype Mockup (STPM) Operational Characteristics

Description: The Single Tube Prototype Mockup (STPM) was constructed to be used as a tool to evaluate the mechanical problems involved in operating and maintaining many components of the Plutonium Recycle Test Reactor (PRTR). This report has been written to acquaint interested HAPO components with the capability of the STPM and for use as an aid in scheduling tests and/or to properly evaluate testing results obtained from the mockup.
Date: July 2, 1959
Creator: Scott, P. A.
Partner: UNT Libraries Government Documents Department
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Quarterly Report of Non-Production Reactor Fuels Reprocessing Budget Activity 3790

Description: This report summarizes the research and development work carried out during March, April and May, 1959, for Budget Activity 2790 - Separations Development for Non-Production Reactors, The effort on Activity 2790 will enable Hanford to begin reprocessing in January, 1962, the fuel elements from power reactors which employ depleted or slightly enriched uranium fuels.
Date: July 2, 1959
Creator: Cooper, V. R.
Partner: UNT Libraries Government Documents Department
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Portable Radiation Instrumentation Standardization

Description: This development work was undertaken to investigate and standardize scintillation detector and transistorized circuitry techniques in instruments used for detecting and measuring alpha and beta particles, gamma photons, and both slow and fast neutrons. At the present time, the standard radiation detection instrumentation used at Hanford employ vacuum-tube circuitry with typical detectors being ion chambers, G-M tubes, HF3 tubes, etc. The vacuum tubes require excessive battery power, and some of… more
Date: July 1, 1960
Creator: Spear, W. G.
Partner: UNT Libraries Government Documents Department
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