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Chemical Processing Department Monthly Report: September 1963

Description: This report, from the Chemical Processing Department at HAPO for September 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; weapons manufacturing operation; and power and crafts operation.
Date: October 21, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Department Monthly Report: May 1963

Description: This report, from the Chemical Processing Department at HAPO for May 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; weapons manufacturing operation; and power and crafts operation.
Date: June 21, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Analysis of E-N target conversion data

Description: Production efficiency studies of the E-N loading require that conversion ratio values for both plutonium and tritium be defined. Changing of the core-loading charge makeup with each core load to obtain a more efficient loading has theoretically resulted in increasing the tritium conversion ratio. Tritium recovery data from the third H Reactor E-N loading has recently become available for analysis. The buildup of product is much slower in fringe blanket material then in core target pieces. The s… more
Date: November 21, 1963
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
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Irradiation and Performance of Depleted Uranium

Description: The production of plutonium containing 17 to 18 per cent Pu-240 has been proposed for Hanford as part of the over-all process for production of transuranium isotopes. Purpose of this report is to summarize measures that would be taken to ensure good performance of the depleted uranium fuel elements and to predict the performance of the depleted fuel.
Date: May 21, 1963
Creator: Heeb, C. M.; Knight, F. W. & Spencer, H. G.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: February 1963

Description: This report, for February 1963 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; employee relations; weapons manufacturing operation; and safety and security.
Date: March 21, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Metastability of alpha plutonium

Description: The metastability of alpha plutonium above the {alpha} {r_equilibrium} {beta} equilibrim transformation temperature (112 C) was studied by metallographic techniques. The purpose of this study was to extend the previous work on the {alpha} {yields} {beta} transformation which was accomplished using fluid displacement techniques{sup 1} and to obtain a basis for determining the length of time the alpha phase is stable at high temperatures. Approximate isothermal reaction curves were determined exp… more
Date: January 21, 1963
Creator: Nelson, R. D.
Partner: UNT Libraries Government Documents Department
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A program for the numerical control of a pulse increment system

Description: This report will describe the important features of the development of magnetic tapes for the numerical control of a pulse-increment system consisting of a modified Gorton lathe and its associated control unit developed by L. E. Foley of Equipment Development Service, Engineering Services, General Electric Co., Schenectady, N.Y. Included is a description of CUPID (Control and Utilization of Pulse Increment Devices), a FORTRAN program for the design of these tapes on the IBM 7090 computer, and i… more
Date: August 21, 1963
Creator: Gray, D. C.
Partner: UNT Libraries Government Documents Department
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Production of special nuclear materials in N-Reactor

Description: In the summer of 1962, a brief scoping study of the N-Reactor`s capability as a producer of tritium concurrently with plutonium and steam was completed and documented. This study indicated that there might be considerable incentive in pursuing the development of a multi-product mode of operation of the N-Reactor. Early in 1963 reports presented the preliminary production and cost data, and brief discussions of the potential technical problems which mav arise in a multi-product mode of operation… more
Date: October 21, 1963
Creator: Condotta, D. L. & Pierick, E. G.
Partner: UNT Libraries Government Documents Department
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Transformation of retained phases in plutonium

Description: The transformation of retained phases of plutonium of different quality has been determined over a period of 10--12 months, by observing the density variation with time. A large density increase of each specimen was observed. The density increase of the low quality metal was the greatest and that of the highest quality metal was the least. The magnitudes of these increases are apparent from the graphs. One of the specimens fractured into two pieces after ten months. Also, surface cracks appeare… more
Date: January 21, 1963
Creator: Nelson, R. D.
Partner: UNT Libraries Government Documents Department
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Dissolved air in process water study: Summary report

Description: During the early part of CY-1961, water leak frequency on plant began to pose a mounting problem. At this time, DR reactor exhibited a leak mechanism which, although observed to some extent at other reactors, appeared to be primarily a DR problem. This mechanism can best be described as a trench running longitudinally along the top portion of the process tube. The dimensions vary considerably; however, the lengths attained were generally about two to there feet and the width was roughly one inc… more
Date: January 21, 1963
Creator: Radtke, W. H.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: October 1963

Description: This report, for October 1963 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; employee relations; weapons manufacturing operation; and safety and security.
Date: November 21, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Department Monthly Report: January 1963

Description: This report, for January, 1963 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; finished products operation; financial operations; facilities engineering; research employee relations; weapons manufacturing operation; and power and several maintenance operation.
Date: February 21, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
open access

Specifications and Procedures Used in Manufacturing U$sub 3$O$sub 8$- Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor

Description: A thin plate-type element containing a dispersion of 20% enriched U/sub 3/O/sub 8/ was developed and successfully used in the 5-Mw pool-type research reactor at the Puerto Rico Nuclear Center. The underlying criteria that guided the design are presented. The technological factors, such as compatibility, corrosion resistance, and irradiation behavior, which led to the selection of U/ sub 3/O/sub 8/ as the fissile compound and aluminum as the cladding and matrix material, are reviewed. The fabric… more
Date: October 21, 1963
Creator: Kucera, W. J.; Leitten, C. F. Jr. & Beaver, R. J.
Partner: UNT Libraries Government Documents Department
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EVALUATION OF ULTIMATE DISPOSAL METHODS FOR LIQUID AND SOLID RADIOACTIVE WASTES. PART III. INTERIM STORAGE OF SOLIDIFIED WASTES

Description: The costs of interim storage of solidified Purex and Thorex wastes in water-filled canals were estimated as the third part of a study to evaluate, from the standpoint of econoNonemics and hazards, the various steps leading to and including the permanent disposal of highly radioactive liquid and solid wastes. The wastes were assumed to have been solidified following their production in a plant proccessed 1500 metric tons per year of uranium converter fuel it a burnup of 10,000 Mwd/ton and 270 to… more
Date: October 21, 1963
Creator: Blomeke, J O; Perona, J J; Weeren, H O & Bradshaw, T L
Partner: UNT Libraries Government Documents Department
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PHASE EQUILIBRIA IN THE SYSTEM NaF-UF$sub 4$

Description: No Description Available.
Date: February 21, 1963
Creator: Thoma, R.E.; Insley, H.; Hebert, G.M.; Friedman, H.A. & Weaver, C.F.
Partner: UNT Libraries Government Documents Department
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AN ALGOL 60 SYNTAX CHECKER FOR THE IBM 7090 COMPUTER

Description: A syntax checker was designed based on the syntax of Algol as previously described. It was desirable to design the syntax checker as a set of mutually recursive processors tied together by building blocks which perform certain bookkeeping functions. Because of the recursive nature of the language and of the syntax checker, the problem of recovery after an error required much attention. A method was devised which permits most programs to be checked completely despite errors. The syntax checker w… more
Date: March 21, 1963
Creator: Lietzke, M.P.
Partner: UNT Libraries Government Documents Department
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Effects of Large Neutron Doses and Elevated Temperature on Type 347 Stainless

Description: Tests of subsize tensile and impact specimens of Type 547 stainless steel irradiated in three capsules to fastneutron exposures of up to 1.1 x 10/sup 22/ nvt were conducted. Ductile fractures at impact energies of 65 ft-lb, representing a 35% decrease in impact strength, were noted at room temperature. Impact energies of approximates 20 ft-lb and a fracture with both brittle and ductile characteristics were observed at -300 deg F. Irradiation-induced property changes included increases in yield… more
Date: January 21, 1963
Creator: Murr, W. E.; Shober, F. R.; Lieberman, R. & Dickerson, R. F.
Partner: UNT Libraries Government Documents Department
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Nucleon-Meson Cascade Calculations: Shielding Against an 800-Mev Proton Beam

Description: Nucleon-meson cascade calculations were carried out and the dose as a function of depth was obtained for an 800-Mev proton beam incident on a shield. The physical properties used for the shielding medium are only a rough approximation to the properties of any particular medium. Muon, neutron, pion, and proton dose rates and fluxes are listed. (auth)
Date: February 21, 1963
Creator: Alsmiller, R. G., Jr. & Murphy, J. E.
Partner: UNT Libraries Government Documents Department
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HYDROLYSIS OF URANIUM CARBIDES BETWEEN 25 AND 100 . II. AS-CAST ALLOYS CONTAINING 2 TO 10 WT % CARBON

Description: Reactions with water of as-cast uranium-carbon alloys containing 2to 10 wt% carbon (UC/sub 0.4/ to UC/sub 2.2/) were investigated by using gas- chromatography for analysis of the gaseous products. Uranium metal-uranium monocarbide alloys yielded 2 moles of free hydrogen per mole of free metal, in addition to methane, small quantities of higher molecular weight gaseous hydrocarbons, and a solid, hydrous, tetravalent uranium oxide. The gaseous producte contained all the carbon originally present … more
Date: January 21, 1963
Creator: Bradley, M.J. & Ferris, L.M.
Partner: UNT Libraries Government Documents Department
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Nucleon-Meson Cascade Calculations: The Star Density Produced by a 24-Gev Proton Beam in Heavy Concrete

Description: The nuclear star density produced by a 24-Bev proton beam in a material having approximately the properties of heavy concrete is calculated. A comparison is made with experimental measurements made at CERN; but, since the quantity that can be calculated is not the same as that measured, no firm conclusions can be drawn. Proton, neutron, pion, and muon intensities are plotted vs. distance as are star densities. (auth)
Date: January 21, 1963
Creator: Alsmiller, R. G., Jr. & Murphy, J. E.
Partner: UNT Libraries Government Documents Department
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Survey of Recent Developments in Solvent Extraction With Tributyl Phosphate

Description: Tributyl phosphate can be used for extraction in processing all current power reactor fuels. Nitric acid is the only salting agent required. Typical flowsheets are presented. In aluminum nitrate systems which are more than 0.1 M acid deficient, the uranium distribution coefficient is a function of pH and independent of aluminum concentration; the coefficient remains constant at one in fluoride systems when the nitrate to fluoride ratio is approximates 3.5. Many objectionable properties of degra… more
Date: March 21, 1963
Creator: Blanco, R. E.; Blake, C. A., Jr.; Davis, W. Jr. & Rainey, R.H.
Partner: UNT Libraries Government Documents Department
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