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Kinetics of the Alkylation and Acylation of Nickel Dipivaloyimethide

Description: Abstract: A study was made of the reactions of nickel dipivaloyimethide with the following reagents: tirphenylmethyl chloride, benzoyl chloride, [rho]-chloro and [rho]-methyl benzoyl chloride. Infrared spectra of the easily hydrolyzed product of tritylation seem to indicate that enol ether, the product of O-alkylation, is formed. the acyl halides reactor to give the triketones. the latter have been characterized by spectra and C, H, analysis. the kinetics of all the reactions studied were found to settle down to a second order rate law after a fast initial reaction. These reactions are catalyzed by an impurity in the acyl chloride. Then benzoyl chloride with a different purity was used, the second order rate constant for the benzoylation of nickel DPM ranged from 0.02-0.20. The air oxidation of nickel dipivaloymethide was found to compete with the acylations under the conditions of these studies. An investigation of the phenomenon showed that nickel pivalate is the major product. Pivalic acid was also detected in the product mixture. This oxidation takes place in chlorobenzene and in aromatic hydrocarbons. It occurs in 1201 when small amount on benzoyl chlorides are present.
Date: July 1959
Creator: Johnson, Kenneth Eugene & Hammond, George Simms, 1921-2005
Partner: UNT Libraries Government Documents Department
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Radioactive particles in the 234-5 Building ventilation exhaust

Description: The 234-5 Building ventilation exhaust is continuously sampled for the purpose of estimating the amount of radioactive (alpha emitting) material discharged to the atmosphere. Although a record is kept of the gross amount of radioactive material discharged, few data are available concerning the size and kind of active particles in the exhaust air. Knowledge of the particle size permits: (1) an estimate of the validity of samples drawn through the sampling system, (2) a better knowledge of what the active particle ground deposition pattern might be, and (3) may provide information relating to filter performance. The kind of radioactive material discharged is important in determining relative health hazards. The object of this work was to determine the size and kind of radioactive particles in the 234-5 Building ventilation exhaust. A secondary objective was to review present routine sampling of the stream with particular regard to the particulates to be sampled.
Date: July 13, 1959
Creator: Postma, A. K. & Schwendiman, L. C.
Partner: UNT Libraries Government Documents Department
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The Palmolive cycle at Hanford

Description: The Palmolive program is directed toward the recovery of neptunium-237 and production of plutonium-238. The neptunium is recovered during the chemical processing of irradiated uranium and is purified and fabricated into target elements. The target elements are irradiated to produce plutonium-238 by neutron capture of neptunium-237 and are processed to provide plutonium for shipment to the final customer and neptunium for recycle within the system. This report summarizes a preliminary engineering study of the technical and economic factors involved in installing long-term Palmolive manufacturing facilities at Hanford to meet the reduced production goals. Prime emphasis is placed on the process technology and plant equipment requirements for fabricating and reprocessing neptunium target elements on a production basis. The relationships of these phases of the target cycle to the recovery and purification of virgin neptunium in the Purex Plant and irradiation of target elements in the Hanford reactors are reviewed in the light of the reduced plutonium-238 demands.
Date: July 10, 1959
Creator: Beard, S. J. & Judson, B. F.
Partner: UNT Libraries Government Documents Department
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Specifications for Critical Mass Control Redox Plant - E-metal

Description: The specifications given in this document cover the processing of E-Metal. E-Metal is defined as natural uranium which has been enriched with U-235 to a concentration of 0.95 percent. The higher U-235 content makes the E-Metal more reactive than either natural or irradiated natural uranium. This difference in reactivity places a definite limit on the amount of massive metal that can be charged to the present Redox dissolvers. Once the slugs have been dissolved, the processing of E-Metal is essentially the same as the processing of natural uranium. Thus, except for the dissolver charge size, the following specifications reflect few actual changes in numerical limits. One change that needs to be recognized is that the amount of U-235 plus plutonium in the metal solution is much closer to the maximum {open_quotes}always safe{close_quotes} ratio than with irradiated natural uranium. Once the E-Metal uranium has been separated from its accompanying plutonium, no critical mass of uranium can be assembled because the enrichment is below the minimum critical.
Date: July 1, 1959
Creator: Harmon, M. K.
Partner: UNT Libraries Government Documents Department
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Proposed projection fuel testing program 2

Description: Sufficient changes in the original projection fuel testing schedule have occurred to make the original schedules confusing. It is the intent of this document to revise an up-date those schedules so as to be a more realistic guide for associated development programs.
Date: July 27, 1959
Creator: Callen, A. C.
Partner: UNT Libraries Government Documents Department
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Operational physics comments on fuel pile operational charge-discharge

Description: This document has been written in part to answer questions concerning the feasibility and advisability of ``quickie`` discharge of ruptures at C Reactor. Justification of full pile operational charge-discharge (OC-D) is based in part on outage savings resulting from improved, rupture removal. Since a portion of the rupture removals might be accomplished within the scram recovery time (quickie) it is necessary to consider recovery time as a function of anticipated future power levels. In addition to answering the questions mentioned above, it was felt worthwhile at this time to discuss equilibrium control problems associated with OC-D which have been apparent during operation of prototype equipment, and on the basis of this information to consider reactor control with full pile OC-D.
Date: July 15, 1959
Creator: Carter, R. D. & Ferguson, R. L.
Partner: UNT Libraries Government Documents Department
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The Hard-Core Pinch. I

Description: This report analyzes a linear, hard-core pinch tube built to examine tubes afflicted by small-scale instabilities evident from many observations.
Date: July 31, 1959
Creator: Birdsall, D. H.; Colgate, Stirling A. & Furth, Harold P.
Partner: UNT Libraries Government Documents Department
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The Hard-Core Pinch. II

Description: This report describes a toroidal version of the hard-core pinch and the additional information it can obtain to what the analogous linear pinch can get.
Date: July 31, 1959
Creator: Birdsall, D. H.; Colgate, Stirling A. & Furth, Harold P.
Partner: UNT Libraries Government Documents Department
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Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report

Description: From preface: This report covers Phase I of the authorized work, consisting of determination of the specific reactor concept and size for the most economic reactor, preparation of a reference design of the most promising concept and estimated capital and generating costs, evaluation of the variations in cost as a function of unit size, and evaluation of the reductions in ultimate costs for a power station having multiple units of the same type.
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
Partner: UNT Libraries Government Documents Department
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Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant

Description: "This study is one of four initiated in 1958 by the Division of Reactor Development, U.S. Atomic Energy Commission, to assess the feasibility of power generation through the use of certain types of nuclear reactors. These studies are available from the Office of Technical Services, U.S. Department of Commerce, Washington 25, D.C."
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
Partner: UNT Libraries Government Documents Department
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Boiling Water Reactor Study [Part 1]: 306 Mw Power Reactor Conceptual Design

Description: From introduction: In general, the objective of this study is to provide for the development of the conceptual design criteria for the most promising type of boiling water reactor and associated complete electrical generating plant consistent with a schedule calling for start of construction in July 1960.
Date: July 1959
Creator: Ebasco Services Incorporated
Partner: UNT Libraries Government Documents Department
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Boiling Water Reactor Study [Part 2]: Separate Studies

Description: From introduction: This section presents the principal results of the optimization study done to establish the economic basis for selection of the core and fuel design.
Date: July 1959
Creator: Ebasco Services Incorporated
Partner: UNT Libraries Government Documents Department
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Boiling Water Reactor Study [Part 3]: 306 Mw Coal-Fired Installation

Description: From introduction: The objectives of this study are to determine the estimated capital and energy costs of this typical conventional coal-fired installation, consistent with a schedule calling for completion of construction April 1964.
Date: July 1959
Creator: Ebasco Services Incorporated
Partner: UNT Libraries Government Documents Department
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Organic Cooled Reactor Study [Part 3]: Reactor Concept Evaluation

Description: From summary and conclusions: The purpose of this volume is to present the results of design studies to select the optimum-sized electric power station utilizing an organic cooled nuclear reactor and to evaluate and optimize the various reactor concepts, with special attention to selection of the moderator, consistent with the basic design criteria established by the AEC.
Date: July 1959
Creator: Bechtel Corporation
Partner: UNT Libraries Government Documents Department
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The control of beryllium hazards

Description: From abstract: "The toxicological properties of beryllium and compounds of beryllium are briefly reviewed, together with the historical development of the recommendations for maximum permissible beryllium air concentrations. The application of the enclosure technique presently in use at this laboratory for the control of beryllium hazards is described... Monitoring procedures used to evaluate the performance of enclosures are discussed."
Date: July 15, 1959
Creator: Lindeken, Carl L. & Meadors, Orville L.
Partner: UNT Libraries Government Documents Department
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Electron-Population Analysis and the Dipole Moment of the LiH ¹Σ⁺ Excited State / A.M. Karo

Description: Abstract: "Detailed consideration is given to some properties of the first excited electronic state. Following the analysis proposed bv Mulliken, SCF LCAO-MO coefficients are used to obtain qualitative information about the electron distributions. Comparison is made with earlier work with respect to the description of the excited-state dipole moment, the effective electric moment between the ground and excited states is also calculated. From this, the oscillator strength for the first allowed transition is computed as a function of the internuclear distance."
Date: July 1959
Creator: Karo, Arnold M.
Partner: UNT Libraries Government Documents Department
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Thermodynamics of Irreversible Processes: The Experimental Verification of the Onsager Reciprocal Relations

Description: Report discussing theories of irreversible thermodynamic processes. "The purpose of this review is to collect the presently available experimental data for a variety of quite different irreversible phenomena and to show that this evidence does indeed verify the Onsager Reciprocal Relations."
Date: July 30, 1959
Creator: Miller, Donald Gabriel
Partner: UNT Libraries Government Documents Department
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CGI-844: 100-K coolant back-up system scope requirements

Description: Several decisions regarding basic project philosophy must be made in order to proceed with scope design and the preparation of equipment procurement specifcations. The purpose of this document is to present as much pertinent data as possible to allow the project representatives to become familiar with the problems involved. A meeting of Representatives is planned for the near future after receipt of project authorization to discuss the scope of this project and its relationship to CG-775. Emergency flow requirements of the K reactors for planned future power levels is approximately 32,000 gpm within 68 sec. A detailed study of the existing high-pressure cross-tie line reveals that a duplicate cross-tie line and five low lift pump operation would be required to provide this flow. The existing emergency generation capacity is not adequate to supply five low lift pumps and all other necessary emergency electrical loads. A possible solution to adequate emergency flows is to connect the proposed steam turbine pump directly to the risers and to consider the turbine pump as the last ditch system. If it is determined that this does not meet the criteria of separate systems, then an alternate solution must be found.
Date: July 28, 1959
Creator: Watson, D. F.
Partner: UNT Libraries Government Documents Department
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Shutdown heat exchangers

Description: Typical transient temperature curves for the reactor outlet coolant have been obtained for the cooldown period. Additional curves showing the relationship of several variables on the required heat exchanger area were obtained.
Date: July 30, 1959
Creator: Condotta, D. L.
Partner: UNT Libraries Government Documents Department
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