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1. K+ Charge Exchange - Search For K+ Charge Exchange

Description: An experiment was designed utilizing a charge-exchange reaction to study the decay and interactions of the neutral K mesons produced. The experiment produced no events that could be interpreted as either the decay or interaction of neutral K mesons. The nature of the experiment and the possible explanations of this unexpected result are presented in this paper.
Date: July 29, 1959
Creator: Birge, Robert W.; Courant, Hans J.; Lanou, Robert E., Jr. & Whitehead, Marian N.
Partner: UNT Libraries Government Documents Department
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105-N charge-discharge rates

Description: Figures have and can be generated that indicate a higher charge-discharge rate if required before 105-N will be comparable with existing reactors. Also, these figures show an apparent operating cost incentive to increase the charge-discharge rates proposed for 105-N. Although these figures may be true by themselves, other figures developed from the same information and stated on a basis that affords a true comparison, show that the proposed rates for 105-N are compatible with those in existing reactors. However, the accomplishments of existing reactors should be considered as a guide only and not as Criteria since the design basis has already been established for Project CAI-816. An average charge-discharge rate has been proposed for 105-N that is compatible with the two main ground rules of the Project. Namely, the capital cost limitation and the plant factor. This rate of 8 tubes/hr. is one that appears to be reasonable from the charge-discharge design aspects and there is a good possibility that it can be increased with operational experience.
Date: July 2, 1959
Creator: Nesbitt, J. F.
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

[Advertisement for Richardson Coiffures]

Description: Photograph of a slide advertising the beauty shop Richardson Coiffures. The background of the slide is an image of the building where the shop is located which is two stories. The building is brick with a Spanish tile roof and there are three brick pillars in the center of the image. Between these pillars are intricate metal railings on the second story and there are windows for the shops set between the pillars on both floors. In between the pillars on the first floor, there is a white rectangle with black text in it that reads "Richardson Coiffures 3313 Winthrop Ridglea". The slide is pinned to a black board.
Date: July 6, 1959
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections

[Aisles 10 and 11 in Hills Store]

Description: Photograph of an aisle at the Hills Store. The shelves of this aisle are stocked full of can food, with brands such as Honey Boy, Campbell's, Hunts, and Eat Well. Above the shelves on the left is a sign that reads "10 Canned Juices Tomato Juice Canned Fruits" and to the left of this is a sign for the other side of these shelves that reads "9 Canned Tomatoes Canned Beans Canned Corn". In the middle of the signs between the 9 and 10 is a sign that says "Serve Coca-Cola at Home". Above the shelves on the right of the image is a sign that reads "11 Meat Sauces Canned Meats Canned Fish" and to the right of this a sign for aisle 12 is visible. The end cap of aisle 11 has plant food and pest killer on it while there are stacks of Good Rich cans on the end cap of aisle 10. At the end of this aisle, shelves that are lining the wall are visible and these have bottles of syrup on them with boxes of Ball jars stacked on top of the shelves.
Date: July 11, 1959
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
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ANALYSIS OF SELF-SHUTDOWN BEHAVIOR IN THE SPERT I REACTOR

Description: Presented at the 1958 Winter Meeting of the American Nuclear Society, December 9, 1958. Experimental and theoretical work on the selflimiting response of reactors to step and ramp insertions of reactivity is discussed along with the general characteristics of self-limiting power bursts. The static characteristics of the cores investigated are presented and the techniques of measurement are discussed. Data from step and ramp tests are presented and compared with the predictions of a theoretical formulation of reactor self- shutdown in terms of energy release. The discussion includes an evaluation of some postulated shutdown mechanisms in the light of experimental results. Some results of detailed calculations of shutdown effects due to specific mechanisms which are believed to contribute significantly to reactor self-shutdown are presented. (auth)
Date: July 23, 1959
Creator: Forbes, S. G.; Bentzen, F. L.; French, P.; Grund, J. E.; Haire, J. C.; Nyer, W. E. et al.
Partner: UNT Libraries Government Documents Department
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ANNUAL REPORT

Description: The national laboratory concept, laboratory objectives, the staff, research facilities. research activities, and administration are discussed in general terms and a financial statement is given. Fairly detailed accounts are given for the research programs in the fields of physics, accelerator development, instrumentation, applied mathematics, chemistry, nuclear engineering, biology, and medicine. (W.D.M.)
Date: July 1, 1959
Partner: UNT Libraries Government Documents Department
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An Application of Spencer's Method to the Stieltjes and Hamburger Moment Problems

Description: Given the moments of a function it is often desirable to obtain a numerical approximation of the function. A method for estimating the solutions of the Stieltjes and Hamburger moment problems is developed. Calculations indicate that the method is both feasible and accurate. (auth)
Date: July 1, 1959
Creator: Guilinger, W. H.
Partner: UNT Libraries Government Documents Department

[Attendees at P.G.W. Convention in dining room]

Description: Photograph of a group of conference attendees at the P.G.W. Convention. Individuals in the photo appear to be engaging in conversation and preparing to eat a meal. On the back wall, there is a pull-down projection screen.
Date: July 8, 1959
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections

[B.G.P. modern house]

Description: Photograph of a B.G.P. modern house. The house has wood siding, white window paneling, and a brick chimney. The doors are also white, and there are various small trees in the front yard. Other larger trees are shown behind the house. A driveway is partially visible on the right side of the image.
Date: July 10, 1959
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
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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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Centrifugal Casting of Aluminum-Uranium Alloys

Description: "Centrifugal-casting techniques were investigated as a method of producing hollow cylindrical extrusion billets of aluminum-35 w/o uranium. Among the variables evaluated were melt temperature, mold and pouring-spout configurations, mold speed, and method of pouring. With the equipment employed it was found that the best castings were produced stilizing a pouring temperature of 2400 F, a heavy-walled steel cylinder rotating between 700 to 900 rpm for the mold and bottom-pouring technique employing a retractable pouring spout. Sound, nonporous billets 26 in. long and 5 in. in diameter were produced with a yield after machining of over 75 per cent of the original charge. The major losses occurred in the pouring spout-and-cup assembly. This loss is relatively unaffected by the casting length; and, therefore, coatings of greater length than 26 in. should results in even greater recoveries.
Date: July 20, 1959
Creator: Daniel, Norman E.; Foster, Ellis L. & Dickerson, Ronald F.
Partner: UNT Libraries Government Documents Department
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CENTRIFUGAL CASTING OF ALUMINUM-URANIUM ALLOYS

Description: Centrifugal-casting techniques were investigated as a method of producing hollow cylindrical extrusion billets of aluminum-35 wt.% uranium. Among the variables evaluated were melt temperature, mold and pouring-spout configurations, mold speed, and method of pouring. With the equipment employed it was found that the best castings were produced utilizing a pouring temperature of 2400 ction prod- , a heavy-walled steel cylinder rotating between 700 and 900 rpm for the mold and a bottom-pouring technique employing a retractable pouring spout. Sound, nonporous billets 26 in. long and 5 in. in diameter were produced with a yield after machining of over 75% of the original charge. The major losses occurred in the pouring spout-and-cup asserably. This loss is relatively unaffected by the casting length; and, therefore, castings of greater length than 26 in. should result in even greater recoveries. (auth)
Date: July 20, 1959
Creator: Daniel, N.E.; Foster, E.L. Jr. & Dickerson, R.F.
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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The Chattanooga Shale of Tennessee as a Source of Uranium: Final Report

Description: From major objective: The over-all aim of the study has been to obtain a thorough geologic picture of the Chattanooga shale in the area under consideration, with emphasis upon stratigraphic relationships and associated special problems from which, in turn, implications may be obtained as to the origin and age of the formation and possibly the source of the uranium. The study has not been aimed primarily at exploration for uranium and its economic aspects.
Date: July 1, 1959
Creator: Stockdale, Paris B. & Klepser, Harry J.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, June 1959

Description: Production of Pu from separations plants and output of unfabricated Pu exceeded commitments. Purex plant set a new record high for U processed. Production and shipments of UO{sub 3} met schedules. Purex solvent extraction battery performed below normal, probably because of poor solvent quality. NaOH addition to Redox coating removal waste is being reduced. A 3fold improvement in Recuplex product Al impurity was achieved by means of a specific gravity difference > 0.15 between dilute aqueous feed and extractant. Sintered, high-silica crucibles are being tested in RMA production line in Finished Products Operation. Scope design of a fission product shipping cask was completed; powder temperature should be below 440 F for 1 MCi cerium-144 + impurities. Feasibility of using one outside Purex canyon entrance (stairwell opening) for relief damper opening was tested and found to be insufficient. A drawing of the 6-inch continuous centrifuge being evaluated as a vacuum drum filter on RMA button line was reviewed. Casks were designed for the NPR project. (DLC)
Date: July 22, 1959
Creator: MacCready, W. K.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report for April 1959

Description: A concentration cell electrode was installed in a fritted glass surface and was used to measure the surface KCl concentration while water was being transpired through the surface into a mixed tank of 0.1 M KCl. The results from the first Fluorox run made with crude UF/sub 4/ showed that 85.3% of the theoretical amount of UF/sub 6/ was accounted for, with 17.9% being collected in cold traps and the remainder being consumed in various side reactions. Installation was completed of apparatus to study the electrolytic removal of nickel on an engineering scale from concentrated HRT fuel solution. An extremely low yield stress of 0.02 lb/sq ft was measured for a thoria-urania slurry containing 2.5 wt.% Al/sub 2/O/sub 3/ and spherical particles of 1.7 micron mean diameter. Preliminary data on the rate of uranium sorption on Dowex 21K from sulfate solutions were correlated with a simple spherical diffusion model. Laboratory scale studies to determine the effect of reflux time, HNO/sub 3/ concentration, and air sparge on chloride removal from APPR-type Darex dissolver product showed that an air sparge is definitely beneficial in chloride removal. Preliminary cyclic cleaning tests showed that boiling 25% caustic solution was adequate for cleaning type F (20 micron) porous metal filter elements fouled in the absence of filter aid with siliceous sludge from Darex solvent extraction feed solutions. Sections of unirradiated stainless steel-clad UO/sub 2/, sheared into lengths of 1/2 in., 1 in., 2 in., and 2 3/4 in., were leached free of UO/sub 2/ with 10 M HNO/sub 3/ in 30, 45, 60, and 75 min, respectively. The abrasive blade cost for the removal of inert end adapters from selected reactor assemblies ranges from 12 for the Gas-Cooled Reactor to 19 for Consolidated Edison. A zirconium dissolution was carried to completion at 600 ction prod- …
Date: July 21, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Partner: UNT Libraries Government Documents Department
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