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Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design

Description: Preface: The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary … more
Date: February 28, 1959
Creator: Alco Products (Firm)
Partner: UNT Libraries Government Documents Department
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PROBLEMS IN ACCOUNTABILITY MEASUREMENTS ASSOCIATED WITH THE INTERIM CHEMICAL PROCESSING PROGRAM

Description: Available knowledge of precision limits in S.S. accountability measurements and/or calculations by reactor and chemical processing groups is surveyed and summarized. Experienee in comparisons of reactor (production and research) calculations vs. chemical plant accountability measurements is also reported. A general tentative conclusion is that available precisions ( plus or minus 0.54 to plus or minus 0.78%) in chemical plant measurements (bulk and analytical) for fissionable material accountab… more
Date: May 28, 1959
Creator: Arnold, E D & Gresky, A T
Partner: UNT Libraries Government Documents Department
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Problems in Accountability Measurements Associated with the Interim Chemical Processing Program

Description: Available knowledge of precision limits in S.S. accountability measurements and/or calculations by reactor and chemical processing groups is surveyed and summarizes. Experience in comparisons of reactor (production and research) calculations versus chemical plant accountability measurements is also reported. A general tentative conclusion is that available precisions (+/- 0.54 to +/- 0.78% ) in chemical plant measurements is also reported. A general tentative conclusion is that available precis… more
Date: May 28, 1959
Creator: Arnold, E. D. & Gresky, A. T.
Partner: UNT Libraries Government Documents Department
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AN EVALUATION OF THE PROPERTIES AND BEHAVIOR OF ZIRCONIUM-URANIUM ALLOYS

Description: Data from a survey of the literature and other available information on zirconium--uranium alloys have been reviewed for the purpose of obtaining a coherent picture of current knowledge about the properties and behavior of zirconium--uranium alloys. The results of the survey were used to revise and extend the presentation of material gathered earlier in a similar study and reported in BMI1030 in August 1955. The constitution of zirconium-uranium alloys is discussed, and a constitutional diagram… more
Date: September 28, 1959
Creator: Bauer, A.A. ed.
Partner: UNT Libraries Government Documents Department
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Isotope Separation and Isotope Exchange. A Bibliography With Abstracts

Description: The unclassified literature covering 2498 reports from 1907 through 1957 has been searched for isotopic exchange and isotepic separation reactions involving U and the lighter elements of the periodic chart through atomic number 30. From 1953 to 1957, all elements were included Numerous references to isotope properties, isotopic ratios, and kinetic isotope effects were included. This is a complete revision of TID-3036 (Revised) issued June 4, 1954. An author index is included. (auth)
Date: October 28, 1959
Creator: Begun, G. M.
Partner: UNT Libraries Government Documents Department
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Radioactive Waste Treatment and Disposal -- a Bibliography of Unclassified Literature, Part 3

Description: This bibliography of the unclassified literature on radioactive waste treatment and disposal has been compiled from references published in the Nuclear Science Abstracts, volume 12, no. 13 (July 15, 1958) through volume 13, no. 14 (July 31, 1959). This bibliography brings up-to-date previous bibliographies published as CF-57-8-118 and CF-58-7-77.
Date: September 28, 1959
Creator: Blomeke, J. O.
Partner: UNT Libraries Government Documents Department
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Waste Treatment and Disposal Problems of the Future Nuclear Power Industry

Description: The elements of waste treatment and disposal are assessed which are expected to become important in the development of the nuclear power industry of the future. Growth of the nuclear power economy is considered along with composition and quantities of anticipated waste. In addition, the economic implications of waste disposal are considered. It is concluded that research should be concentrated on decontaminating off-gases and on conversion of wastes to a more suitable form than liquid for stora… more
Date: January 28, 1959
Creator: Bruce, F.R.
Partner: UNT Libraries Government Documents Department
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Waste Treatment and Disposal Problems of the Future Nuclear Power Industry

Description: The elements of waste treatment and disposal are assessed which are expected to become important in the development of the nuclear power industry of the future. Growth of the nuclear power economy is considered along with composition and quantities of anticipated waste. In addition the economic implications of waste disposal are considered. It is concluded that research should be concentrated on decontaminating off gases and on conversion of wastes to a more suitable form than liquid for storag… more
Date: January 28, 1959
Creator: Bruce, Francis Robert, 1919-
Partner: UNT Libraries Government Documents Department
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Increased production from deliberate discharge cycling

Description: Considerable production gains might be attained if each reactor discharged its entire flattened region during one scheduled outage instead of utilizing several outages for this purpose. Several of the older reactors are now discharging a high percentage of their flattened zones in a single outage and could be put into this type of operation with relatively little difficulty. Production gains may be possible through better flattening efficiency, a more favorable rupture rate effect, fewer non-eq… more
Date: May 28, 1959
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
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Toy Top Plasma Injector

Description: Introduction: "It is the purpose of this note to describe the construction and operation of the plasma injectors used in the magnetic high compression experiments in progress at the Lawrence Radiation Laboratory at Livermore. As the investigations of these injections is still in progress, remarks concerning their operation or the characteristics of the injected plasma are of a tentative nature."
Date: May 28, 1959
Creator: Coensgen, F. H.; Cummins, W. & Sherman, A.
Partner: UNT Libraries Government Documents Department
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Toy Top Plasma Injector

Description: The construction and operation of the plasma injector, Toy Top, used ia the magnetic high compression experements in progess at the Lawrence Radiation Jab. at Livemore are described The essential part of the injector consists of a stack of deuterated titanium washers 3/4 in. O.D. and/2 in. I.D. Details of the construction are sbown (W.D.M.)
Date: May 28, 1959
Creator: Coensgen, F.; Cummins, W. & Sherman, A.
Partner: UNT Libraries Government Documents Department
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Analysis of 100-K emergency water requirements after CGI-844 pump failure

Description: The demand plot has a 5-set, modified pump decay curve; it shows that 20,000 gpm emergency flow would be required within 80 seconds of complete pump power failure. Bases for the demand curve are constant bulk inlet temperature of 2 C, constant bulk outlet temperature of 95 C, K-3 I&E fuel elements, and initial reactor flow of 188,000 gpm.
Date: May 28, 1959
Creator: Corlett, R. F.
Partner: UNT Libraries Government Documents Department
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THE HGCR-1, A DESIGN STUDY OF A NUCLEAR POWER STATION EMPLOYING A HIGH- TEMPERATURE GAS-COOLED REACTOR WITH GRAPHITE-UO$sub 2$ FUEL ELEMENTS

Description: The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO/sub 2/ fuel appear to be less than 0.2% of thos… more
Date: July 28, 1959
Creator: Cottrell, W. B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
Partner: UNT Libraries Government Documents Department
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STATUS REVIEW OF THE KEWB PROGRAM

Description: jectives, the accomplishments, and a summary of the work outstanding. The obtectives of the experimental and analytical studies were to investigate and reach an understanding of the kinetic behavior of aqueous homogeneous reactors. Information produced by the program, experiments on the spherical core, capsule experiments, and the remaining work schedule are discussed. (W.D.M.)
Date: January 28, 1959
Creator: Flora, J. W.
Partner: UNT Libraries Government Documents Department
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A Radiofrequency Separator For High-Energy Particles

Description: This report is an outgrowth of the MURA Users' Conference of June 1959. At that conference the group on beam separators discussed the problem of whether particle separation could be achieved at the machine energies under consideration. A preliminary version of the scheme outlined here was given at the conference. Later, after flaws were discovered, it was modified. The attempt is not to show that this is the way it should be done, but to show with reasonable certainty that there is at least one… more
Date: October 28, 1959
Creator: Good, Myron L.
Partner: UNT Libraries Government Documents Department
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High Temperature Corrosion Study Interim Report for the Period November 1958 Through May 1959

Description: Samples of grade A Monel snd grade A nickel were subjected statically in a single reactor to an undiluted atmosphere of gaseous fluorine at pressures up to one atmosphere absolute and temperatures up to 1500 deg F. The grade A Monel was conservatively estimated to have consumed at least 40 times as much fluorine as grade A nickel during the entire period of the investigation. Samples of fused alpha Al/sub 2/O/sub 3/, alpha -Al/sub 2/O/sub 3/- MgO spinel, and alpha -Al/sub 2/O/sub 3/-NiO--nickel… more
Date: July 28, 1959
Creator: Hale, C. F.; Barber, E. J.; Bernhardt, H. A. & Rapp, K. E.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-280-A-FP: Irradiation of alloyed dingot uranium fuel elements

Description: Objective of this test is to authorize irradiation of alloyed, low hydrogen dingot uranium fuel elements on a pilot scale, and to monitor their performance. Initially, 25 tons per month of alloyed, low hydrogen dingot material will be charged for two months. Measured charges will be loaded with the initial 25 tons to monitor the stability of this material. Following a two-month delay in the monitor charging, and if the dingot meets all specifications, routine charging of quantities up to 60 ton… more
Date: August 28, 1959
Creator: Hall, R. E. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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Reduction of Radioactive Waste to Solids for Ultimate Storage

Description: A procedure is presented for processing high level radioactive wastes. The steps are: pot calcination of acid and neutral waste followed by separation by distillation of the fission products from effluent liquid and gaseous streams. The fission products would be recycled to the calcination pot. After calcination, the pot contents would be stored in a controlled area for cooling and accountability.
Date: January 28, 1959
Creator: Hancher, C. W.
Partner: UNT Libraries Government Documents Department
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Calculation of Effective Resonance Integrals

Description: Effective resonance integrals for fuel and fertile materials were calculated as a function of materials concentration in homogeneous media. For the fissile materials (U-235, Pu-239), results were obtained from multigroup, monte-carlo, and statistical model calculations. For the fertile materials (U-238), results were obtained from monte-carlo and multigroup calculations and were compared with experimental results.
Date: August 28, 1959
Creator: Jaye, S.
Partner: UNT Libraries Government Documents Department
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