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INTERACTION OF TWO METAL SLABS OF PLUTONIUM IN PLEXIGLAS

Description: Neutron multiplication measurements were performed on two identical finite Pu-metal slab assemblies separated and reflected by plexiglas. (auth)
Date: December 28, 1959
Creator: Schuske, C.L.; Goodwin, A. Jr.; Bidinger, G.H. & Smith, D.F.
Partner: UNT Libraries Government Documents Department
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Net return course - operational severity index formuli

Description: This document presents a nomograph from which the relationship between reactor operating parameters, tube power, and outlet temperature can be correlated with rupture rate. The index indicates the severity of the reactor climate during irradiation and does not include the metal quality parameters defined in the rupture rate equation. The general form of the Operational Severity Index Equation is OSI=P{sup 3.3}/1000{times}t{sub 0}{sup 8.7}/100, where OSI, is the unitless Operational Severity Ind… more
Date: December 28, 1959
Partner: UNT Libraries Government Documents Department
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Geologic Studies of Underground Nuclear Explosions Rainier and Neptune. Final Report

Description: The approximate physical distribution and condition of displaced and ruptured rock materials in the Rainier and Neptune areas were established by geologic observation of structural and lithologic details, and stratigraphic correlations. The effects of the detonations were found to be related to the rock types considered from the standpoint of engineering materials as well as to their structural positioning. Gross displacements and fracturing are in apparent accord with Mohr theory of rupture st… more
Date: October 28, 1959
Creator: Thompson, T. L. & Misz, J. B.
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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Neutron Age in Graphite-Water Lattices.

Description: The Fermi age of thermal neutrons in a lattice containing both water and graphite in some sort of weighted average of the age in water and in graphite independently, with correction for volumes of non-moderating elements or voids. The correct weighting function has been in question during design calculations for the NPR. This paper presents a very simple and direct approach to the problem, resulting in a weighting equation which seems to be theoretically sound. Unfortunately, simple theories ca… more
Date: October 28, 1959
Creator: Simpson, D. E.
Partner: UNT Libraries Government Documents Department
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PRELIMINARY EVALUATION OF A PROPOSED FUEL MATERIAL FOR HIGH TEMPERATURE REACTORS

Description: Results are reported for preliminary experiments to determine the stability of solid solutions of UO/sub 2/ and ThO/sub 2/ in air at temperatures of 2500 deg F and above. The results are compared with those obtained by workers at Argonne during development work on the Borax IV experimental breeder reactor. It is concluded that further evaluation of the system at temperatures above 2500 deg F is required. (auth)
Date: October 28, 1959
Creator: Juenke, E.F.
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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A Study of Problems Associated With Release of Fission Products From Ceramic Fuels in Gas-Cooled Reactors

Description: The diffusion of fission products out of the fuel elements leads to increased shielding requirements, a greater hazard due to their possible release to the surroundings, and more difficult maintenance problems. Continuous processing of the contaminated coolant may alleviate the hazard and maintenance problems; however, extensive in-pile loop experiments are needed for a quantitative evaluation of methods. By proper design of major components such as heat exchangers and blowers, direct maintenan… more
Date: October 28, 1959
Creator: Lane, J. A.; Bennett, L. L.; Culver, H. N.; King, L. J.; Sanders, J. P.; Scott, J. L. et al.
Partner: UNT Libraries Government Documents Department
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Automatic Reader for Air-Monitoring Filter Paper

Description: An automatic reader was developed for scanning 4 x 9in. filter papers from systems that monitor particulate airborne activity. Paper tape shows alpha and betagamma activities, together with counting times and identifying data, for any samples exceeding a predetermined value a special indicator mark is added. (auth)
Date: September 28, 1959
Creator: Thaxter, M. D. & Taussig, Thomas
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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Construction Materials for Various Head-End Processes for the Aqueous Reprocessing of Spent Fuel Elements

Description: Materials of construction were evaluated for use in critical areas of head-end processes for the aqueous reprocessing of spent nuclear fuel elements. The SulfexThorex, Darex-Thorex, Darex, Zirflex, and Zircex processes were considered. The effect of varying heat treatments on the resistance of the materials was also evaluated. Dissolution of unirradiated fuel pins was carried out in vessels of promising materials. The corrosion rate of Ni-o-nel was about 5 mils per month during actual fuel-pin … more
Date: August 28, 1959
Creator: Peterson, C. L.; Miller, P. D.; Jackson, J. D. & Fink, F. W.
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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GAS-PRESSURE BONDING OF ZIRCALOY-CLAD FLAT-PLATE URANIUM DIOXIDE FUEL ELEMENTS

Description: A solid-state bonding technique involving the use of gas pressure at elevated temperatures was investigated for the preparation of compartmented Zircaloy-clad flat-plate uranium dioxide fuel elements. These investigations involved development of methods for the surface preparation and assembly of fuel- element components for bonding, determination of optimum bonding parameters, development of barrier coatings for uranium dioxide to prevent reaction with Zircaloy, and extensive testing and evalu… more
Date: August 28, 1959
Creator: Paprocki, Stan J.; Hodge, Edwin S.; Carmichael, Donald C. & Gripshover, Paul J.
Partner: UNT Libraries Government Documents Department
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OXIDE FLUORINATION TOWER

Description: A 3-inch-diameter flame tower for the conversion of uranosic oxide to uranium hexafluoride with elemental fluorine was tested for possible use in the fluorination step of the present uranium recovery process. The oxide was fed from a hopper to the tower by a screw feeder. The fluorine and the oxide entered at the top and flowed concurrently down through the tower. The unreacted or partially reacted oxide was collected in an ash receiver at the bottom. Fine solid particles were removed from the … more
Date: August 28, 1959
Creator: Peoples, L.C.
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. Emerg… more
Date: July 28, 1959
Creator: Watson, D. 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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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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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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DEFUELING THE S2G REACTOR

Description: The defueling of the S2G Reactor which was conducted at the Electric Boat Division, General Dynamics Corporation Groton Connecticut during January 1959, is reported from the viewpoint of the participating personnel from Knolls Atomic Power Laboratory. The sequence of events is outlined, difficulties encountered during the operation are described, and conclusions of possible interest to other naval nuclear reactors are given (auth)
Date: May 28, 1959
Creator: Moore, C.V.
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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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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