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Accidental nuclear excursion Recuplex operation 234-5 facility. Final report: Date of incident: April 7, 1962

Description: On Saturday morning, April 7, 1962, at about 1059 Armed Forces time, an accidental nuclear excursion occurred in the plutonium waste recovery facility (Recuplex) of the 234-5 Building. This excursion did not result in any mechanical damage or spread of contamination. Three employees of the General Electric Company received overexposures to gamma and neutron radiation. None were fatally exposed; in each case the overexposure was recognized promptly, and following medical observation and testing … more
Date: August 1, 1962
Partner: UNT Libraries Government Documents Department
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Aeroradioactivity Survey and Areal Geology of Parts of East-Central New York and West-Central New England (ARMS-I)

Description: Report concerning "[a]n airborne gamma-radiation survey of Connecticut, Rhode Island, and parts of New York, Massachusetts, New Hampshire, and Vermont" (p. 5) made between 1958 and 1960 that indicated that a broad range of radioactivity exists in those areas depending on the type of bedrock. Correlations are drawn between this radioactivity and the geology of the region.
Date: August 1962
Creator: Popenoe, Peter
Partner: UNT Libraries Government Documents Department
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Analytical Studies of Transient Effect in Fast Reactor Fuels: [Part] 1

Description: From abstract: "An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined and possible mechanisms of failure are analyzed."
Date: August 1962
Creator: Osborn, R. B. & Sherer, D. B.
Partner: UNT Libraries Government Documents Department
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Application of Distillation Techniques to Radiochemical Separations

Description: Nuclear Science Series'' of the National Research Council. Committee on Nuclear Science. The use of vacuum distillation of inorganic compounds and metals for radiochemical separations is reviewed. A brief description of the experimental apparatus which is most often used for the distillation is outlined. Advantages and disadvantages of the various techniques are discussed. Detailed separation procedures are described for wet chemical distillation separations as well as for separations of daught… more
Date: August 1, 1962
Creator: DeVoe, J. R.
Partner: UNT Libraries Government Documents Department
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BEAM TRANSPORT. A Selected, Annotated Bibliography

Description: References applicable to the problems of transponting charged particles in the areas external to accelerators are presented. The 891 references cover the period 1949 to 1981, with a few references both prior and subsequent to this period included. Part I is concerned with the more general aspects of electron optics. Part II contains the references that deal more directly with applications to particle accelerators. Arrangement within each pant is by broad subject with cross references listed at … more
Date: August 1, 1962
Creator: Kepple, R.R.
Partner: UNT Libraries Government Documents Department
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Bibliography on Atomic Transition Probabilities

Description: Report presenting a bibliography on atomic transition probabilities. The papers are arranged according to elements and stages of ionization, and the method employed and class of transitions are indicated behind each reference. Only articles on discrete transitions, both permitted and forbidden, are listed. Also included is a supplementary list of papers dealing with transition probabilities from a general point of view, a table showing the availability of numerical material on the individual at… more
Date: August 1, 1962
Creator: Glennon, B. M. & Wiese, W. L.
Partner: UNT Libraries Government Documents Department
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Boundary Effects in Rotating-Plasma Experiments

Description: The problem of current continuity and viscous drag at the boundaries in rotating-plasma experiments is discussed. A hypothetical model having a steady state with axial symmetry is emphasized; it is shown that the discharge impedance derived from this model does not agree with many observations. The Homopolar III'' experiment is described in which the flux surfaces were strongly convex and parallel to the toroidal-shaped electrodes. In this way friction at the insulators was reduced. But the str… more
Date: August 1, 1962
Creator: Kunkel, W.B.; Baker, W.R.; Bratenahl, A. & Halbach, K.
Partner: UNT Libraries Government Documents Department
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Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

Description: Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.
Date: August 1962
Creator: Hanthorn, H. E.
Partner: UNT Libraries Government Documents Department
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Calculations of the Doppler Coefficient of Large Ceramic-Fueled Fast Reactors

Description: ABS>Calculations of the Doppler coefficient of large, ceramicfueled fast reactors containing plutonium were made by means of the ELMOE program to provide accurate flux calculations. The temperature-dependent cross sections of P. Greebler et al., for U/sup 238/ and Pu/sup 239/ were used. Doppler coefficients of the order of 10/sup -5/ ntermediate tem k/ C were obtained, in agreement with Greebler's results. Coefficients of carbide fueled reactors are about 0.7 of those of oxide-fueled reactors a… more
Date: August 1, 1962
Creator: Bhide, M.G. & Hummel, H.H.
Partner: UNT Libraries Government Documents Department
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, APRIL-JUNE 1962

Description: Research and development progress is reported on chemical-metallurgical processing, fuel cycle applications of voiatility and fluidization techniques, calorimetry, reactor safety, energy conversion, determination of nuclear constants, and routine operations. (M.C.G.)
Date: August 1, 1962
Partner: UNT Libraries Government Documents Department
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Critical Experiments for Pl-2 and Their Analysis

Description: The critical experiments showed that the original specification of 1.0 wt% for the boron concentration could be reduced to 0.25 wt% without reducing the one-rod-out shutdown margin below 2 1/2% reactivity as measured by rod drop experiments. Good agreement was obtained between calculated and measured eigenvalues for the small, clean cores which were analyzed. In cores with no control rods and containing all fuel, 0.0, 0.25, or 1.1 wt% boronstainless steel, and with all 0.25 wt% boron-stainless … more
Date: August 1962
Creator: Gailar, O.; Harding, R. S. & Knapp, R. W.
Partner: UNT Libraries Government Documents Department
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Designing for Remote Handling

Description: This manual discusses problems of remote handling and suggests design details for components, assemblies, and system of NERVA engines which will greatly aid remote maintenance.
Date: August 1, 1962
Creator: Huffman, S.A.
Partner: UNT Libraries Government Documents Department
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Determination of the Practicality of the Osmionic Process

Description: Report that contains a design for a more efficient osmionic demineralizer that could run for two weeks with no problems that still 2 to 3 times as costly as demineralization by electrodialysis.
Date: August 1962
Creator: Southern Research Institute
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS MONTHLY PROGRESS LETTER FOR MONTH OF JULY 1962

Description: Major effort during the report period was expended on the preparation and characterization of samples scheduled for in-pile screening tests. Other activities were continued on installation of hot metallographic cell installation and preparation and evaluation of UO/sub 2/-PuO/sub 2/ coprecipi tation processes. Data obtained in three preparation runs are included. A steady state intermediate production run was used to study the effects of ammonia evolved during the initial stages of mixed oxide … more
Date: August 1, 1962
Creator: Puechl, K.H.
Partner: UNT Libraries Government Documents Department
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Elastic Thermal Stress in Reactor Fuel Elements -- a Comparative Study of Various Shapes

Description: A method for comparison and evaluation of thermoelastic stresses is given for a range of fuel element shapes based on parameters available from the initial study of a reactor system. The shapes studied, in descending order of stress level are circular rods, concentric tubes, flat plates, and a matrix of circular holes.
Date: August 1962
Creator: Binns, Ian M.
Partner: UNT Libraries Government Documents Department
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AN EVALUATION OF MATERIALS OF CONSTRUCTION FOR THE SULFLEX AND ZIRFLEX PROCESSES

Description: concentration is not greater than four molar and the nitric acid greater than five molar. In addition, core dissolutions should be done below the boiling point, and heat transfer surface termperatures during core dissolution should be maintained below 240 deg F. Carpenter 20 is probably less satisfactory for Sulfex service because of selective weld attack. Neither Ni-o-nel, 309 SCb, or 304L is a satisfactory construction material for uninhibited Zirflex solutions. Cupric ion lowers the corrosio… more
Date: August 1, 1962
Creator: Katz, H. & Isler, R.
Partner: UNT Libraries Government Documents Department
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A Facility for Chemical Separation of Pu$sup 23$$sup 8$

Description: A facility for separation of Pu/sup 238/ and Np/sup 238/ from irradiated neptunium dioxide target slugs was designed, constructed, and operated at the Savannah River Laboratory. A description is given of the facility and the design details of equipment. (auth)
Date: August 1, 1962
Creator: Coogler, A L & Fowler, B F
Partner: UNT Libraries Government Documents Department
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A Facility for Chemical Separation of Pu238

Description: Technical report. From Abstract : "A facility for separation of Pu238 and Np237 from irradiated neptunium dioxide target slugs was designed, constructed, and operated at the Savannah River Laboratory. This report describes the facility and includes design details of equipment." From Summary : "The main problems encountered during the design of the facility were: (1) to provide adequate containment and shielding of the radioactive materials, (2) to select chemical- and radiator-resistant materia… more
Date: August 1962
Creator: Coogler, Arthur L. & Fowler, Bill F.
Partner: UNT Libraries Government Documents Department
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Fission product tritium in separations wastes and in the ground water

Description: The fairly recent discovery that tritium is a product of uranium fission prompted the analysis of separations plant waste streams and the local ground water for this radionuclide. The purpose of the sampling and analytical program was to determine the concentrations and relative distribution of tritium in cribbed-waste streams and its concentration and disposition in the local ground water regime. These factors are of interest from the environmental monitoring standpoint; they are also potentia… more
Date: August 1, 1962
Creator: Haney, W. A.; Brown, D. J. & Reisenauer, A. E.
Partner: UNT Libraries Government Documents Department
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