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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 the men were released to return to work. In compliance with AEC Manual Chapter 0703, an AEC-HAPO committee composed of two AEC employees and five General Electric employees was appointed by the Manger, HOO, with the concurrence of the General Manager, HAPO, to conduct an investigation of the incident. The committee`s purpose was to determine the cause, nature, and extent of the incident, and recommend action to be taken by others to minimize or preclude future incidents of this magnitude. A study of operating practices and operating conditions that appeared to exist prior to, during, and subsequent to the accident was made by the committee. The committee believes that this report provides sufficient information to answer questions which may arise as a result of the criticality incident except those relating to its cause.
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 daughter radioactivity from target materials by direct heating of the target. (auth)
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 the end of each section. An author index is included. (M.C.G.)
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 atoms and ions, and a table of conversion factors.
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 structure of the discharge deviated drastically from axial symmetry near the outer surface. Several studies led to the conclusion that the flow pattern probably involved secondary flows. A detailed analysis of this structure was not possible. It was also found that the rotational speed could not be raised above a few cm/ mu sec because the insulators failed in spite of the special design of the experiment. 28 references. (auth)
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 at the same fuel enrichment. Effective coarse- group elastic-removal cross sections for light elements are tabulated. It appears that, with tabulations of this sort as a guide, coarse-group sets of cross sections can be constructed to give adequate accuracy in calculations of Doppler coefficients without use of ELMOE. (auth)
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 steel and fuel elements surrounded by aluminum-water displacers, the calculated eigenvalues were 0.7 to 1.0% greater than the measured values. In a core with 0.25 wt% boronstainless steel and with the center control rod fully inserted, the calculated eigenvalue was 1.0% larger than measured. In one case, a core composed entirely of fuel and with the center control rod fully inserted, the calculated eigenvalue was 0.33% DELTA k smaller than that measured. The calculated power distributions compared extremely well with those measured in the fuel assemblies. Shutdown measured by the boron substitution method, where the worth of the boron was measured by calibrating both a single control rod and a bank of rods, was found to give consistent results which in turn agreed to within 0.5% DELTA k with shutdown measured by the rod drop technique. The rod drop measurements with 0.25 wt% boron gave a shutdown of 2.52% with the central control rod withdrawn. Correcting for the small difference between the mockup and the reference core, the shutdown margin for the PL-2 was 3% DELTA k/k. Shutdown measurements obtained by moving a calibrated control rod from all into its critical position and maintaining criticality by the compensating motion of another rod or rods, were found to give widely differing results depending on the combination of rods used. Measurements in a boron-stainless steel …
Date: August 1, 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 precursor conversion on ADU precipitation. To determine whether or not selfreduction occurs, charges of the precursor were thermally decomposed in N/sub 2/ using fast and slow temperature rises on similar samples. Results are included which indicate that no significant amount of self-reduction occurs under these conditions. Effort is also continuing on development of techniques for producing spherical particles by mechanical agglomeration and sintering, and by plasma torch fusion. (J.R.D.)
Date: August 1, 1962
Creator: Puechl, K.H.
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 corrosion rate of 309 SCb to 30--40 mils per year, but is not a satisfactory inhibitor for 304L or Ni-o-nel. (auth)
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 materials, and (3) to provide for remote operation and maintenance of process equipment. ... This report contains a discussion of the major design problems and a detailed description of the facility and equipment."
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 potentially of real value in evaluation of the regional ground water hydrology. This report presents the initial results of the process waste and ground water tritium-sampling program. Two-dimensional comparisons of the ground water tritium analyses with routine gross beta analyses are also presented.
Date: August 1, 1962
Creator: Haney, W. A.; Brown, D. J. & Reisenauer, A. E.
Partner: UNT Libraries Government Documents Department
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FUEL CYCLES FOR AN 800 Mw(t) PEBBLE-BED REACTOR

Description: Reactivity lifetime calculations were made for an 800Mw(t) pebble-bed reactor on the basis of a batch-fueling cycle, a once-through equilibrium cycle, and a gradedexposure equilibrium cycle. The maximum lifetime, obtained with the graded-exposure equilibrium cycle, was 1.41 fissions per initial fissionable atom. In this case the conversion ratio was 0.62 and the neutron leakage from the core was 0.078. The same fuel composition gave 1.29 fissions per initial fissionable atom on a once-through equilibrium cycle and 0.92 fissions per initial fissionable atom on a batch cycle. (auth)
Date: August 1, 1962
Creator: Carlsmith, R.S.
Partner: UNT Libraries Government Documents Department
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