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ABRAC---an IBM-704 Three Dimensional Nuclear-Thermal Depletion Program With Distributed Void Effects

Description: ABRAC is a three dimensional nuclear thermal depletion program to study the effects of water moderator density changes, resulting from flow variations and boiling, on neutron flux distribution and depletion. The program requires an IBM-704 with a memory of 32.768 words and ten tape units. (auth)
Date: March 1960
Creator: Jacobi, W. M.; Lawton, T. J.; Meanor, S. H. & Parrette, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Application of Nuclear Energy to Agriculture

Description: Differences were found in the radiosensitivity of cacao clones. Studies are continuing to see if these differences are related to nuclear damage. Radiosensitivity of rubber, palms, and bananas are being studies. Angustifolia mutants appeared from irradiated coffee seeds. The response was linear with thermal neutrons but exponential with gamma rays. The hypothesis of a two hit chromosomal aberration is being tested with coffee and Crotalaria which probably gave an exponential response (sectorial… more
Date: March 1, 1960
Creator: {{{name}}}
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section B Monthly Progress Report, March 1960

Description: Consolidated Edison type fuel pellets were irradiated and analyzed, to determine the extent of fracturing, particle size of fines produced, and the rate of dissolution in boiling 13M HNO/sub 3/-0.04M NaF -0.1M Al(NO/sub 3/)3. Fused sodium or potassium hydroxide was used to shatter the pellets at 400 deg C or higher. Similar pellets were dissolved in H/sub 3/PO/sub 4/ and fused ammonium bifluoride. An investigation was made of the thermodynamics and limits of flammability of gases expected durin… more
Date: March 1, 1960
Creator: Blanco, R E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section C Progress Report for December 1959 and January 1960

Description: The recovery of Th from Blind River ion exchange barrens with di(2- ethylhexyl)phosphoric acid was investigated. The recovery of Tc and Np from fluorination plant residues with tertiary amine was studied. The extraction of Np/sup 4+/ by quaternary ammonium nitrates is reported. A solvent recovery procedure involving successive use of Na/sub 2/CO/sub 3/washing and Al/sub 2/O/ sub 3/- adsorption was demonstrated in laboratory tests as a possible method for the purification and decontamaination of… more
Date: March 1, 1960
Creator: Brown, K. B.; Allen, K. A.; Blake, C. A.; Coleman, C. F.; Crouse, D. J.; Gresky, A. T. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A COLORIMETER FOR IN-LINE ANALYSIS OF URANIUM AND PLUTONIUM SOLUTIONS

Description: A colorimeter is described that can be used to monitor process solutions continuously for uranyl nitrate or plutonium nitrate concentration. The instrument was tested under plant conditions in the concentration range from 0.1 to 70 grams of uranium per liter and 0.1 to 10 grams of plutonium per liter. The instrument error was plus or minus 1% of the span, but errors of 15 to 20% can be caused by other variables such as acidity and other salts present. (auth)
Date: March 1, 1960
Creator: Colvin, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Physics Design

Description: The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and powerdensity distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor. (J.R.D.)
Date: March 1, 1960
Creator: Barringer, H. S.; Flickinger, R. B. & Spetz, S. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE DEPLETION OF BURNABLE POISON IN ENDURANCE CALCULATIONS

Description: Methods of relating the bunnable poison concentration in a reactor to the fuel concentration during the life of the core are presented. These methcds correspond to the following ways of using bunnable poison: (1) in discrete lumps, (2) in a homogeneous rnixture with the fuel, and (3) a combination of these. Nuclear data relevant to the U/sup 235/-B/sup 10/ system are presented. (auth)
Date: March 1, 1960
Creator: Dahlberg, R.C. & Judge, F.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design of LCCBM and LCCBN Loops

Description: The special fabrication requirements of the newer columbium alloys, particularly with respect to brazing, stress relieving, weld filler wire, etc., necessitates individual detail and layout drawings for the construction of forced convection corrosion loops from different columbium alloys. Accordingly, it is requested that detail and layout drawings be provided for two forced convection corrosion loops to the specifications outlined.
Date: March 1, 1960
Creator: Coyle, C.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Diffusion of Hydrogen in Zirconium Hydride

Description: The diffusion of hydrogen in zirconium hydride was studied using permeation techniques. The rate of permeation of hydrogen through zirconium hydride disks was measured for small concentration gradients. Data were obtained at 61 to 65 at.% hydrogen and 500 to 750 ction prod- C. The diffusion coefficients were determined by the time-lag method. Ho variation of the diffusion coefficients with hydrogen concentration was observed. The diffusion coefficients can be expressed by D (cm/sup 2/ per sec) … more
Date: March 1, 1960
Creator: Albrecht, W. M. & Goode, W. D., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Irradiated OMRE Fuel Elements First Core Loading

Description: Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date: March 1, 1960
Creator: Walter, J. H.; Leirich, J. F. & Calkins, G. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fast Reactor Core Design Parameter Study

Description: Report describing parametric studies of eleven fast reactor fuel systems undertaken to determine the design and economic factors for producing electricity. The methods used for making the parametric studies are described, as well as the results of these studies. Appendices begin on page 103.
Date: March 1960
Creator: Atomic Power Development Associates
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Halogen Collector Test Program

Description: Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date: March 1, 1960
Creator: Arthur D. Little, Inc.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Halogen Collector Test Program

Description: Efficiency tests of removal of radioactive iodine from an air stream were performed on the following halogen collectors: a silver-plated copper-ribbon bed: activatedcharcoal beds, 0.5 and l.0 in. deep: a molecular-sieve bed; and a sodium thiosulfate bed. The tests were conducted at 70 and 160 deg F and at 70 and 95% relative humidity. Only the activated-charcoal collectors achieved a high iodineremoval efficiency over a sustained period at the various operating conditions. (C.J.G.)
Date: March 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Heavy Water Moderated Power Reactors. Progress Report for January 1960

Description: Approximately one-quarter of the construction and 85% of the firm design of the Heavy jWater Components Test Reactor (HWCTR) were complete at the end of January 1960. Safeguards analyses of the liquid-D/sub 2/O-cooled loop of the HWCTR showed that none of the accidents considered to date have serious potential. Exploratory tests of the a device for quenching the steam that would be generated in the boiling-D/sub 2/O- cooled loop of the HWCTR showed that a quencher could be designed to operat sa… more
Date: March 1960
Creator: Isakoff, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High Flux Isotope Reactor--a General Description

Description: The High Flax lsotope Reactor (HFIR) is being planned for construction at Oak Ridge National Laboratory as a supporting facility in the program of investigation of the properties of the transplutonium elements. The reactor will be a flux-trap reactor consisting of a berylliumrefiected, light-water-cooled annular fuel region surroundin g a light-water island. An irradiation sample of 200 to 300 g of Pu/sup 242/ will be placed in the island where a thermalneutron flux of approximately 3 x 10/sup … more
Date: March 1, 1960
Creator: Cole, T E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

IBM-704 CODES FOR REACTIVITY STEP CALCULATIONS (RE-126 AND RE-135)

Description: Two codes were written for the IBM-704 to calculate the behavior of a reactor following a step change in reactivity, using one-group. space- independent, zero-power kinetic theory. The reactor is assumed to be running at constant level before the step is made, either at critical or subcritical conditions, with an external source. The code RE-128 assumes all delayed-neutron precursors in equilibrium at the time of the step, while the code RE-135 allows cases with nonequilibrium precursors to be … more
Date: March 1, 1960
Creator: Cohn, C. E. & Toppel, B. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Interactions of Antiprotons in Hydrogen, Beryllium, and Carbon

Description: To determine the nature of the interactions between antinucleons and nucleons, it has been necessary to do an experiment in which the elastic, inelastic, and charge-exchange interactions could be measured. Improvements in the 6-Bev Bevatron have permitted production of a considerably larger flux of antiprotons, than was available in earlier studies. With the use of strong-focusing magnetic quadrupoles, a crossed electric- and magnetic-field spectrometer, and time-of-flight scintillation counter… more
Date: March 1, 1960
Creator: Cork, Bruce
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
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