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ORR Operations for Period April 1961 to April 1962

Description: A summary of the activities in the 4th operational year is presented for the ORR. On-stream time at 30 Mw was relatively steady with 75.4 and 83.7% representing the lowest and highest quarters. Modification of the ball-latch mechanism of the shim-rod-drives is in progress. The primary cooling system bypass control valve was modified and a d-c pony motor was added at the No. 3 primary pump. This addition was made to increase the reliability of adequate water flow for afterheat cooling. A study o… more
Date: October 16, 1962
Creator: Binford, F.T.; Casto, W.R. & Colomb, A.L.
Item Type: Refine your search to only Report
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NUCLEAR SUPERHEAT PROJECT TENTH QUARTERLY PROGRESS REPORT, OCTOBER-DECEMBER 1961

Description: Results in the Nuclear Superheat Project are summarized. Topics covered include: conceptual design and program evaluation, fuel technology, materials development, experimental physics, coolant chemistry, heat transfer, mechanical development, SADE and E-SADE, and mixed spectrum superheat study. (M.C.G.)
Date: October 31, 1962
Creator: Pennington, R.T.
Item Type: Refine your search to only Report
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EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report No. 3, April-June 1961

Description: The heat-transfer loop was completed and is in operation. Difficulty was experienced in obtaining a sufficiently strong connection between the burnout- detector voltage tap and the heating element. This problem and its potential solution are described. The lack of means of obtaining controlled burnout prevented collection of data on the burnout effects of the ultrasonic field. (auth)
Date: October 31, 1962
Creator: Romie, F.E.
Item Type: Refine your search to only Report
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JULY, AUGUST, SEPTEMBER, 1961

Description: Development activities are reported on pyrometallurgical processes including melt refining and those using liquid metal solvents. Development of processing facilities for EBR II is also reported. In other work, laboratory- and engineering-scale investigations on fluoride volatility processes were condueted, and conversion of UF/sub 6/ to UO/sub 2/ was studied. Investigations are also reported concerning the kinetics of metal ignition and oxidation, and metalwater reactions. In work associated w… more
Date: October 31, 1962
Item Type: Refine your search to only Report
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CORE A CRITICAL STUDIES FOR THE ENRICO FERMI ATOMIC POWER PLANT ON ZPR-III

Description: A critical studies program for the Enrico Fermi Atomic Power Plant was run with the ZPR-III fast critical facility. The objectives of this program included determination of the U enrichment required for criticality, the effect of minor variations in core and blanket composition, reactivity coefficients, control and safety rod characteristics, power distribution, spectral indices, and the reactivity worth and wave shape of the oscillator rod. The experimental program was separated into two phase… more
Date: October 1, 1962
Creator: Branyan, C.E.
Item Type: Refine your search to only Report
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SNAP Radioisotope Space Programs Quarterly Progress Report No. 9, October 1 Through December 31, 1961

Description: All Phase I and Phase II testing was completed. Both launches of Phase I were successful, neither Phase II launches were successful. Test data recovered on Phase I launchings included optical coverage of re-entry and the trajectory and weather data; no telemetry canister temperature data were obtained. No test data were obtained on Phase II experiments. Reduction of Phase I test data was begun. The Phase II (Sub-subtask 7.3.2) was terminated December 20, 1961, when no test data were recovered f… more
Date: October 31, 1962
Item Type: Refine your search to only Report
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RADIOISOTOPE AND RADIATION APPLICATIONS. Quarterly Progress Report

Description: The study of the mechanism of free-radical formation and decay in polymeric materials was continued and extended to include an investigation of the potential application of this information to the development of novel graft copolymers. The study of postirradiation grafting techniques employing both peroxide initiation and direct grafting was continued. In addition, the effect of molecular weight on site formation was further investigated. Licenses and license applications for approximately 300 … more
Date: October 18, 1962
Creator: Sunderman, D.N., ed.
Item Type: Refine your search to only Report
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Evaluation of Subsize Izod Specimen Designs for Determining the Notch Toughness of Zircaloy-2

Description: Correlations were made on Zircaloy-2 Izod impact data and Charpy-V drop- weight data. Subsize Izod impact specimens of various geometries and notch configurations and standard ASTM Charpy-V specimens were prepared from bar and plate stock and tested. Drop-weight tests were also conducted and the NDT (nil- ductility transition) temperature was determined for 1/2 in. Zircaloy-2 plate. Results show that the impact properties of Zircaloy-2 are sensitive to hydrogen concentration, specimen and notch… more
Date: October 1, 1962
Creator: Prislinger, J. J.
Item Type: Refine your search to only Report
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Delayed Failure Hydrogen Embrittlement of Zirconium. Summary Report, September 15, 1961 to September 14, 1962

Description: The extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress was investigated. Susceptibility to time-dependent fracture was evaluated for unalloyed zirconium and Zircaloy-2 with 200 and 500 ppm hydrogen as well as for an experimental Zr Al-Sn-Mo alloy and the Canadian Zr-2.5Nb cladding material. For unalloyed zirconium and Zircaloy-2 containing up to 500 ppm hydrogen, no room-temperature, timedepe… more
Date: October 10, 1962
Creator: Weinstein, D. & Holtz, F. C.
Item Type: Refine your search to only Report
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GAUGE FOR MEASURING BOW OF TUBES

Description: A mechanical gage was designed to measure the bow over any one-foot length of long cylindrical material. The gage was used successfully for measuring bow in components of tubular fuel elements at the Savannah River Laboratory. (auth)
Date: October 31, 1962
Creator: Alewine, G.B.
Item Type: Refine your search to only Report
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AN IBM 7090 FORTRAN PROGRAM FOR ASME UNFIRED PRESSURE VESSEL DESIGN AND PRELIMINARY COST ESTIMATION

Description: An IBM 7090 FORTRAN program was written for the preliminary design and cost estimation of unfired pressure vessels with or without a jacket. Both vessel and jacket designs conform to the 1959 ASME Boiler and Pressure Vessel Code, Section VIII, Unfired Pressure Vessels. Vessels and jackets from 5 in. pipe through 84 in. o.d. and 1/4 in. through 1 1/2 in. in metal thickness may be designed by this program as written. Total vessel cost is the sum of metal and fabrication costs, each on a weight ba… more
Date: October 17, 1962
Creator: Prince, C. E. & Milford, R. P.
Item Type: Refine your search to only Report
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Thermal-Stress and Strain-Fatigue Analyses of the MSRE Fuel and Coolant Pump Tanks

Description: Thermal-stress and strain-fatigue analyses of the MSRE fuel and coolant pump tanks were completed for determining the quantity of coollng air required to obtain the maximum life of the pump tanks and to determine the acceptability of the pump tanks for the intended service of 100 heating cycles from room temperature to 1200 deg F and 500 reactor power-change cycles from zero to 10 Mw. A cooling-air flow rate of 200 cfm for the fuel pump tank was found to be an optimum value that provided an amp… more
Date: October 1, 1962
Creator: Gabbard, C.G.
Item Type: Refine your search to only Report
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SNAP 7 Program--Task 8--Strontium-90 Fueled Thermoelectric Generator Development. Quarterly Progress Report No. 5, November 1, 1961 to January 31, 1962

Description: The SNAP 7A battery and converter were subjected to the required shock, vibration and temperature teats. The generator was fueled, postfueling radiation levels were checked and the generator was integrated into the complete SNAP 7A system. After the completion of acceptance tests, the SNAP 7A system was installed in a buoy which, in turn, was anchored in the bay where it will be subjected to further evaluation. The SNAP 7C generator was shipped for transport to Antarctica. The generator will po… more
Date: October 31, 1962
Creator: McDonald, W. A.
Item Type: Refine your search to only Report
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SNAP Programs: Task 6--Fuel Technology Development Program. Quarterly Progress Report No. 7, April 1 Through June 30, 1961

Description: Progress made in the development of isotope power sources for thermoelectric and thermionic conversion to electrical energy is reported. The Heavy Elements Processing Facility for processing americium and fabricating americium capsules for irradiation was opened and hot operation was begun. Modifications to the americium purification system were completed and checkout operations were begun. Process specifications were established for dissolution of the irradiated capsules and the major equipmen… more
Date: October 31, 1962
Item Type: Refine your search to only Report
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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report, October 1-December 31, 1961

Description: Continued effort is reported on preparation and characterization of PuO/ sub 2/ and UO/sub 2/-- PuO/sub 2/ mixtures. Sintering and characterization of pellets for irradiation tests was emphasized, and efforts were also devoted to plasma torch production of spherical PuO /sub 2/ and coating of oxide materials. PuO/sub 2/ produced by the oxalate process from low concentration feed contains agglomerates which are not readily broken down, while that produced from normal feed contains larger agglome… more
Date: October 31, 1962
Item Type: Refine your search to only Report
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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report for Period January 1 through March 31, 1962

Description: During this reporting period, particular effort was of aced on powder blending and pellet sintering studies prior to irradiation sample fabrication, and, subsequently, the production and characterization of the pellets slated for irradiation. Also, PuO/sub 2/ and UO/sub 2/-PuO/sub 2/ characterization studies were continued, and new techniques are being developed. Specifically, dynamic moisture pickup determinations on PuO/sub 2/ were made in moist air, N, and CO/ sub 2/ atmospheres using a reco… more
Date: October 31, 1962
Item Type: Refine your search to only Report
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Chemical Processing Technology Quarterly Progress Report, January-March 1961

Description: Studies are reported on aqueous zirconium processing, dissolution of BeO- UO/sub 2/ ceramic fuel, the aqueous stainless steel process, the behavior of dibutyl phosphates, use of boron (boric acid) solution to assure critical safety, fluidized bed calcination, conversion of amorphous alumina to alpha alumina, the Demonstrational Waste Calcining Facility, removal of long-lived radioisotopes from waste solutions, separation of iron, nickel, and chromiun from stainless steel waste solutions, electr… more
Date: October 31, 1962
Creator: Bower, J. R.
Item Type: Refine your search to only Report
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Physics Division Summary Report, February-March 1962

Description: Progress is reported in experimental nuclear physics on calculations concerning the distribution of lifetimes of neutrons in glass scintillation neutron detectors and on the probabilities for single, double, and triple scattering of neutrons in thin plates. Precision measurements of gamma-ray energies and intensities were used to modify and extend the level scheme of Hf/ sup 178/. The presence of three K = 0 rotational bands (besides the ground state) and two K = 2 rotational bands are indicate… more
Date: October 31, 1962
Item Type: Refine your search to only Report
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Low Temperature Thermoluminescence of Gamma Irradiated Potassium Dihydrogen Phosphate

Description: Thermoluminescence in potassium dihydrogen phosphate (KDP) induced by Co/ sup 60/ gamma irradiation at liquid nitrogen temperature (-198 deg C) was investigated. Glow curves in the temperature range --196 to 0 deg C were measured for a series of gamma exposure dosages ranging from 10/sup 4/ roentgen to 5 x 10/sup 6/ roentgen. The heating rate used for glow curve measurements was 12 deg C per minute. Twice recrystallized Mallinckrodt reagent grade potassium dihydrogen phosphate, with a grain siz… more
Date: October 19, 1962
Creator: Sims, T. M.
Item Type: Refine your search to only Thesis or Dissertation
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