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Production test IP-250-A irradiation of Zircaloy-2 jacketed tube-and-tube elements in the KER loops

Description: This report discusses testing three-foot Zircaloy-2 jacketed tube-and-tube elements with either natural or 1.6% enriched unalloyed or 2% zirconium alloyed uranium which will be irradiated in any of the KER Loops to goals up to 5000 WD/T. Downstream thermocouples to measure flow channel coolant temperatures will be included for charges of enriched elements. Special tray discharges to prevent the fall of the elements to the basin are required for all loadings. The tube-and-tube geometry is being … more
Date: June 1, 1959
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Relative Ball 3X-VSR reactivity strength DR reactor. Interim Report of PT IP-126-C

Description: Prior to this experiment, no measurements of Ball 3X effectiveness had been performed for any of the older 2004-tube Hanford piles, and calculations concerning total control requirements were made assuming the vertical safety system strength equal to the strength of the B, D, F vertical safety rods. With current and projected enrichment loadings, the vertical control system was calculated to be inadequate to satisfy the total control criteria at all times, resulting in the necessity to provide … more
Date: June 1, 1959
Creator: Simpson, D. E.
Partner: UNT Libraries Government Documents Department
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K Reactor panellit protection against plugging incidents with low front header pressure

Description: The purpose of this report is to present the results of experimental tests made to determine the degree of protection offered by the Panellit system to accidental flow reductions caused by plugging incidents to a K reactor process tube operating at low front header pressures.
Date: June 1, 1959
Creator: Fitzsimmons, D. E. & Hesson, G. M.
Partner: UNT Libraries Government Documents Department
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Hazards Summary Report for a Three Watt Polonium-210 Fueled Thermoelectric Generator

Description: A hazards survey was made of the Auxiliary Power Unit (APU) for space vehicle applications. The APU utilizes the decay process from 1570c of Po/sup 210/ to generate thermal energy. The design is described and diagrams are given. The factors involved in the integration of the thermoelectric generator into the Discoverer or Sentry vehicles are discussed. The physical, chemical, nuclear, and radiobiological properties of Po/sup 210/ are given. The shielding requirements for the APU are outlined. T… more
Date: June 1, 1959
Partner: UNT Libraries Government Documents Department
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COUPLED TRANSMISSION LINES

Description: >Tests on a coupled transmission line resonator show that a fairly accurate value of the coupling coefficient can be predicted by considering line geometry. The measured values of V/sub 02/ and I/sub 02/ appear to agree with predicted values. Development of a resonator for ORIC with two coupled transmission lines is under way. (W.L.H.)
Date: June 1, 1959
Creator: Warsham, R E & Mosko, S W
Partner: UNT Libraries Government Documents Department
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Liquid Metal Loops Irradiated on the ORNL Graphite Reactor and the LITR

Description: From abstract: Liquid alkali metals were circulated in a series of structural alloy loops under reactor radiation at high temperature. The first of these loops was a lithium-stainless steel (type 316) system, and the remainder were sodium-Inconel. No effect of radiation other than radioactivation was found. Mass transfer and metallurgical processes attributable to the operating temperatures were observed."
Date: June 1, 1959
Creator: Parkinson, W. W. & Sisman, O.
Partner: UNT Libraries Government Documents Department
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The Nuclear Spins and Magnetic Moments of Certain Gold and Silver Isotopes

Description: An atomic-beam magnetic-resonance apparatus operating on the flop-in principle was used to measure the nuclear spins and hyperfine-structure separations of the /sup 2/S/sub 1/2, electronic ground state for several radioactive isotopes of silver and gold. The results of these experiments, together with calculated values of the nuclear magnetic-dipole moments, are given (auth)
Date: June 1, 1959
Creator: Ewbank, W. B.
Partner: UNT Libraries Government Documents Department
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Sequential Separation of Some Actinide Elements by Anion Exchange

Description: Methods are presented by which trace amounts of several actinide elements are separated. Use is made of the large differences in distribution coefficients, so careful chromatographic techniques are not necessary. Small columns are used, allowing the desired constituent to be obtained in 10 ml or less. One method is used to separate americium, plutonium, and neptunium. These elements are sequentially eluted from columns of Dowex 1 resin in that order by 8 M HNO/sub 3/, 0.02 M ferrous sulfamate i… more
Date: June 1, 1959
Creator: Roberts, F. P. & Brauer, F. P.
Partner: UNT Libraries Government Documents Department
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First Sodium Reactor Experiment (SRE) Test of Hallam Nuclear Power Facility (HNPF) Control Materials

Description: An experiment was conducted in the SRE to measure temperatures and neutron flux levels in and near a boron-containing simulated control rod. The data are being used to check analytical methods developed for prediction of control rod heat generation rates and maximum temperatures in this type of control rod in the Hallam Nuclear Power Facility. The maximum observed temperatures with a reactor power level of 20 Mw were 1363 deg F for a boron-- nickel alloy ring having a 0.105-in. radial clearance… more
Date: June 1, 1959
Creator: Arneson, S. O.
Partner: UNT Libraries Government Documents Department
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GAMMA RAYS FROM THE INTERACTION OF 14-Mev NEUTRONS WITH BERYLLIUM

Description: The cross section for the Be/sup 9/(n,t')Li/sup 7*/ -- Li/sup 7/ + gamma (0.477 Mev) reaction was measured in the vicixity of 14 Mev by detecting the gamma rays at scattering angles from 30 to 150 degrees. A time-of-flight technique was used to distinguish the gamma rays from the high neutron background. The cross section drops from 20 mb at 13.6 Mev to 10 mb at 14.1 Mev and then rises to 30 mb at 14.7 Mev. (auth)
Date: June 1, 1959
Creator: Benveniste, J.; Mitchell, A. C.; Schrader, C. D. & Zenger, J. H.
Partner: UNT Libraries Government Documents Department
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Study of 40 MW Pressurized Water, Boiling Water, and Organic Moderated Reactors for Production of Process Steam

Description: The study efforts were toward the creation of a reactor design for each of the three types and the development of each concept to a point where the range of costs could be established. The studies presented have high burnup cores of low enrichment in an effort to minimize fuel costs. Of the three designs presented to deliver 1.25 x 10/sup 5/ lb/hr of 380 deg F steam at 196 psia the PWR core is the most favorable. (W.D.W.)
Date: June 1, 1959
Creator: Link, L. E.; Armstrong, R. H.; Breden, C. R.; Gariboldi, R. J.; Genens, L. E.; Kelber, C. N. et al.
Partner: UNT Libraries Government Documents Department
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A Double Pulse Eddy Current Testing System

Description: ing. Radiography was used to ore fter bending. The ultrainspect the alloys cores, ished fuel elements. as used to determine element core blanks. at ing fatigue tests were performed in the range 1300 to 1500 F, for frequencies of 6 and 60 cpm. Continuous traces of load and strain were made to determine relationships between stress, strain, and lifetime, for lifetimes vithin the range of 10/sup 3/ and 10/sup 5/ cycles. The data obtained indicate that fatigue strength, whether measured in stress, … more
Date: June 1, 1959
Creator: Renken, C.J. & Myers, R.G.
Partner: UNT Libraries Government Documents Department
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Microbarograph Instrumentation

Description: Microbarographs are used at the Nevada test site to measure acoustic energy at certain locations with respect to blasts. These data are used then to decide if weather conditions are favorable for a nuclear test. The microbarograph and its operation are described in detail. (T.R.H.)
Date: June 1, 1959
Creator: Hansen, H. E.
Partner: UNT Libraries Government Documents Department
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Summary of HRT Run 14

Description: A detailed study of HRT Run 14, which was abruptly terminated by the formation of a hole in the Zircaloy-2 core tank is presented. In this run the reactor was operated at high temperature and pressure for ten days from March 25 to April 4, 1958. Nuclear power operation extended from March 29 until April 4, when fuel solution leaked into the heavy-water blanket. The maximum power level attained was 6.4 Mw. The reactor equipment performance was satisfactory, except for the core vessel, but the nu… more
Date: June 1, 1959
Creator: Engel, J. R.; Haubenreich, P. N.; Kolb, J. O. & Richardson, D. M.
Partner: UNT Libraries Government Documents Department
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COMMENTS OF THE HANDLING OF PLUTONIUM

Description: Many of the features of plutonium facilities have been covered, and a number of them have been omitted. A great variety of safety equipment is available, together with trained personnel to operate it. All of these devices, however, do not assure a contamination-free operation. Basically, the careful design of enclosures, experimental equipment, and procedures when handled by trained personnel represents the only approach to the problem of plutonium handling. (auth)
Date: June 1, 1959
Creator: Steindler, M.J.
Partner: UNT Libraries Government Documents Department
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The Set Codes--IBM 704 Codes for the Calculation of the Stresses in a Pressure Vessel With an Ellipsoidal Head

Description: A solution to the problem of stresses in a pressure vessel with an ellipsoidal head has long been sought by pressure vessel designers. To meet this need the codes described in this report were written The codes are based on a finite-difference approximation to the LoveMeissner equations which are the basis of the bending theory of thin shells. (auth)
Date: June 1, 1959
Creator: Bilodeau, G.G.; Callaghan, J.B. & Kraus, H.
Partner: UNT Libraries Government Documents Department
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METHODS OF CONTROLLING CORE-WALL TEMPERATURES IN AQUEOUS HOMOGENEOUS REACTORS

Description: The problem of controlling the surface temperatures of core vessels in two-region aqueous homogeneous reactors was examined by analyzing several possible systems for cooling the wall: (1) direction of the inlet core fluid along the wall at a high velocity; (2) passage of heavy water through the wall of a double-wall core vessel; and (3) flow of cool blanket slurry past the wall. If the required flow conditions can be achieved, method (1) will keep the surface temperature within 20 deg C of the … more
Date: June 1, 1959
Creator: Rosenthal, M W
Partner: UNT Libraries Government Documents Department
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Extraction of Uranium, Magnesium, Zirconium, and Cerium From Bismuth With a Fused Fluoride Salt Mixture

Description: The extraction of uranium, magnesium, cerium, zirconium, and niobium from bismuth with a molten mixture of sodium fluoride and zirconium fluoride was demonstrated. Comparative rates of extraction were obtained. The effects of high concentrations of magnesium and of hydrogen fluoride sparging on the extraction process were investigated. Tracer studies demonstrated that exchange occurs between zirconium dissolved in the bismuth and zirconium in the fused salt. The applicability of the fused fluor… more
Date: June 1, 1959
Creator: Adams, M. D.; Fischer, J.; Meyer, R. J. & Phillips, N. D.
Partner: UNT Libraries Government Documents Department
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PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MAY 1959

Description: Data are presented on the electrical conductivity of unirradiated UO/sub 2/. A stud of the creep properties of annealed and of 15% cold-worked Zircaloy-2 at 290, 345, and 400 deg C is in progress. High-purity Mo single crystals are being grown in a modified Andrade furnace. Research to develop a method of sink- float density measurement to identify factors affecting irradiation-induced volume changes in graphite was continued. The simulation of conditions after a lossof-coolant incident in the … more
Date: June 1, 1959
Creator: Dayton, R.W. & Tipton, C.R. Jr.
Partner: UNT Libraries Government Documents Department
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RE-34, AN IBM-704 REACTOR SHIELDING PROGRAM

Description: An IBM-704 shielding program is described which solves, by a finite difference method, the multigroup diffusion equation system in slab, cylindrical, or spherical geometry, with a prescribed source distribution given for the highest energy group. A wide choice of boundary conditions has been made available at the outer boundaries and either continuity of flux and current or the black boundary'' condition may be specified at each regional interface. The machine time required to process an averag… more
Date: June 1, 1959
Creator: Butler, M.K. & Cook, J.M.
Partner: UNT Libraries Government Documents Department
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