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THE DEVELOPMENT OF A SUMP-TYPE SOLIDIFIED-METAL SEAL

Description: A solidified-metal seal for possible use in moIten-saIt systems was fabricated and tested on a laboratory scale/su The seal consisted of an 80 Au-20 Cu (wt%) sealant alloy in contact with IN0R-8 base metal/su Eleven successive helium-leak-tlght sealings were effected before termination of the test due to a leak in one of the mating parts/su With better control over the heating cycle and slight modifications in seal design, it is expected that the useful life of a seal of this type could be exte… more
Date: March 15, 1962
Creator: Donnelly, R.G.
Partner: UNT Libraries Government Documents Department
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Criteria for the Design of the Thorium Fuel Cycle Development Facility

Description: Criteria for the conceptual design of the proposed Thorium Fuel Cycle Development Facility to be located at the Oak Ridge National Laboratory were established and are presented. In addition, conceptual layouts of the building and equipment are included. Reference fuel elements and processes that were selected as a basis for developing criteria for the facility are described. (auth)
Date: March 1, 1962
Creator: Irvine, A.R. & Lotts, A.L.
Partner: UNT Libraries Government Documents Department
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Emission Characteristics of Tantalum, Tungsten, Rhenium, and Iridium in Plasma Diodes

Description: Experimental determinations of the ionic and electronic emission characteristics of Ta, W, Re, and lr cathodes in vapor thermionic converters are compared. It is shown that Ta provides superior thermal ionization qualities at high pressure compared with W, Re, and Lr. High electronic current densities may be obtained from Cs on Re and Cs on Ir at much lower Cs vapor pressures than from Ta or W. An over-all efficiency of 19% was achieved with a Re cathode at 2440 deg K. (auth)
Date: March 15, 1962
Creator: Gust, W. H.
Partner: UNT Libraries Government Documents Department
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Evaluation of Heat Rejection Systems for PL-3

Description: An investigation was made of heat rejection systems for use in the PL-3 nuclear power plant, designed for placement at Byrd Station, Antarctica. It was concluded that the glycol-coupled surface condenser and air blast cooler combination appears to be suited for PL-3 plant requirements and operating conditions. (auth)
Date: March 1, 1962
Creator: Thurnau, C. J.
Partner: UNT Libraries Government Documents Department
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Spent Fuel Transfer, Storage and Shipment for PL-3

Description: In refueling development studies performed on PL-3 Phase I design, several methods of fuel transfer, storage, and shipment were investigated. An evaluation of the relative merits of the systems and designs under study, as applied to either the BWR or PWR concepts, is made and optimum designs are selected. An analysis of spent fuel shipping cask shielding requirements is presented, along with recommendations for future study in this area. (auth)
Date: March 1, 1962
Creator: Hauenstein, G. C. & Pomeroy, D. L.
Partner: UNT Libraries Government Documents Department
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Research in Radiobiology. Annual Report of Work in Progress on the Chronic Toxicity Program

Description: Separate abstracts were prepared on 8 sections of this report. Data are also included on the status of dogs at various time intervals following the injection of various doses of Ra/sup 226/, Pu/sup 239/, Ra/sup 228/, Th/sup 228, and Sr/sup 90/. (C. H.)
Date: March 31, 1962
Creator: Dougherty, T. F.
Partner: UNT Libraries Government Documents Department
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Multigroup Calculations of Effective Delayed-Neutron Fractions, Prompt- Neutron Lifetime, and Related Kinetics Parameters. IBM-704 Program 1188/RE

Description: In the course of a recent study of kinetics parameters, it was found that RE-185, because of its limitations, was inadequate to handle the problems involved with the reactors considered. Program ll88/RE was written entirely independent of and is intended to make RE-185 obsolete. The multigroup calculations of primary interest performed by the code are as follows: the total effective delayed-neutron fraction and its distribution into six ' families'' which are characterized by their periods; the… more
Date: March 1962
Creator: Kvitek, L. C.
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium. Quarterly Report No. 2, December 15, 1961 to March 14, 1962

Description: The purpose of this investigation is to determine the extent to which Zr and Zr alloys exhibit delayed failure (static fatigune) as caused by a combination of absorbed H and applied stress. Both notched and unnotched specimens of unalloyed Zr and Zircaloy-2 were hydrogenated to 200 ppm and 500 ppm by means of a modified Sieverts apparatus; specimens were evaluated at room temperature. Thus far, no time-dependent fracture was observed which can be attributed to the delayed failure phenomenon; it… more
Date: March 30, 1962
Creator: Weinstein, D. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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SALT PHASE CHLORINATION OF REACTOR FUELS. IV. NIOBIUM BEHAVIOR IN THE LEAD CHLORIDE AND CHLORINE-LEAD CHLORIDE SYSTEMS

Description: Investigation of the behavior of Nb in PbCl/sub 2/ showed that the Nb dissolution rate is quite low. Since stirring increases the rate appreciably, it is likely that the initial reaction is diffusion controlled. A subsequent reaction is linear in rate with an activation energy of 23.4 kcal per mole. Incomplete volatilization of dissolved Nb from PbCl/sub 2/ is due to the presence of lower oxidation states of Nb. The addition of Cl to PbCl/sub 2/ increases the rate of dissolution of Nb. The rate… more
Date: March 15, 1962
Creator: Teague, J. L.; Hahn, H. T. & Vander Wall, E. M.
Partner: UNT Libraries Government Documents Department
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GUIDE TO NUCLEAR POWER COST EVALUATION. VOLUME 4. FUEL CYCLE COSTS

Description: Information on fuel cycle cost is presented. Topics covered include: nuclear fuel, fuel management, fuel cost, fissionable material cost, use charge, conversion and fabrication costs, processing cost, and shipping cost. (M.C.G.)
Date: March 15, 1962
Partner: UNT Libraries Government Documents Department
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EGCR EXPERIMENTAL LOOPS, PRELIMINARY DESIGN REPORT

Description: The EGCR was designed to accommodate up to four gascooled experimental loops plus several experimental fuel elements in the open core. Two of the loops will utilize 51/2-in.-O.D. stainless steel tubes passing through the core along an axis which is about 17 in. from the central axis of the core. The other two loops will utilize 91/2-in.-o.d. tubes about 68 in. from the central axis. Inherent safety in the design, facility design, primary loop design, auxiliary systems and equipment design, prim… more
Date: March 27, 1962
Creator: Neill, F.H. & Michelson, C.
Partner: UNT Libraries Government Documents Department
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STATUS REPORT ON LAMB WAVES

Description: Theoretical and experimental aspects of Lamb waves are considered. These are described as body waves, or modes, which travel throughout an entire plate and are radiated from both surfaces, so that it is possible to detect Lamb waves when the receiver and sender are on opposite sides of the plate. Studies concerning applications of Lamb waves are reported in the field of nondestructive testing. (J.R.D.)
Date: March 1, 1962
Creator: di Novi, R.A.
Partner: UNT Libraries Government Documents Department
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Quarterly Status Report on LAMPRE Program for Period Ending February 20, 1962

Description: BS>LAMPRE I. The reactor operation is discussed. A malfunction in the shim operation was found and corrective measures taken. The core reloadings and other reactor modifications are described. The results of a gamma scanning of a fuel capsule are given. Fuel and Container Development. The properties and behavior of the Core I and the materials developed for Core II are described. Corrosion tests were carried out on pure Ta containers with molten Pu-Ce-Co alloys at 750 to 900 deg C, and the resu… more
Date: March 1, 1962
Partner: UNT Libraries Government Documents Department
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LABORATORY PROGRESS ON THE DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE BY DEEP- WELL INJECTION

Description: Results of laboratory studies on the neutralization of Purex-type wastes are reported, including the radiochemical distribution of the fission products in the precipitate and supernate and the effect of sodium and calcium neutralizations on fission-produet separation. The problem of interstitial precipitation encountered when a second incompatible liquid is injected into a formation is discussed. Results indicate a piston-iike displacement of the interstitial liquid by the injected waste with o… more
Date: March 1, 1962
Creator: Lacy, W.J.; Sealand, O.M.; Jacobs, D.G. & Struxness, E.G.
Partner: UNT Libraries Government Documents Department
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MANY-BODY THEORY (Based on a series of lectures given by J.R. Schrieffer)

Description: ABS>Notes from a series of l5 lectures on many-body theory given at Argomme Nationaf Laboratory in the spring of 1961 are presented. Topics covered include: formalism of quantum field theory, Heisenberg and interaction representations, Green's functions in the many-body problem, perturbation expansion for Green's functions, high-density electron gas, and theory of superconductivity. (M.C.G.)
Date: March 1, 1962
Creator: Bassani, F. & Robinson, J.
Partner: UNT Libraries Government Documents Department
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THE DESIGN AND CONSTRUCTION OF THERMAL FLOWMETERS

Description: A thermal flowmeter was designed and tested which will measure a wide range of flow rates for highly corrosive gases. Response to flow rate changes is fast. The pararaeters for changing the size and response to the flowmeter were evaluated. (auth)
Date: March 1, 1962
Creator: Kessie, R.W.
Partner: UNT Libraries Government Documents Department
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MTR Fast Neutron Flux Measurements for Cycle 146

Description: The fast neutron fluxes in selected positions of the MTR were measured for Cycle 146. The measurements were made at the beginning, throughout, and at the end of the cycle (564 Mwd). Vertical traverses for each position monitors are shown. (auth)
Date: March 20, 1962
Creator: Weber, L. D. & Hogg, C. H.
Partner: UNT Libraries Government Documents Department
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A STUDY OF LIQUIDS BY NEUTRON SCATTERING

Description: A radial density-distribution function for liquids was derived with the aid of the assumption that vibrational modes exist in liquids. The distribution function was obtained only for elastically scattered neutrons. A study of si(s) curves as a function of temperature, as well as the energy distribution of the scattered neutrons, affords a way in which to construct a model describing the motion of atoms in a liquid. (auth)
Date: March 1, 1962
Creator: Persiani, P.J.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Technology Quarterly Progress Report, October-December 1961

Description: The ICPP processed Al fuel, prtncipally of the MTR-ETR type, durtng this quarter. Newly designed and installed processing equipment exhibited excellent operating performance. This included direct-air-pulsed extraction, stripping and scrub columns, and a cascade-controlled continuous evaporator in first cycle product concentration service. Aqueous zirconium fuel processing studies continued with the objective of adapting the hydrofluoric acid process to continuous dissolution-complexing to incre… more
Date: March 28, 1962
Creator: Bower, J. R.
Partner: UNT Libraries Government Documents Department
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ULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX) HAZARD REPORT

Description: UHTREX utilizes a high-temperature, He-cooled, graphite moderated reactor employing unclad, refractory fuel elements. The reactor is designed to produce a msximum thermal power of 3 Mw and a maximum exit He temperature of 2400 deg F. The purpose of the experimert is to evaluate the advantages of the simple fuel against the disadvantages of the associated operation of a contaminated coolant loop. The mechanical and nuclear design of the reactor and related apparatus are described, discussed, and… more
Date: March 1, 1962
Partner: UNT Libraries Government Documents Department
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SPECTRAL SHIFT CONTROL REACTOR BASIC PHYSICS PROGRAM-THEORETICAL ANALYSIS. PART I. ANALYSIS OF EXPERIMENTS

Description: The data obtained in the series of SSCR experiments and the theoretical analysis of the results demonstrate the spectral shift control principle clearly. The critical assemblies show that considerably larger amounts of fuel can be loaded into a core moderated with a mixture of D/sub 2/O and H/sub 2/O than in one moderated with H/sub 2/O alone. The measured Cd ratios and the calculated neutron balances show that the excess reactivity associated with this extra mass is held up in the resonance ab… more
Date: March 1, 1962
Creator: Wehmeyer, D.B.; Doederlein, J.M.; Roach, K.E. & Wittkopf, W.A.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, August 1961

Description: Engineering studies of a 6-in.-ID countercurrent foam column were started. The capacity of Mark II Stacked Clone Contactor was found to be limited by gradually increasing entrainment. Thoria sols were prepared from trough denitrator products in a conical bottom tank agitated by circulation through an external centrifugal pump. Experimental results agreed favorably with predicted results for the reaction of CO with CuO and fur the simultaneous reactions of H/ sub 2/ and CO with CuO. In a 2-in. d… more
Date: March 1, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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Annual Progress Report on Fuel Element Development for Fiscal Year 1961

Description: Progress in fuels and materials development is summarized. Major areas of investigation include a materials study by means of sample fuel plates containing uranium alloys or cermets, burnable poisons, non-uniform fuel and poison distributions and clad with various aluminum alloys; and an engineering study of fuel element geometries optimized in heat transfer, hydraulics, and materials strength. Up to 45 wt% U-Al alloys, 6 to 65 wt% UO/-Al and U3O6-Al dispersions, including enrichments ranging f… more
Date: March 1, 1962
Creator: Gibson, G. W. & Shupe, O. K.
Partner: UNT Libraries Government Documents Department
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