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Development of a High Velocity Solid Particle Launcher for Laboratory Erosion Studies. [Reentry Vehicle Heat Shields]

Description: A solid particle launcher for laboratory erosion studies has been developed and successfully demonstrated. Performance of the launcher is predicted by a two-dimensional, time-dependent theoretical analysis to within the experimental uncertainty. The present device accelerates 100 μm diameter glass spheres to velocities of 2.1+/- 0.6 km/sec. The system is safe, reliable, and has a test repetition of about 2 shots/hour.
Date: March 1, 1975
Creator: Aeschliman, D. P.; Mulac, A. J.; Guzman, J. A.; Eaton, R. R. & Fox, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Unit Operations Section Monthly Progress Report, September 1961

Description: Nine samples of ThO/sub 2/ -UO/sub 2/ prepared as part of the solgel process development studies showed no consistent effects from small variations in several process parameters. The reaction of methane and copper oxide was studied. Engineering studies of the continuous dissolution of simulated U-Zr-Sn fuels in 6.5 M NH4F, 0.6-1.0 M NH/sub 4/NO/sub 3/, 0.1 M H/sub 2/O/sub 2/ were continued in modified 6-in.-dia. equipment. A total of 1642 kg of U from NaK bonded SRE Core I fuel rods wad dejacke… more
Date: April 1, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, February 1962

Description: In the operation of 6-in.-dia. foam-liquid columns, increase in either the liquid flow or foam flow caused increased channeling with increased HTU. Flooding values for the Immi mixer-settler were obtalned using the amine extraction final cycle Pu flowsheet. Two tests of the addltlon of uranyl nitrate to a thoria sol were made, one of which gave a good product and the other a product which disintegrated during calcination. Material balances for 22 waste calcination runs are summarized. (auth)
Date: August 23, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PILOT PLANT SHUTDOWN AND Pu-Al PROCESSING

Description: The large aqueous pilot plant facilities at ORNL were cleaned and are being put in standby condition. Experience was gained during the year as anion exchange was used to recover more than one kg of plutonium left in the exploded evaporator system. This experience is being applied to a new recovery program just beginning in cell 1 of Building 4507. (auth)
Date: September 25, 1961
Creator: Bresee, J.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cryogenic supplies for the TFTR neutral beam line cryopanels

Description: Cryocondensing panels will be used for the Neutral Beam Lines of the TFTR to satisfy a pumping speed requirement of 2.5 x 10/sup 6/ l/s. The cryocondensing panels are fed by liquid helium (LHe), boiling at selectable temperatures of 4.5/sup 0/K or 3.8/sup 0/K. Liquid nitrogen (LN/sub 2/) panels and chevrons thermally shield the LHe panel. The closed-loop LHe supply system and the open loop LN/sub 2/ system are discussed. The helium refrigerator of minimum 1070-W capacity, together with its dist… more
Date: January 1, 1977
Creator: Pinter, G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Manipulator comparative testing program

Description: The Manipulator Comparative Testing Program examined differences among manipulator systems from the United States and Japan. The manipulator systems included the Meidensha BILARM 83A, the Model M-2 of Central Research Laboratories Division of Sargent Industries (CRL), and the GCA Corporation PaR Systems Model 6000. The site of testing was the Remote Operations Maintenance Demonstration (ROMD) facility, operated by the Fuel Recycle Division in the Consolidated Fuel Reprocessing Program at the Oa… more
Date: January 1, 1986
Creator: Draper, J. V.; Handel, S. J.; Sundstrom, E.; Herndon, J. N.; Fujita, Y. & Maeda, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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DYNAVAC: a transient-vacuum-network analysis code

Description: This report discusses the structure and use of the program DYNAVAC, a new transient-vacuum-network analysis code implemented on the NMFECC CDC-7600 computer. DYNAVAC solves for the transient pressures in a network of up to twenty lumped volumes, interconnected in any configuration by specified conductances. Each volume can have an internal gas source, a pumping speed, and any initial pressure. The gas-source rates can vary with time in any piecewise-linear manner, and up to twenty different tim… more
Date: July 8, 1980
Creator: Deis, G.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design of a continuous duty cryopump

Description: A continuous duty cryopump system was designed and developed that comprises a self-contained cryopump for installation into a vacuum chamber, and a microprocessor controller for automatic operation. This deuterium pump has two units in a single housing, arranged so that one is pumping while the other is being regenerated. Liquid helium-cooled, finned sections in each unit pump deuterium by condensation, and a third pump integral within the cryopump housing collects the regenerated gas. A microp… more
Date: May 1, 1985
Creator: Sedgley, D.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Multielement analysis of geologic materials by inductively coupled plasma-atomic emission spectroscopy

Description: Atomic emission spectroscopy using an inductively coupled plasma (ICP) source permits the rapid acquisition of multielement geochemical data from a wide variety of geologic materials. Rocks or other solid samples are taken into solution with a four acid digestion procedure and introduced directly into the plasma; fluid samples are acidified or analyzed directly. The entire process is computer-controlled, fully-automated, and requires less than five minutes per sample for quantitative determinat… more
Date: March 1, 1980
Creator: Christensen, O.D.; Kroneman, R.L. & Capuano, R.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pumping behavior of sputter ion pumps

Description: The ultrahigh vacuum requirements of ISABELLE is obtained by distributed pumping stations. Each pumping station consists of 1000 l/s titanium sublimation pump for active gases (N/sub 2/, H/sub 2/, O/sub 2/, CO, etc.), and a 20 l/s sputter ion pump for inert gases (methane, noble gases like He, etc.). The combination of the alarming production rate of methane from titanium sublimation pumps (TSP) and the decreasing pumping speed of sputter ion pumps (SIP) in the ultrahigh vacuum region (UHV) lea… more
Date: unknown
Creator: Chou, T S & McCafferty, D
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Hot cell studies of tritium removal from and dissolution of an irradiated thoria fuel

Description: Tritium removal and dissolution studies on an irradiated thoria-based fuel were conducted in the High Level Caves at the Savannah River Laboratory (SRL). The objectives of these studies were to define the effects of key process-related parameters on tritium evolution and subsequent dissolution. The test program at SRL determined the effects on tritium removal of particle size, heating temperature, oxidation, and agitation. ThO/sub 2//UO/sub 2/ (95%/5%) fuel from the Elk River Reactor, irradiate… more
Date: January 1, 1980
Creator: Pickett, J.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, May 1961

Description: The experimental results on the oxidation of H from a He stream with CuO pellets were very close to the predicted behavior based on the mathematical model. Experimental measurements of uranyl sulfate loading rates on chloride equilibrated resin showed little variation with solution concentrations. A tentative flowsbeet was proposed for cost analysis of processing a Pebble Bed Reactor. A U-Zr plate was dissolved in nitrate-free Zirflex solution. An authentic TRIGA prototype was processed in engi… more
Date: December 26, 1961
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Wire Scanner for SM-1

Description: Preliminary design concepts are presented for a wire scanner for experimentally evaluating spatial variations of neutron flux in the SM-l reactor core. Results of a literature search and determination of optimum criteria for flux mapping the core in minimum time dictated requirements for design concepts and specifications. The utility of both manually instrumented and automatically instrumented wire scanners was analyzed with respect to rapidity of measurement, selectivity of detector location,… more
Date: November 22, 1961
Creator: Kemp, S. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiochemical analysis of the first plateout probe from the Fort St. Vrain high-temperature gas-cooled reactor

Description: This report presents the analysis of radioactive elements on the first plateout probe from the Fort St. Vrain high-temperature gas-cooled reactor. The plateout probe is a device which samples the primary coolant for condensible fission products. Circuit inventories of individual radionuclides are estimated from the probe analysis. The analysis shows that the radioactive contamination in the primary circuit is remarkable low, with activation product concentrations much greater than that of fissi… more
Date: June 1, 1982
Creator: Burnette, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HANFORD STUDIES FOR EGCR COMBUSTION CHARACTERISTICS. Summary Report

Description: The temperature, geometry, and flow conditions which exist in the EGCR were duplicated in a mock-up designated as the EGCR Burning Rig to establish the combustion conditions in the reactor. The conditions under which the EGCR Burning Rig will ignite were established and an analytical model was developed which predicts these conditions. Because the Burning Rig cannot exactly dupIicate the reactor situation the final prediction of the safety of the EGCR must rest on computer calculations employin… more
Date: October 10, 1961
Creator: de Halas, D.R.; Dahl, R.E. & Jackson, J.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The safety record at the tritium systems test assembly

Description: This work addresses an important objective of the TSTA-demonstrating that the large tritium inventories required for fusion reactors can be routinely handled, without radiation exposure to operating personnel and without significant environemtnal releases. The techniques by which TSTA has achieved low releases and personnel exposures include high-integrity primary piping systems that exclude contact between tritium and organic materials, a secondary containment system that encloses all primary … more
Date: February 1, 1988
Creator: Coffin, D.O.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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SIZE ANALYSIS OF PARTICULATES FOUND IN AIR AT HANFORD PLUTONIUM FABRICATION FACILITIES

Description: A study was made on the characteristics of radioactively contaminated air at Hanford work locations. One of the main objectives in this study is to define the size of particular air contamination in plutonium handling facilities. In addition to characterizing the particulate contamination, it is desirable to know the normal background particle size distribution. Data are summarized on general particle size distribution and radioactive particle distribution at two Hanford plutonium fabrication f… more
Date: August 1, 1962
Creator: Selby, J.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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Unique sampling and transfer system for the Fluorinel Dissolution and Storage Facility

Description: Liquid sampling, sample transfer and analytical systems for the Fluorinel Dissolution and Storage Facility (FAST) are required for monitoring feed and process solutions on a constant basis during fuel dissolution. Due to sequential batch dissolution, sampling becomes important in monitoring and tracking the dissolution phase of each dissolver. The sampling cell contains 10 liquid samplers, a pneumatic sample transfer sender/receiver, a decontamination service station, plastic transfer capsule c… more
Date: January 1, 1980
Creator: Jacobson, M. E.; Carter, J. A. & Paige, D. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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