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Testing program for determining the mechanical properties of concrete to temperatures of 621/sup 0/C

Description: Concrete temperatures in a Liquid Metal Fast Breeder Reactor (LMFBR) in excess of normal code limits can result from postulated large sodium spills in equipment cells. Elevated temperature concrete property data which may have application for providing a basis for the design and evaluation of such postulated accident conditions is limited. Data thus needed to be developed commensurate with LMFBR plant applications for critical physical and mechanical concrete properties under prototypic thermal… more
Date: January 1, 1980
Creator: Oland, C.B.; Naus, D.J. & Robinson, G.C.
Partner: UNT Libraries Government Documents Department
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Design and operation of an inert gas facility for thermoelectric generator storage

Description: While the flight hardware is protected by design from the harsh environments of space, its in-air storage often requires special protection from contaminants such as dust, moisture and other gases. One of these components, the radioisotope thermoelectric generator (RTG) which powers the missions, was deemed particularly vulnerable to pre-launch aging because the generators remain operational at core temperatures in excess of 1000 degrees centigrade throughout the storage period. Any oxygen perm… more
Date: January 1, 1990
Creator: Goebel, C. J.
Partner: UNT Libraries Government Documents Department
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Investigation of breached depleted UF sub 6 cylinders

Description: In June 1990, during a three-site inspection of cylinders being used for long-term storage of solid depleted UF{sub 6}, two 14-ton cylinders at Portsmouth, Ohio, were discovered with holes in the barrel section of the cylinders. An investigation team was immediately formed to determine the cause of the failures and their impact on future storage procedures and to recommend corrective actions. Subsequent investigation showed that the failures most probably resulted from mechanical damage that oc… more
Date: January 1, 1991
Creator: DeVan, J. H.
Partner: UNT Libraries Government Documents Department
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Quarterly Progress Report on Fission Product Behavior in LWRs for the Period October-December 1977

Description: Analysis of release data obtained during High Burnup Fuel Test 10 (HBU-10) has been completed. In this test the fuel rod segment was ruptured by internal pressurization at 900/sup 0/C, at which time the temperature was rapidly increased to 1200/sup 0/C and maintained at this temperature for 10 min. Approximately 0.061% of the total cesium inventory in the rod segment was released; this was accompanied by the release of about 1.69% of the total /sup 85/Kr inventory. Moreover, about 0.022% of the… more
Date: February 1, 1978
Creator: Malinauskas, A. P.; Lorenz, R. A.; Collins, J. L.; Osborne, M. F.; Whatley, S. K. & Towns, R. L.
Partner: UNT Libraries Government Documents Department
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Investigation of leaks in fiberglass-reinforced pressure vessels by direct observation of hollow fibers in glass cloth

Description: A simple method of visual observation of hollow fibers within fiberglass cloth has been developed. This visualization can aid in determining the contribution these fibers make toward leaks observed in fiberglass-reinforced epoxy resin pressure or vacuum vessels. Photographs and frequency data of these hollow fibers are provided. 3 figs.
Date: January 1, 1988
Creator: McAdams, J.
Partner: UNT Libraries Government Documents Department
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Remote Plastic Bag Passout Unit for High-Level Radiochemical Operations

Description: A system is designed for making remote sealed-bag passouts from a multicurie-level chemistry processing enclosure. The polyethylene bags are changed remotely without exposing contaminated surfaces while always maintaining a low leak rate seal. The system employs an interchange box (passout box) attached to the chemistry enclosure. Integrated with the box is a hydraulically operated jack that raises and lowers the bags, and a welder-cutter for sealing them. A single master-slave manipulator team… more
Date: August 1, 1961
Creator: Fleischer, E. S.; Parsons, T. C. & Howe, P. W.
Partner: UNT Libraries Government Documents Department
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Investigation of cooling coil corrosion in storage tanks for radioactive waste

Description: The high frequency of cooling coil leaks observed in high-heat waste storage tanks soon after sludge removal operations is attributed to pitting, according to laboratory corrosion studies. Experiments show that the most likely series of events leading to coil leakage is (1) excessive dilution of basic nitrite in the supernate, (2) initiation of attack in crevices due to oxygen depletion cells, and (3) acceleration of the attack by sulfate dissolved from the sludge. When sludge was slurried with… more
Date: January 1, 1978
Creator: Ondrejcin, R.S.
Partner: UNT Libraries Government Documents Department
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RADIOLOGICAL HAZARDS FROM RUPTURE OF THE SECONDARY COOLANT SYSTEM OF THE 10 Mw ESCR

Description: The hazards study was made to determine the radiation level from the secondary sodium lines of the l0-Mw ESCR, and to evaluate the corresponding radioactive concentration in the secondary loop and the maximum permissible effective activation flux in the intermediate heat exchanger. The results are presented graphicallyn the radiation level from the coolant lines during normal operation as a function of line diameter and Na/sup 4/ concentration; the effective thermal neutron activation flux leve… more
Date: January 19, 1960
Creator: Piccot, A.R.
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF RING-JOINT FLANGES FOR USE IN THE HRE-2

Description: Ring-joint flanges were studied in thermal-cycle tests as part of the development work associated with Homogeneous Reactor Experiment No. 2 (HRE-2). The purpose of this study was to provide criteria for design, installation, and operation of joints that would remain leaktight under reactor operating temperatures and pressures. Joints ranging from 1/2 in., l500 lb to 4 in., 2500 lb and with various initial bolt loadings were cycled between room temperature and 636 deg F. It was demonstrated that… more
Date: December 21, 1961
Creator: Robinson, J. N.; Lundin, M. I. & Spiewak, I.
Partner: UNT Libraries Government Documents Department
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Carolinas Virginia Tube Reactor (Cvtr) in-Plant Testing Project.

Description: This report gives a description of a project which provides realistic information on containment system behavior that can be used to evaluate and improve analytical and experimental techniques thus allowing increased confidence in applying such technique to safety analysis of nuclear power plants.
Date: January 1, 1969
Creator: Norberg, J.A.
Partner: UNT Libraries Government Documents Department
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FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. Final Report

Description: >The basic fuel element consisted of a uniform dispersion of fuel in a 1 1/2 inch diameter graphite sphere. Ceramic coatings for the retention of fission products were studied. It was found-that molecularly deposited'' ceramics such as alumina, siliconized silicon carbide, and pyrolytic carbon were excellent barriers to fission product leakage. The most advantageous location for ceramic coatings was found to be on the individual fuel particles, where the coating was subject to smaller forces an… more
Date: April 30, 1961
Partner: UNT Libraries Government Documents Department
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Gamma densitometer for measuring Pu density in fuel tubes

Description: A fuel-gamma-densitometer (FGD) has been developed to examine nondestructively the uniformity of plutonium in aluminum-clad fuel tubes at the Savannah River Plant (SRP). The monitoring technique is ..gamma..-ray spectroscopy with a lead-collimated Ge(Li) detector. Plutonium density is correlated with the measured intensity of the 208 keV ..gamma..-ray from /sup 237/U (7d) of the /sup 241/Pu (15y) decay chain. The FGD measures the plutonium density within 0.125- or 0.25-inch-diameter areas of th… more
Date: January 1, 1982
Creator: Winn, Willard G.
Partner: UNT Libraries Government Documents Department
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Establishment and maintenance of a coal sample bank and data base

Description: Data from both instruments indicate that atmospheric oxygen is leaking into the primary and secondary containers. The methods and containers tested cannot maintain an inert atmosphere over the long term. The actual percentage of oxygen in the containers is thought to be influenced by several factors: (1) Flushing with argon by any method only displaces part (50 to 80%) of the atmospheric air present in the container after it is filled with coal. Because the atmosphere may not be homogeneous, an… more
Date: February 1, 1989
Creator: Davis, A.
Partner: UNT Libraries Government Documents Department
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FLUX DISTRIBUTIONS AND LEAKAGE CURRENTS FOR SRE, P-16

Description: BS>Two-group, two-region criticality calculations were made for 10 and 11 ft diameter tanks. The 10 ft tank required a core radius of 102 cm and the 11 ft tank a core radius of 95 cm for criticality. In the calculations, the fluxes were assumed to go to zero at the edge oi the graphite reflector. The fast group of the two-group calculation was broken down into 3 fast groups. The leakage out of the core and reflector for the 4 energy groups is given. (M.C.G.)
Date: January 29, 1954
Creator: Balent, R.
Partner: UNT Libraries Government Documents Department
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Study of plutonium oxide leak rates from shipping containers. Quarterly progress report, October 1, 1977--December 31, 1977

Description: The study was initiated in Oct. 1976. Several tasks are to be undertaken. In combination, they have the end objective of defining the leak rates of plutonium oxide from characterized leaks in shipping containers. Research progress is reported on each of the four tasks. (TFD)
Date: January 1, 1978
Creator: Schwendiman, L. C.; Pobereskin, M.; Mishima, J.; Sutter, S. L.; Madia, W. J.; Schmidt, E. W. et al.
Partner: UNT Libraries Government Documents Department
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Helium/solid powder O-ring leakage correlation experiments using a radiotracer

Description: UO/sub 2/ definitely leaked past the O-ring in three of the tests confirming the major results of the previous work. Continuous leakage at these levels may require additional precautions under present regulatory policies. The mechanism and the time and particle size dependence for the leakage are not known, but there is some indication leakage is more likely at low temperatures. It is possible leakage is due to movement of the O-ring during temperature or pressure cycling at the beginning or en… more
Date: January 1, 1984
Creator: Bild, R. W.; Leisher, W. B.; Weissman, S. H. & Seya, M.
Partner: UNT Libraries Government Documents Department
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Flight-systems safety program. Progress report, February 1982

Description: This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Coordination and Special Projects of the US Department of Energy by los Alamos National Laboratory. Most of the studies discussed here are ongoing. Results and conclusions described may change as the work continues. Published reference of the results cited in this report should not be made without the explicit permission of the person in charge of th… more
Date: February 1, 1982
Creator: Bronisz, S. E.
Partner: UNT Libraries Government Documents Department
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Tank 241-A-105 leak assessment

Description: Tank 241-A-105 is one of 149 single shell tanks constructed at Hanford to contain and store highly radioactive wastes originating from the processing of spent nuclear reactor fuel. Radiation detection and temperature monitoring devices installed beneath the tank indicate that several episodes of leakage of waste from the tank have occurred. The aim of this study was to evaluate the previous estimates and reanalyze the data to provide a more accurate estimate of leakage from the tank. The princi… more
Date: June 1, 1991
Partner: UNT Libraries Government Documents Department
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An Experimental Approach to Determining Subsurface Leakage From a Surface Impoundment Using a Radioisotope Tracer

Description: Bromine-82, a 35.3-h half-life radionuclide, was used as a tracer to determine the paths and rates of leakage from an unlined, 1,000,000-gal (3,785,000 L), surface impoundment at the Oak Ridge National Laboratory. Since the impoundment is underlain and surrounded by storm sewer and sanitary sewer lines (most of them predating the impoundment), known and suspected leak sites in storm drain catch basins and sanitary sewer manholes were sampled periodically and analyzed for /sup 82/Br. A series of… more
Date: January 1, 1986
Creator: Ashwood, T. L.; Story, J. D.; Larsen, I. L. & Schultz, F. J.
Partner: UNT Libraries Government Documents Department
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5MW Raft River facility experience

Description: The Raft River geothermal plant is a small binary cycle conversion system which uses isobutane as the working fluid. This plant uses a staged boiler concept to achieve better performance than could be obtained by a single boiler. The plant was designed to operate with a geothermal water inlet temperature of 143/sup 0/C (290/sup 0/F) and produce a nominal generator output of 5MW. The plant is supported by a supply and injection system consisting of three supply wells (about 1524m or 5000 ft deep… more
Date: January 1, 1980
Creator: Whitbeck, J.F.
Partner: UNT Libraries Government Documents Department
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