2,789 Matching Results

Search Results

Advanced search parameters have been applied.

Final Report : Production Test 105-329-F, Filled Block Graphite Sample Report

Description: This report provides data on production test 105-329-P and solid graphite samples used to analyze damage obtained from controlled natural erosion tests. The data provided will help establish current ideas on the status of filler block graphite and interpretation of the data will assist in establishing pile operating temperature limits based on stored energy.
Date: November 1, 1950
Creator: Johnson, P. A., {}
Partner: UNT Libraries Government Documents Department

Friction studies of graphite and mixtures of graphite with several metallic oxides and salts at temperatures to 1000 degrees F

Description: Report presenting an experimental friction study using graphite and mixtures of graphite with lead oxide, cadmium oxide, sodium sulfate, or cadmium sulfate as solid lubricants. Runs were made at temperatures up to 1000 degrees Fahrenheit with various steel and Inconel combinations.
Date: February 1956
Creator: Peterson, Marshall B. & Johnson, Robert L.
Partner: UNT Libraries Government Documents Department

Investigation of Graphite Bodies : Progress Report No. 3 for the Period March 1, 1959 to May 31, 1959

Description: This document is the third in a series of progress report that records investigations of graphite bodies. Along with the report, two appendices are given to describe the different graphite bodies: "Synthetic Binders for Carbon and Graphite" and "High Temperature Physical Properties of Molded Graphites".
Date: June 10, 1959
Creator: Bradstreet, Samuel W.
Partner: UNT Libraries Government Documents Department

Uranium Oxide Aerosol Transport in Porous Graphite

Description: The objective of this paper is to investigate the transport of uranium oxide particles that may be present in carbon dioxide (CO2) gas coolant, into the graphite blocks of gas-cooled, graphite moderated reactors. The transport of uranium oxide in the coolant system, and subsequent deposition of this material in the graphite, of such reactors is of interest because it has the potential to influence the application of the Graphite Isotope Ratio Method (GIRM). The GIRM is a technology that has been developed to validate the declared operation of graphite moderated reactors. GIRM exploits isotopic ratio changes that occur in the impurity elements present in the graphite to infer cumulative exposure and hence the reactor’s lifetime cumulative plutonium production. Reference Gesh, et. al., for a more complete discussion on the GIRM technology.
Date: January 23, 2012
Creator: Blanchard, Jeremy; Gerlach, David C.; Scheele, Randall D.; Stewart, Mark L.; Reid, Bruce D.; Gauglitz, Phillip A. et al.
Partner: UNT Libraries Government Documents Department

Temperature distribution in an inhomogeneous cell

Description: Report describing "the effects of variable graphite conductivity and of the gas layers in the lattice" under the assumptions that "graphice conductivity varies as a power of the distance from the center of each cell" and "uniform distribution of heat sources" - from abstract.
Date: unknown
Creator: Triplett, John R.
Partner: UNT Libraries Government Documents Department

Correlation of chemical analyses on graphite bars and test pile results

Description: From abstract: "The chemical analyses of graphite test bars obtained from National Carbon Company and the analyses performed by the Hanford Works Laboratories Division do not correlate significantly with the test pile results, nor do the chemical analyses obtained from National Carbon Company agree with those done in the Handford Works Laboratories. Chemical results obtained at Hanford on samples taken lengthwise from individual bars correlated significantly with the individual test pile results."
Date: unknown
Creator: Lane, J.J.
Partner: UNT Libraries Government Documents Department

The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

Description: Report documenting "the long-term irradiation stability of the graphite used as the moderator in the Experimental Gas Cooled Reactor (EGCR) at Oak Ridge" (p. 1) by irradiating capsules at the General Electric Test Reactor. This includes the design and construction of the experiment, experiment procedures, and results of irradiation. Appendices begin on page 83.
Date: September 1964
Creator: Helm, J. W.
Partner: UNT Libraries Government Documents Department

Carbide coatings on graphite

Description: From abstract: "A Method has been developed for the uniform coating of graphite tubes with carbides of niobium, tantalum, and zirconium by thermal composition of their respective halide vapors."
Date: 1957
Creator: Blocher, J. M., Jr.; Ish, Carl J.; Leiter, Don P.; Plock, Layne F. & Campbell, Ivor E.
Partner: UNT Libraries Government Documents Department

Modified-Graphite Technology : Quarterly Report No. 1

Description: From abstract: "This report summarizes the past year of study of fine, molded, multicrystalline graphites with particular reference to the interrelation among certain properties with the composition, fabricating techniques, and thermal treatments found to influence them."
Date: January 20, 1960
Creator: Bradstreet, Samuel W.
Partner: UNT Libraries Government Documents Department

Statistical Comparison of the Baseline Mechanical Properties of NBG-18 and PCEA Graphite

Description: High-purity graphite is the core structural material of choice in the Very High Temperature Reactor (VHTR), a graphite-moderated, helium-cooled design that is capable of producing process heat for power generation and for industrial process that require temperatures higher than the outlet temperatures of present nuclear reactors. The Baseline Graphite Characterization Program is endeavoring to minimize the conservative estimates of as-manufactured mechanical and physical properties by providing comprehensive data that captures the level of variation in measured values. In addition to providing a comprehensive comparison between these values in different nuclear grades, the program is also carefully tracking individual specimen source, position, and orientation information in order to provide comparisons and variations between different lots, different billets, and different positions from within a single billet. This report is a preliminary comparison between the two grades of graphite that were initially favored in the two main VHTR designs. NBG-18, a medium-grain pitch coke graphite from SGL formed via vibration molding, was the favored structural material in the pebble-bed configuration, while PCEA, a smaller grain, petroleum coke, extruded graphite from GrafTech was favored for the prismatic configuration. An analysis of the comparison between these two grades will include not only the differences in fundamental and statistically-significant individual strength levels, but also the differences in variability in properties within each of the grades that will ultimately provide the basis for the prediction of in-service performance. The comparative performance of the different types of nuclear grade graphites will continue to evolve as thousands more specimens are fully characterized from the numerous grades of graphite being evaluated.
Date: August 1, 2013
Creator: Carroll, Mark C. & Rohrbaugh, David T.
Partner: UNT Libraries Government Documents Department