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Production test IP-245-A dual area trip-out of B & C Reactor process pumps

Description: The objectives of the test described in this report are to obtain current knowledge of the flow characteristics of the B and C Reactor flow systems under various transient conditions that have a reasonable probability of occurrence. These tests will be used to revaluate the B and C Reactor bulk temperature limits, the Ball 3X low pressure trip settings, and quantitative adequacy of emergency flow from the combined high tanks - export system.
Date: March 26, 1959
Creator: Long, J. T. & Jones, S. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Prerequisite requirements for higher graphite temperature limits and/or nitrogen atmosphere at all reactors

Description: The graphite temperature limits specified in the process standards-are being closely approached or have limited power levels at B, D, DR, and reactors. An increase of approximately 50--100 C in graphite temperature limits at these reactors would permit year-around operation on bulk outlet temperature limits. There has been considerable recent interest in extending to all reactors the use of nitrogen as a reactor gas constituent. With present graphite temperature limits, significant benefit from… more
Date: February 26, 1962
Creator: Graves, S. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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K-Reactor Retubing Program graphite temperature study

Description: A project has been proposed and the funds allocated for the replacement of the central zone aluminum process tubes at both K Reactors with smooth bore zirconium process tubes of approximately the same outside diameter as the original tubes. Associated with this project is the problem of relieving the present graphite stack distortion in the vicinity of the process tube channels and counteracting or prereliving, at this time, the expected graphite stack distortion that, will take place over the … more
Date: December 26, 1962
Creator: Agar, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production losses associated with K Reactor graphite temperature limits

Description: As power levels have been raised at the K Reactors, the graphite temperature limit has caused significant production losses. These losses have come from three sources: (1) Occasions vhen pile power was directly limited because the graphite temperatures were limiting; (2) Losses in ECT because control rod movements to control graphite temperatures are not necessarily the best rod movements for pile, flattening; and (3) Losses due to lack of control in the final stages of an operating period beca… more
Date: April 26, 1960
Creator: Fuller, N. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LLNL high-field coil program

Description: An overview is presented of the LLNL High-Field Superconducting Magnet Development Program wherein the technology is being developed for producing fields in the range of 15 T and higher for both mirror and tokamak applications. Applications requiring less field will also benefit from this program. In addition, recent results on the thermomechanical performance of cable-in-conduit conductor systems are presented and their importance to high-field coil design discussed.
Date: March 26, 1986
Creator: Miller, J. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Equations of state for self-excited MHD generator studies

Description: We have constructed a state-of-the-art equation of state (EOS) for argon covering the temperature density range attainable by currently proposed self-excited MHD generators. The EOS for conditions in the flow channel was obtained primarily by a non-ideal plasma code (ACTEX) that is based on a many body activity expansion. For conditions in the driver chamber the EOS was primarily obtained from a fluid code (HDFP) that calculates the fluid properties from perturbation theory based on the insulat… more
Date: February 26, 1980
Creator: Rogers, F. J.; Ross, M.; Haggin, G. L. & Wong, L. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Temperature and Contamination on Mpcms Electrodes in 241-Ay-101 and 241-an-107 Tank Waste Simulants

Description: This report documents the results of tests designed to characterize the relationship between temperature and the measured potential of electrodes installed on multi-probe corrosion monitoring systems in waste tanks. This report also documents the results of tests designed to demonstrate the impact of liquid in-leakage into electrode bodies as well as the contamination of primary reference electrodes by diffusion through the electrode tip.
Date: March 26, 2010
Creator: Dahl, M. M.; Philo, S. L.; Edgemon, G. L.; Bell, J. L. S. & Moore, C. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Abrupt onset of a second energy gap at the superconducting transition of underdoped Bi2212

Description: he superconducting gap--an energy scale tied to the superconducting phenomena--opens on the Fermi surface at the superconducting transition temperature (Tc) in conventional BCS superconductors. In underdoped high-Tc superconducting copper oxides, a pseudogap (whose relation to the superconducting gap remains a mystery) develops well above Tc (refs 1, 2). Whether the pseudogap is a distinct phenomenon or the incoherent continuation of the superconducting gap above Tc is one of the central questi… more
Date: May 26, 2007
Creator: Hussain, Zahid; Lee, W. S.; Vishik, I. M.; Tanaka, K.; Lu, D. H.; Sasagawa, T. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The Development of Models to Optimize Selection of Nuclear Fuels through Atomic-Level Simulation

Description: Demonstrated that FRAPCON can be modified to accept data generated from first principles studies, and that the result obtained from the modified FRAPCON make sense in terms of the inputs. Determined the temperature dependence of the thermal conductivity of single crystal UO2 from atomistic simulation.
Date: January 26, 2009
Creator: Phillpot, Prof. Simon; Sinnott, Prof. Susan B.; Seifert, Prof. Hans & Tulenko, Prog. James
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Anisotropic intermediate valence in Yb2M3Ga9 (M = Rh, Ir)

Description: The intermediate valence compounds Yb{sub 2}M{sub 3}Ga{sub 9} (M = Rh, Ir) exhibit an anisotropic magnetic susceptibility. We report measurements of the temperature dependence of the 4f occupation number, n{sub f}(T), for Yb{sub 2}M{sub 3}Ga{sub 9} as well as the magnetic inelastic neutron scattering spectrum S{sub mag}({Delta}E) at 12 and 300 K for Yb{sub 2}Rh{sub 3}Ga{sub 9}. Both n{sub f}(T) and S{sub mag}({Delta}E) were calculated for the Anderson impurity model with crystal field terms wit… more
Date: April 26, 2005
Creator: Christianson, A. D.; Lawrence, J. M.; Lobos, A. M.; Aligia, A. A.; Bauer, E. D.; Moreno, N. O. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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An experimental study of adsorption in vapor-dominated geothermal systems

Description: We report results of steam adsorption experiments conducted for rock samples from vapor-dominated geothermal reservoirs. We examine the effect of the temperature on the adsorption/desorption isotherms. We find that the temperature effect is only important on the desorption such that the hysteresis becomes more pronounced as the temperature increases. The scanning behavior within the steam sorption hysteresis loop is also studied to investigate the behavior during repressurization. Collection of… more
Date: January 26, 1995
Creator: Satik, Cengiz & Horne, Roland N.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Long-Term Waste Package Degradation Studies at the Yucca Mountain Potential High-Level Nuclear Waste Repository

Description: The Site Recommendation (SR) process for the potential repository for spent nuclear fuel (SNF) and high-level nuclear waste (HLW) at Yucca Mountain, Nevada is underway. Fulfillment of the requirements for substantially complete containment of the radioactive waste emplaced in the potential repository and subsequent slow release of radionuclides from the Engineered Barrier System (EBS) into the geosphere will rely on a robust waste container design, among other EBS components. Part of the SR pro… more
Date: February 26, 2002
Creator: Mon, K. G.; Bullard, B. E.; Longsine, D. E.; Mehta, S.; Lee, J. H. & Monib, A. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Vibrational and Electronic Properties of Fullerene and Carbon-Based Clustors. Final Reports for period July 1, 1997 - June 30, 2001

Description: Lattice dynamics is of central importance for the mechanism of ferroelectricity. In particular, the soft mode behaviors are directly related to many of their ferroelectric and dielectric properties. In this project, we have carried out experimental studies of the vibrational spectra of SrTiO{sub 3} films grown by pulsed laser deposition using a metal-oxide bilayer structure. Raman scattering, with and without bias electric field, and Fourier-transform far-infrared ellipsometry were utilized. Th… more
Date: November 26, 2002
Creator: Xi, X.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Stability of Uranium Alloys at High Exposures

Description: Postirradiation examinations were begun of a series of unrestrained dilute uranium alloy specimens irradiated to exposures up to 13,000 MWD/T in NaK-containing stainless steel capsules. This test, part of a program of development of uranium metal fuels for desalination and power reactors sponsored by the Division of Reactor Development and Technology, has the objective of defining the temperature and exposure limits of swelling resistance of the alloyed uranium. This paper discusses those test … more
Date: March 26, 2001
Creator: McDonell, W.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Status of Irradiation Tests of Dilute Uranium Alloys in NaK-Containing Stainless Steel Capsules

Description: To extend experience with uranium metal fuels to the high exposures required for power reactor operation, the Savannah River Laboratory has conducted over several years a series of irradiation tests of small uranium specimens of various alloy compositions in NaK-containing stainless steel capsules. These tests were designed specifically to establish the limits on exposure that could be reached during irradiation of the alloys at various temperatures without swelling and to determine the metallu… more
Date: March 26, 2001
Creator: McDonell, W.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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C-106 High-Level Waste Solids: Washing/Leaching and Solubility Versus Temperature Studies

Description: This report describes the results of a test conducted by Battelle to assess the effects of inhibited water washing and caustic leaching on the composition of the Hanford tank C-106 high-level waste (HLW) solids. The objective of this work was to determine the composition of the C-106 solids remaining after washing with 0.01M NaOH or leaching with 3M NaOH. Another objective of this test was to determine the solubility of various C-106 components as a function of temperature. The work was conduct… more
Date: January 26, 2000
Creator: Lumetta, G. J.; Bates, D. J.; Berry, P. K.; Bramson, J. P.; Darnell, L. P.; Farmer, O. T., III et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Prototype Engineered Barrier System Field Tests; Progress report

Description: This paper presents selected preliminary results obtained during the first 54 days of the Prototype Engineered Barrier System Field Tests (PEBSFT) that are being performed in G-Tunnel within the Nevada Test Site. The test described is a precursor to the Engineered Barrier Systems Field Tests (EBSFT). The EBSFT will consist of in situ tests of the geohydrologic and geochemical environment in the near field (within a few meters) of heaters emplaced in welded tuff to simulate the thermal effects o… more
Date: July 26, 1989
Creator: Ramirez, A. L.; Beatty, J.; Buscheck, T. A.; Carlson, R.; Daily, W.; LaTorre, V. R. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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