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A report on high-level nuclear waste transportation: Prepared pursuant to assembly concurrent resolution No. 8 of the 1987 Nevada Legislature

Description: This report has been prepared by the staff of the State of Nevada Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) in response to Assembly Concurrent Resolution No. 8 (ACR 8), passed by the Nevada State Legislature in 1987. ACR 8 directed the NWPO, in cooperation with affected local governments and the Legislative committee on High-Level Radioactive Waste, to prepare this report which scrutinizes the US Department of Energy`s (DOE) plans for transportation of high-level radioacti… more
Date: December 1, 1988
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Optical, mass, and auger spectra from e-bombarded KBr

Description: We have measured the mass spectrum and optical emission lines of neutral potassium atoms ejected from KBr at T = 300/degree/K and 443/degree/K bombarded by 2-keV electrons. The room-temperature data may be complicated by the nonstoichiometry of the alkali-enriched sample surface and seem difficult to interpret. The high-temperature sample, which maintains the proper stoichiometry, produces data in support of gas-phase excitation of alkali atoms desorbed from the surface. 15 refs., 4 figs.
Date: January 1, 1988
Creator: Arakawa, E.T. & Kamada, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A theoretical prediction of critical heat flux in forced convection boiling during power transients

Description: In this paper, a theoretical prediction of critical heat flux (CHF) during power transients in forced convective boiling is presented. The analysis is restricted to the departure from nucleate boiling (DNB) type of CHF at low qualities. The developed theory is compared with the experimental data available in the literature. The agreement is favorable. The results are discussed in terms of the various parameters affecting the transient CHF. This new model also is compared with the semi-empirical… more
Date: January 1, 1988
Creator: Pasamehmetoglu, K.O.; Nelson, R.A. & Gunnerson, F.S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A theoretical prediction of critical heat flux in subcooled pool boiling during power transients

Description: Understanding and predicting critical heat flux (CHF) behavior during steady-state and transient conditions are of fundamenatal interest in the design, operation, safety of boiling and two-phase flow devices. This paper discusses the results of a comprehensive theoretical study made specifically to model transient CHF behavior in subcooled pool boiling. This study is based upon a simplified steady-state CHF model in terms of the vapor mass growth period. The results obtained from this theory in… more
Date: January 1, 1988
Creator: Pasamehmetoglu, K. O.; Nelson, R. A. & Gunnerson, F. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fabrication and characterization of MCC (Materials Characterization Center) approved testing material---ATM-2, ATM-3, and ATM-4 glasses

Description: Materials Characterization Center glasses ATM-2, ATM-3, and ATM-4 are designed to simulate high-level waste glasses that are likely to result from the reprocessing of commercial nuclear reactor fuels. The three Approved Testing Materials (ATMs) are borosilicate glasses based upon the MCC-76-68 glass composition. One radioisotope was added to form each ATM. The radioisotopes added to form ATM-2, ATM-3, and ATM-4 were /sup 241/Am, /sup 237/Np, and /sup 239/Pu, respectively. Each of the ATM lots w… more
Date: March 1, 1988
Creator: Wald, J.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Solvent extraction studies of 10% TBP flowsheets in the solvent extraction test facility using irradiated fuel from the Fast Flux Test Facility

Description: Two solvent extraction experiments were made in the Solvent Extraction Test Facility (SETF) during Campaign 10 to continue the evaluation of: (1) a computer control system for the coextraction-coscrub contractor; and (2) a partitioning technique that separates uranium and plutonium without the aid of chemical reductants. The Fast Flux Test Facility (FFTF) fuel used in this campaign had burnups of {approximately}55 and {approximately}60 (average) MWd/kg. During both experiments, the computer con… more
Date: March 1, 1988
Creator: Benker, D. E.; Bigelow, J. E.; Bond, W. D.; Campbell, D. O.; Chattin, F. R.; King, L. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Research programs for Division of Chemical Sciences, Office of Basic Energy Sciences, Department of Energy

Description: A chemical sciences review meeting was held in which research programs in chemistry were discussed. Major topics included: chemistry of actinides and fission products, interactions of solvents, solutes and surfaces in supercritical extraction, chemical and physical principles in multiphase separations, and chemical kinetics of enzyme catalyzed reactions. Individual projects are processed separately for the data bases. (CBS)
Date: January 1, 1988
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Storage of LWR spent fuel in air: Volume 1: Design and operation of a spent fuel oxidation test facility

Description: This report describes the design and operation and technical accomplishments of a spent-fuel oxidation test facility at the Pacific Northwest Laboratory. The objective of the experiments conducted in this facility was to develop a data base for determining spent-fuel dry storage temperature limits by characterizing the oxidation behavior of light-water reactor (LWR) spent fuels in air. These data are needed to support licensing of dry storage in air as an alternative to spent-fuel storage in wa… more
Date: December 1, 1988
Creator: Thornhill, C. K.; Campbell, T. K. & Thornhill, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DWPF (Defense Waste Processing Facility) canister impact testing and analyses for the Transportation Technology Center

Description: A legal weight truck cask design has been developed for the US Department of Energy by GA Technologies, Inc. The cask will be used to transport defense high-level waste canisters produced by the Defense Waste Processing Facility (DWPF) at the Savannah River Plant. The development of the cask required the collection of impact data for the DWPF canisters. The Materials Characterization Center (MCC) performed this work under the guidance of the Transportation Technology Center (TTC) at Sandia Nati… more
Date: December 1, 1988
Creator: Farnsworth, R. K. & Mishima, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Criticality Experiments with Mixed Plutonium and Uranium Nitrate Solution at a Plutonium Fraction of 0.2 and 1.0 in Annular Cylindrical Geometry

Description: A series of critical experiments was completed with mixed plutoniumuranium solutions having Pu/(Pu + U) ratios of approximately 0.2 and 1.0. These experiments were a part of the Criticality Data Development Program between the United States Department of Energy (USDOE), and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. A complete description of, and data from, the experiments are included in this report. The experiments were performed with mixed plutonium-uranium so… more
Date: April 1, 1988
Creator: Lloyd, RC
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Criticality Experiments with Mixed Plutonium and Uranium Nitrate Solution at a Plutonium Fraction of 0.4 in Slab and Cylindrical Geometry

Description: A series of critical experiments was completed with mixed plutonium-uranium solutions having Pu/(Pu + U) ratios of approximately 0.4. These experiments were a part of the Criticality Data Development Program between the United States Department of Energy (USDOE), and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. A complete description of, and data from, the experiments are included in this report. The experiments were performed with mixed plutonium-uranium solutions… more
Date: April 1, 1988
Creator: Lloyd, RC
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Laboratory testing of TiB/sub 2/-based cathodes for electrolytic production of aluminum

Description: Experimental research was performed to evaluate TiB/sub 2/-based cathodes, which may be used for retrofitting existing commercial Hall-Heroult cells. Candidate cathode materials and retrofit designs were analyzed in laboratory-scale electrolysis tests and nonpolarized immersion tests in molten Al. The cathode materials and cathode attachment designs were selected based on a literature review (Schilling, Hagen, and Hart 1987) and previous experimental research at the Pacific Northwest Laboratory… more
Date: July 1, 1988
Creator: Schilling, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Immersion tests of TiB/sub 2/-based materials for aluminum processing applications

Description: This report summarizes molten Al immersion tests conducted under the Stable Cathode Development task to evaluate the microstructural behavior of TiB/sub 2/-based materials. Four types of TiB/sub 2/- based materials were evaluated before and after nonpolarized exposure to molten Al at temperatures encountered in Hall-Heroult cells. Three of the materials, TiB/sub 2/-graphite (TiB/sub 2/-G) composites, TiB/sub 2/-aluminium nitride (AIN) composites, and high-purity TiB/sub 2/ sintered from halide … more
Date: July 1, 1988
Creator: Schilling, C. H. & Graff, G. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Criticality experiments with mixed oxide fuel pin arrays in plutonium-uranium nitrate solution

Description: A series of critical experiments was completed with mixed plutonium-uranium solutions having a Pu/(Pu + U) ratio of approximately 0.22 in a boiler tube-type lattice assembly. These experiments were conducted as part of the Criticality Data Development Program between the United States Department of Energy (USDOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. A complete description of the experiments and data are included in this report. The experiments were perf… more
Date: August 1, 1988
Creator: Lloyd, R.C. (Pacific Northwest Lab., Richland, WA (United States)) & Smolen, G.R. (Oak Ridge National Lab., TN (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of local radiative properties in coal-fired flames. Technical progress report, September 15, 1987--September 15, 1988

Description: Recently, an extensive, in-depth review of the modeling of radiation heat transfer in combustion chambers has been prepared (Viskanta and Menguc, 1987); therefore, there is no need to repeat that material here. It is already known that the most important missing link in the prediction of radiation heat transfer in combustion systems is the lack of detailed information about the optical and physical properties of combustion products (Viskanta and Menguc, 1987). The purpose of this research is to… more
Date: December 31, 1988
Creator: Menguec, M. P.; Agarwal, B.; Bush, M.; Dsa, D. & Subramaniam, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FMG, RENUM, LINEL, ELLFMG, ELLP, and DIMES: Chain of programs for calculating and analyzing fluid flow through two-dimensional fracture networks -- theory and design

Description: This report describes some of the programs developed at Lawrence Berkeley Laboratory for network modelling. By themselves, these programs form a complete chain for the study of the equivalent permeability of two-dimensional fracture networks. FMG generates the fractures considered as line discontinuities, with any desired distribution of aperture, length, and orientation. The locations of these fractures on a plane can be either specified or generated randomly. The intersections of these fractu… more
Date: February 1, 1988
Creator: Billaux, Daniel; Bodea, Sorin & Long, Jane
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Criticality Experiments with Mixed Plutonium and Uranium Nitrate Solution at a Plutonium Fraction of 0.5 in Annular Cylindrical Geometry

Description: A series of critical experiments was completed with mixed plutonium-uranium solutions having Pu/(Pu + U) ratios of approximately 0.5. These experiments were a part of the Criticality Data Development Program between the United States Department of Energy (USDOE), and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. A complete description of, and data from, the experiments are included in this report. The experiments were performed with mixed plutonium-uranium solutions… more
Date: April 1, 1988
Creator: Lloyd, RC
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Educating scientists and engineers: grade school to grad school

Description: This report examines how and why students are drawn toward or deterred from pursuing a career in science or engineering. Schools, families, peers, informal education efforts-such as museums, science centers, special programs, and television— all play a role. The subtitle of this report—Grade School to Grad School—emphasizes that many factors and institutions must be understood as all one system.
Date: June 1988
Creator: United States. Congress. Office of Technology Assessment.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigation of the low enrichment conversion of the Texas A and M Nuclear Science Center Reactor

Description: The use of highly enriched uranium as a fuel research reactors is of concern due to the possibility of diversion for nuclear weapons applications. The Texas A M TRIGA reactor currently uses 70% enriched uranium in a FLIP (Fuel Life Improvement Program) fuel element manufactured by General Atomics. Thus fuel also contains 1.5 weight percent of erbium as a burnable poison to prolong useful core life. US university reactors that use highly enriched uranium will be required to covert to 20% or less… more
Date: January 1, 1988
Creator: Reuscher, Jon A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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1988 DOE model conference proceedings: Volume 3

Description: These Proceedings of the October 3 - 7, 1988, DOE Model Conference are a compilation of the papers that were presented in the technical or poster sessions at the conference. Papers and posters not submitted for publication are not included in the Proceedings. The Table of Contents lists the titles of papers as well as the names of the presenters. These individuals are not, in all cases, the primary authors of the papers published. The actual title pages, appearing later with the papers, show th… more
Date: January 1, 1988
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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DATING: A computer code for determining allowable temperatures for dry storage of spent fuel in inert and nitrogen gases

Description: The DATING (Determining Allowable Temperatures in Inert and Nitrogen Gases) code can be used to calculate allowable initial temperatures for dry storage of light-water-reactor spent fuel. The calculations are based on the life fraction rule using both measured data and mechanistic equations as reported by Chin et al. (1986). The code is written in FORTRAN and utilizes an efficient numerical integration method for rapid calculations on IBM-compatible personal computers. This report documents the… more
Date: December 1, 1988
Creator: Simonen, E. P. & Gilbert, E. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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