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Advanced Fuel Cycle Initiative AFC-1D, AFC-1G and AFC-1H End of FY-06 Irradiation Report

Description: The U. S. Advanced Fuel Cycle Initiative (AFCI) seeks to develop and demonstrate the technologies needed to transmute the long-lived transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products, thereby dramatically decreasing the volume of material requiring disposition and the long-term radiotoxity and heat load of high-level waste sent to a geologic repository. The AFC-1 irradiation experiments on transmutation fuels are expected to provide irradiation performance data on non-fertile and low-fertile fuel forms specifically, irradiation growth and swelling, helium production, fission gas release, fission product and fuel constituent migration, fuel phase equilibria, and fuel-cladding chemical interaction. Contained in this report are the to-date physics evaluations performed on three of the AFC-1 experiments; AFC-1D, AFC-1G and AFC-1H. The AFC-1D irradiation experiment consists of metallic non-fertile fuel compositions with minor actinides for potential use in accelerator driven systems and AFC-1G and AFC-1H irradiation experiments are part of the fast neutron reactor fuel development effort. The metallic fuel experiments and nitride experiment are high burnup analogs to previously irradiated experiments and are to be irradiated to = 40 at.% burnup and = 25 at.% burnup, respectively. Based on the results of the physics evaluations it has been determined that the AFC-1D experiment will remain in the ATR for approximately 4 additional cycles, the AFC-1G experiment for an additional 4-5 cycles, and the AFC-1H experiment for approximately 8 additional cycles, in order to reach the desired programmatic burnup. The specific irradiation schedule for these tests will be determined based on future physics evaluations and all results will be documented in subsequent reports.
Date: September 1, 2006
Creator: Advanced Fuel Cycle Initiative AFC-1D, AFC-1G and
Partner: UNT Libraries Government Documents Department
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Enforcement actions: Significant actions resolved, reactor licensees. Semiannual progress report, January--June 1997; Volume 16, Number 1, Part 2

Description: This compilation summarizes significant enforcement actions that have been resolved during the period (January--June 1997) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to reactor licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication.
Date: September 1, 1997
Partner: UNT Libraries Government Documents Department
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FINAL REPORT: The Role of RUB (related to ubiquitin) Family of Proteins in the Hormone Response

Description: The Rub pathway is a conserved protein modification pathway. RUB (called Rubp1 in budding yeast, Nedd8 in animals and RUB in plants) is a ubiquitin-like 76-amino acid protein. It covalently attaches to protein using an enzymatic machinery analogous to the enzymes that attach ubiquitin to its substrate proteins. However, the nature of the complement of Rub-modified proteins in organisms was not clear. From bioinformatics analyses, one can identify a Rub activating enzymes and Rub conjugating enzymes. However, in many cases, their biochemical properties were not described. In DOE-funded work, we made major advances in our understanding of the Rub pathway in yeast and plants, work that is applicable to other organisms as well. There is a multi-subunit enzyme called SCF in all eukaryotes. The SCF consists of several subunits that serve as a scaffold (the cullin, SKP and RBX subunits) and one subunit that interacts with the substrate. This cullin protein (called Cdc53p in yeast and CULLIN 1 in plants and animals) was a known Rub target. In this work, we identified additional Rub targets in yeast as the other cullin-like proteins Cul3p and Rtt101p. Additionally we described the conservation of the Rub pathway because plant RUB1 can conjugated to yeast Cdc53p- in yeast. In the model plant Arabidopsis thaliana, we characterized the Rub activating enzymes and showed that they are not biochemically equivalent. We also showed that the Rub pathway is essential in plants and characterized plants with reduced levels of rub proteins. These plants are affected in multiple developmental processes. We discovered that they over-produce ethylene as dark-grown seedlings. We characterized a mutant allele of CULLIN1 in Arabidopsis with impaired interaction with RBX and showed that it is unstable in vivo. We used our knowledge of monitoring protein degradation to map the degradation determinants in a plant transcription …
Date: March 27, 2013
Creator: Callis, Judy
Partner: UNT Libraries Government Documents Department
open access

Correlation of Buffet Boundaries Predicted From Wind-Tunnel Tests With Those Measured During Flight Tests on the F8F-1 and X-1 Airplanes -Transonic-Bump Method

Description: Memorandum presenting testing of semispan wing-fuselage models of the F8F-1 and X-1 airplanes in the 16-foot high-speed wind tunnel utilizing the transonic-bump method. The variations of lift coefficient with angle of attack and Mach number and pitching-moment coefficient with lift coefficient at various Mach numbers are presented for the models. The buffet boundaries were found to be in reasonable agreement with those determined from flight tests of full-scale airplanes.
Date: December 24, 1952
Creator: Martin, Andrew & Reed, James F.
Partner: UNT Libraries Government Documents Department
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Mixture Distribution in a Single-Row Radial Engine

Description: "The distribution of the fuel among the various cylinders of a Pratt and Whitney 1340 S1H1-G engine was determined by chemically analyzing samples of exhaust gas from each cylinder. The engine was operated in the 20-foot wind tunnel at different power outputs, specific fuel consumptions, and engine speeds. The results showed that the variation in the quality of the mixture among the different cylinders was approximately 4 percent and was independent of power output, specific fuel consumption, and engine speed. The results also showed that the top cylinders operated with a lower air-fuel ratio than the bottom cylinders" (p. 1).
Date: October 1936
Creator: Gerrish, Harold C. & Voss, Fred
Partner: UNT Libraries Government Documents Department
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Altitude-Wind-Tunnel Investigation of Performance of Several Propellers on YP-47M Airplane at High Blade Loading 2 - Curtiss 838-1C2-18R1 Four-Blade Propeller

Description: "An investigation was conducted in the Cleveland altitude wind tunnel to determine the performance of a Curtiss propeller with four 838-1C2-1SR1 blades on a YP-47M airplane at high blade loadings and engine powers. The study was made for a range of power coefficients between 0.30 and 1.00 at free-stream Mach numbers of 0.40 and 0.50. The results of the force measurements indicate primarily the trend of propeller efficiency for changes in power coefficient or advance-diameter ratio, inasmuch as corrections for the effects of tunnel-wall constriction on the installation have not been applied" (p. 1).
Date: November 26, 1946
Creator: Wallner, Lewis E. & Sorin, Solomon M.
Partner: UNT Libraries Government Documents Department
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Calibrations of Service Pitot Tubes in the Langley 24-Inch High-Speed Tunnel

Description: Report discusses calibration testing performed on a Kollsman type G-1 and an NAF No. 1 pitot tube at several Mach numbers and angles of attack. The effect of drain holes on the flow within the pitot tube was analyzed and the ability to estimate the error in the total pressure was created. The accuracy of the extrapolated and estimated values were found to be within reasonable limits.
Date: February 1946
Creator: Lindsey, W. F.
Partner: UNT Libraries Government Documents Department
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Synthesis and Characterization of Templated Ion Exchange Resins for the Selective Complexation of Actinide Ions

Description: The purpose of this research is to develop a polymeric extractant for the selective complexation of uranyl ions (and subsequently other actinyl and actinide ions) from aqueous solutions (lakes, streams, waste tanks and even body fluids). Chemical insights into what makes a good complexation site will be used to synthesize reagents tailor-made for the complexation of uranyl and other actinide ions. These insights, derived from studies of molecular recognition include ion coordination number and geometry, ionic size and ionic shape, as well as ion to ligand thermodynamic affinity. Selectivity for a specific actinide ion will be obtained by providing the polymers with cavities lined with complexing ligands so arranged as to match the charge, coordination number, coordination geometry, and size of the actinide metal ion. These cavity-containing polymers will be produced by using a specific ion (or surrogate) as a template around which monomeric complexing ligands will be polymerized. The complexing ligands will be ones containing functional groups known to form stable complexes with a specific ion and less stable complexes with other cations. Prior investigator's approaches for making templated resins for metal ions have had marginal success. We have extended and amended these methodologies in our work with Pb(II) and uranyl ion, by changing the order of the steps, by the inclusion of sonication, by using higher complex loading, and the selection of functional groups with better complexation constants. This has resulted in significant improvements to selectivity. The unusual shape of the uranyl ion suggests that this approach will result in even greater selectivities than already observed for Pb(II). Preliminary data obtained for uranyl templated polymers shows unprecedented selectivity and has resulted in the first ion selective electrode for uranyl ion.
Date: 2001-04~
Creator: Murray, George M.; Uy, O. Manual murragm1@aplcomm.jhuapl.edu & uyom1@aplmsg.jhuapl.edu
Partner: UNT Libraries Government Documents Department
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Steam generator tube failures

Description: A review and summary of the available information on steam generator tubing failures and the impact of these failures on plant safety is presented. The following topics are covered: pressurized water reactor (PWR), Canadian deuterium uranium (CANDU) reactor, and Russian water moderated, water cooled energy reactor (VVER) steam generator degradation, PWR steam generator tube ruptures, the thermal-hydraulic response of a PWR plant with a faulted steam generator, the risk significance of steam generator tube rupture accidents, tubing inspection requirements and fitness-for-service criteria in various countries, and defect detection reliability and sizing accuracy. A significant number of steam generator tubes are defective and are removed from service or repaired each year. This wide spread damage has been caused by many diverse degradation mechanisms, some of which are difficult to detect and predict. In addition, spontaneous tube ruptures have occurred at the rate of about one every 2 years over the last 20 years, and incipient tube ruptures (tube failures usually identified with leak detection monitors just before rupture) have been occurring at the rate of about one per year. These ruptures have caused complex plant transients which have not always been easy for the reactor operators to control. Our analysis shows that if more than 15 tubes rupture during a main steam line break, the system response could lead to core melting. Although spontaneous and induced steam generator tube ruptures are small contributors to the total core damage frequency calculated in probabilistic risk assessments, they are risk significant because the radionuclides are likely to bypass the reactor containment building. The frequency of steam generator tube ruptures can be significantly reduced through appropriate and timely inspections and repairs or removal from service.
Date: April 1, 1996
Creator: MacDonald, P. E.; Shah, V. N.; Ward, L. W. & Ellison, P. G.
Partner: UNT Libraries Government Documents Department
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Nuclear Regulatory Commission Issuances, Volume 42, No. 2

Description: This report include the issuances received during the specificed period (August 1995) from the NRC, the Atomic Safety and Licensing Boards, the Administrative Law Judges, and the Decisions on Petitions for Rule Making. In these issuances, the following areas were addressed: (1) Emergency planning at the University of Missouri, (2) Transfer of operating license at Plant Vogtle, (3) Discriminatory action against a whistle-blower at Millstone Units 1 & 2, (4) Regulatory issues related to embittlement and cracking at Oyster Creek, and (5) Age-related deterioration of reactor internals components at Pilgrim.
Date: August 1, 1995
Partner: UNT Libraries Government Documents Department
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GTL-1 Irradiation Summary Report

Description: The primary objective of the Gas Test Loop (GTL-1) miniplate experiment is to confirm acceptable performance of high-density (i.e., 4.8 g-U/cm3) U3Si2/Al dispersion fuel plates clad in Al-6061 and irradiated under the relatively aggressive Booster Fast Flux Loop (BFFL) booster fuel conditions, namely a peak plate surface heat flux of 450 W/cm2. As secondary objectives, several design and fabrication variations were included in the test matrix that may have the potential to improve the high-heat flux, high-temperature performance of the base fuel plate design.1, 2 The following report summarizes the life of the GTL-1 experiment through end of irradiation, including as-run neutronic analysis, thermal analysis and hydraulic testing results.
Date: January 1, 2012
Creator: Perez, D. M.; Chang, G. S.; Woolstenhulme, N. E. & Wachs, D. M.
Partner: UNT Libraries Government Documents Department
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Analysis of Fission Products on the AGR-1 Capsule Components

Description: The components of the AGR-1 irradiation capsules were analyzed to determine the retained inventory of fission products in order to determine the extent of in-pile fission product release from the fuel compacts. This includes analysis of (i) the metal capsule components, (ii) the graphite fuel holders, (iii) the graphite spacers, and (iv) the gas exit lines. The fission products most prevalent in the components were Ag-110m, Cs 134, Cs 137, Eu-154, and Sr 90, and the most common location was the metal capsule components and the graphite fuel holders. Gamma scanning of the graphite fuel holders was also performed to determine spatial distribution of Ag-110m and radiocesium. Silver was released from the fuel components in significant fractions. The total Ag-110m inventory found in the capsules ranged from 1.2×10 2 (Capsule 3) to 3.8×10 1 (Capsule 6). Ag-110m was not distributed evenly in the graphite fuel holders, but tended to concentrate at the axial ends of the graphite holders in Capsules 1 and 6 (located at the top and bottom of the test train) and near the axial center in Capsules 2, 3, and 5 (in the center of the test train). The Ag-110m further tended to be concentrated around fuel stacks 1 and 3, the two stacks facing the ATR reactor core and location of higher burnup, neutron fluence, and temperatures compared with Stack 2. Detailed correlation of silver release with fuel type and irradiation temperatures is problematic at the capsule level due to the large range of temperatures experienced by individual fuel compacts in each capsule. A comprehensive Ag 110m mass balance for the capsules was performed using measured inventories of individual compacts and the inventory on the capsule components. For most capsules, the mass balance was within 11% of the predicted inventory. The Ag-110m release from individual compacts …
Date: March 1, 2013
Creator: Demkowicz, Paul A.; Harp, Jason M.; Winston, Philip L. & Ploger, Scott A.
Partner: UNT Libraries Government Documents Department
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Spin Tests of 1/20-Scale Models of the Chance Vought Revised XF6U-1 and F6U-1 Airplanes, TED No. NACA 2390

Description: "An investigation has been conducted in the Langley 20-foot free-spinning tunnel on the 1/20-scale model of the Chance Vought XF6U-1 airplane altered to represent the XF6U-1 airplane as it will be spin-tested in flight, and also altered to represent the F6U-1 airplane as it will be produced for service use. Spin tests were made to determine the effects of control settings and movements at the normal loading. The results show that the spins obtained on the revised XF6U-1 airplane will be oscillatory in roll and yaw and that recoveries by rudder reversal will be rapid" (p. 1).
Date: June 28, 1948
Creator: Klinar, Walter J. & Berman, Theodore
Partner: UNT Libraries Government Documents Department
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Characterization of 200-UP-1 and 200-ZP-1 Operable Unit Aquifer Sediments and Batch Adsorption Distribution Coefficients for Contaminants of Concern--Fiscal Year 2006 Progress

Description: A total of six core samples from 200-UP/ZP-1 OUs and two additional outcrop samples were characterized during FY2006 by PNNL. One sample (C4971) was identified as slough and not used, but the five other samples identified as intact core samples were used for further analyses. The C4977 sample is gravel-sandy silt and C4990 samples are fine-sandy silt from the Ringold formation. Although the sediments from these two boreholes have similar mineralogical composition, C4990 samples show higher values of Fe oxide content, clay/silt content, and surface area compared those in C4977. The measured Tc Kd values ranged 0–0.2 mg/L for both samples, while U(VI) Kd for C4990 (4.23 mg/L) is much higher than that for C4977 (0.76 mg/L). A key finding from the Kd measurements is that detailed sediment and pore water characterization is necessary to understand the variation in Kd values seen in the empirical batch tests. Without the ancillary characterization of the sediments and pore waters, one might form misleading interpretations of the mechanisms that control the Kd values. Thus, physical, geochemical, and hydrological characterization of the sediments and pore waters should be conducted to increase our understanding of the site-specific Kd measurements. More details for methods and results will be provided in the formal technical report in FY 2007.
Date: September 25, 2006
Creator: Um, Wooyong & Serne, R. Jeffrey
Partner: UNT Libraries Government Documents Department
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Environmentally responsible recycling of thin-film cadmium telluride photovoltaic modules. Final technical report

Description: Continuing from the third quarter, all technical objectives of this Phase II SBIR work were previously and successfully completed. This report is therefore brief and contains two elements (1) a comparison of technical objective accomplishments to the stated goals in the original grant proposal (2) a summary of the third key element of this work; a market analysis for the developed recycling technology systems.
Date: September 9, 2002
Creator: Bohland, John
Partner: UNT Libraries Government Documents Department
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INL High Performance Building Strategy

Description: High performance buildings, also known as sustaina
Date: July 1, 2013
Creator: Fossum, Ernest & Ischay, Chris
Partner: UNT Libraries Government Documents Department
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COMPARISON OF BULK SHIELDING REACTOR CENTERLINE MEASUREMENTS IN WATER WITH PREDICTIONS

Description: Measurements of fast neutron and gamma ray dose rates in water along the centerline of the Bulk Shielding Reactor (BSR) are compared with predictions made by use of three available computer programs. It is found that the predictions are very dependent on the assumptions made concerning power distribution and that the more accurate descriptions of the source lead to predictions that agree with measurements to within 20% throughout thickness ranges as great as 100 centimeters of water. (auth)
Date: November 1, 1958
Creator: Casper, A.W.
Partner: UNT Libraries Government Documents Department
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Final Report for Regulation of Embryonic Development in Higher Plants

Description: The overall goal of the project was to define the cellular processes that underlie embryo development in plants at a mechanistic level. Our studies focused on a critical transcriptional regulator, Arabidopsis LEAFY COTYLEDON (LEC1), that is necessary and sufficient to induce processes required for embryo development. Because LEC1 regulates lipid accumulation during the maturation phase of embryo development, information about LEC1 may be useful in designing approaches to enhance biofuel production in plants. During the tenure of this project, we determined the molecular mechanisms by which LEC1 acts as a transcription factor in embryos. We also identified genes directly regulated by LEC1 and showed that many of these genes are involved in maturation processes. This information has been useful in dissecting the gene regulatory networks controlling embryo development. Finally, LEC1 is a novel isoform of a transcription factor that is conserved among eukaryotes, and LEC1 is active primarily in seeds. Therefore, we determined that the LEC1-type transcription factors first appeared in lycophytes during land plant evolution. Together, this study provides basic information that has implications for biofuel production.
Date: October 22, 2013
Creator: Harada, John J.
Partner: UNT Libraries Government Documents Department
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RERTR-12 Insertion 1 Irradiation Summary Report

Description: The Reduced Enrichment for Research and Test React
Date: September 1, 2012
Creator: Perez, D. M.; Lillo, M. A.; Chang, G. S. & Wools, N. E.
Partner: UNT Libraries Government Documents Department
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MITG Station 2 Build 1 Disassembly

Description: No Abstract. There is a duplicate copy. A decison was made not to send this to the OSTI library.
Date: November 18, 1982
Creator: Eck, Marshall B & Kling, Harry P
Partner: UNT Libraries Government Documents Department
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Data Report on Post-Irradiation Dimensional Change of AGC-1 Samples

Description: This report summarizes the initial dimensional changes for loaded and unloaded AGC-1 samples. The dimensional change for all samples is presented as a function of dose. The data is further presented by graphite type and applied load levels to illustrate the differences between graphite forming processes and stress levels within the graphite components. While the three different loads placed on the samples have been verified [ ref: Larry Hull’s report] verification of the AGC-1 sample temperatures and dose levels are expected in the summer of 2012. Only estimated dose and temperature values for the samples are presented in this report to allow a partial analysis of the results.
Date: June 1, 2012
Creator: Windes, William
Partner: UNT Libraries Government Documents Department
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