Sample records for reactor program quarterly

  1. Light-Water-Reactor safety research program. Quarterly progress report, January--March 1977

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    None

    The report summarizes the Argonne National Laboratory work performed during January, February, and March 1977 on water-reactor-safety problems. The following research and development areas are covered: (1) loss-of-coolant accident research: heat transfer and fluid dynamics; (2) transient fuel response and fission-product release program; (3) mechanical properties of zircaloy containing oxygen; and (4) steam-explosion studies.

  2. REACTOR PHYSICS QUARTERLY REPORT JANUARY, FEBRUARY, MARCH 1970

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Schmid, L. C.; Clayton, E. D.; Heineman, R. E.

    1970-05-01

    The objective of the Reactor Physics Quarterly Report is to inform the scientific community in a timely manner of the technical progress made on the many phases of reactor physics work within the laboratory. The report contains brief technical discussions of accomplishments in all areas where significant progress has been made during the quarter.

  3. The WSTIAC Quarterly. Volume 9, Number 3

    DTIC Science & Technology

    2010-01-25

    program .[8] THE THORIUM FUEL CYCLE AND LFTR POWER PLANT The thorium fuel cycle is based on a series of neutron absorp- tion and beta decay processes...the fig- ure is a graphite matrix moderated MSR reactor with fuel salt mixture (ThF4-U233F4) being circulated by a pump through the core and to a...the core as purified salt. As one of the unique safety features, a melt-plug at the reactor bottom would permit the reactor fluid fuel to be drained

  4. Development of a Model and Computer Code to Describe Solar Grade Silicon Production Processes

    NASA Technical Reports Server (NTRS)

    Srivastava, R.; Gould, R. K.

    1979-01-01

    The program aims at developing mathematical models and computer codes based on these models, which allow prediction of the product distribution in chemical reactors for converting gaseous silicon compounds to condensed-phase silicon. The major interest is in collecting silicon as a liquid on the reactor walls and other collection surfaces. Two reactor systems are of major interest, a SiCl4/Na reactor in which Si(l) is collected on the flow tube reactor walls and a reactor in which Si(l) droplets formed by the SiCl4/Na reaction are collected by a jet impingement method. During this quarter the following tasks were accomplished: (1) particle deposition routines were added to the boundary layer code; and (2) Si droplet sizes in SiCl4/Na reactors at temperatures below the dew point of Si are being calculated.

  5. PM-1 NUCLEAR POWER PLANT PROGRAM. Quarterly Progress Report No. 2 for June 1 to August 31, 1959

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sieg, J.S.; Smith, E.H.

    1959-10-01

    The objective of the contract is the design, development, fabrication, installation, and initial testing and operation of a prepackaged air- transportable pressurized water reactor nuclear power plant, the PM-1. The specified output is 1 Mwe and 7 million Btu/hr of heat. The plant is to be operational by March 1962. The principal efforts were completion of the plant parametric study and preparation of the preliminary design. A summary of design parameters is given. Systems development work included study and selection of packages for full-scale testing, a survey of in-core instrumentation techniques, control and instrumentation development, and development of components formore » the steam generator, condenser, and turbine generator, which are not commercially available. Reactor development work included completion of the parametric zeropower experiments and preparrtions for a flexible zeropower test program, a revision of plans for irradiation testing PM-1 fuel elements, initiation of a reactor flow test program, outliring of a heat tnansfer test program, completion of the seven-tube test section (SETCH-1) tests, and evaluation of control rod actuators leading to specification of a magnetic jack-type control rod drive similar to that reported in ANL-5768. Completion of the prelimirary design led to initiation of the final design effort, which will be the principal activity during the next two project quarters. Preparations for core fabrication included procurement of core cladding material for the zero-power teat core, arrangement with a subcontractor to convent UF/sub 6/ to UO/sub 2/ and to commence delivery of the oxide during the next quarter, development of fuel element fabrication and ultrasonic testing techniques, study of control rod materials, UO/sub 2/ recovery techniques, and boron analysis methods. Preliminary work on site preparation was pursued with receipt of USAEC approval for a location on the eastern slope of Warren Peak at Sundance, Wyoming. A survey of this site is underway. A preliminary Hazards Summary Report is in preparation. (For preceding period see MND-M-1812.) (auth)« less

  6. Light-water-reactor safety research program. Quarterly progress report, July--September 1975

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1975-01-01

    Progress is summarized in the following research and development areas: (1) loss-of-coolant accident research; heat transfer and fluid dynamics; (2) transient fuel response and fission-product release; and (3) mechanical properties of Zircaloy containing oxygen. Also included is an appendix on Kinetics of Fission Gas and Volatile Fission-product Behavior under Transient Conditions in LWR Fuel.

  7. Bulk shielding facility quarterly report, October, November, and December 1976

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hurt, III, S. S.; Lance, E. D.; Thomas, J. R.

    1977-08-01

    The BSR operated at an average power level of 1,836 kw for 78.01 percent of the time during October, November, and December. Water-quality control in both the reactor primary and secondary cooling systems was satisfactory. The PCA was used in training programs and was operated on two occasions when the University of Kentucky students actively participated in training laboratories.

  8. Expansion of high-temperature; high-pressure data set for coal gasification. Fifth quarterly report, September 28-December 28, 1985

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Solomon, P.R.; Serio, M.A.; Hamblen, D.G.

    1985-01-01

    During the fifth quarter, the gas mixing station for the high pressure reactor (HPR) system was completed. This station allows us to make reproducible binary mixtures of any two gases. It will be used for pyrolysis experiments in helium/nitrogen or oxygen/nitrogen and gasification experiments in helium/nitrogen or oxygen/nitrogen and gasification experiments in carbon dioxide/nitrogen. In addition, work began on modifications of the HPR system for high pressure (600 psig) operation. A limited amount of data was taken with the HPR system due to the modifications for the mixing station. However, the test plan experiments for pyrolysis in mixtures of heliummore » and nitrogen were completed. In general, there is a slightly higher yield of volatiles and lower yield of char as the helium content (heating rate) increases. A new technique for measuring char reactivity resulted from an Army SBIR program and was further developed under our other METC Contract. It has also been used to characterize chars generated under the current program. It was evident that the severity of the thermal treatment had a direct effect on char reactivity. In this regard, rapid heating to a relatively low temperature was most favorable while slow heating to a high temperature was least favorable. With regard to pressure effects on reactivity, our preliminary data indicated that higher pressures produce chars lower initial reactivity. A total of four experiments were done in the heated tube reactor (HTR) at 60 psig, 800/sup 0/C maximum tube temperature. The trends are the same as observed in the atmospheric pressure experiments for the same tube temperature and cold gas velocity. During the past quarter, a particle temperature (PT) model was under development for the high pressure entrained flow reactor (HPR). 5 refs., 5 figs.« less

  9. Catalyst and process development for synthesis gas conversion to isobutylene. Quarterly report, October 1, 1992--December 31, 1992

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Anthony, R.G.; Akgerman, A.

    1993-02-01

    The objectives of this project are to develop a new catalyst, the kinetics for this catalyst, reactor models for trickle bed, slurry and fixed bed reactors, and simulate the performance of fixed bed trickle flow reactors, slurry flow reactors, and fixed bed gas phase reactors for conversion of a hydrogen lean synthesis gas to isobutylene. The goals for the quarter include: (1) Conduct experiments using a trickle bed reactor to determine the effect of reactor type on the product distribution. (2) Use spherical pellets of silica as a support for zirconia for the purpose of increasing surface, area and performancemore » of the catalysts. (3) Conduct exploratory experiments to determine the effect of super critical drying of the catalyst on the catalyst surface area and performance. (4) Prepare a ceria/zirconia catalyst by the precipitation method.« less

  10. Physics of reactor safety. Quarterly report, January--March 1977. [LMFBR

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    None

    1977-06-01

    This report summarizes work done on reactor safety, Monte Carlo analysis of safety-related critical assembly experiments, and planning of DEMI safety-related critical experiments. Work on reactor core thermal-hydraulics is also included.

  11. Bulk Shielding Facility quarterly report, April, May and June 1984

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Corbett, B.L.; Lance, E.D.

    1984-12-01

    The BSR operated at an average power level of 1310 kW for 3.8% of the time during April, May, and June. Water-quality control in both the reactor primary and secondary cooling systems was satisfactory. The PCA was used in training startups and was operated on five occasions for the NBS and HEDL recheck of a previous experiment run on the LWR pressure vessel surveillance dosimetry improvement program.

  12. Quarterly Progress Report (January 1 to March 31, 1950)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Brookhaven National Laboratory

    This is the first of a series of Quarterly Reports. These reports will deal primarily with the progress made in our scientific program during a three months period. Those interested in matters pertaining to organization, administration, complete scientific program, personnel and other matters not directly involved in current scientific progress are referred to our Annual Progress Report which is issued in January. We have attempted to describe new information that appears significant, or of interest, to other scientists within the Atomic Energy Commission Laboratories. No effort has been made, however, to detail progress in each and every research project. Littlemore » or no reference will therefore be found to the projects in which progress during the current period is considered too inconclusive. Since our organizational structure is departmental, the work described herein is arranged in the following sequence: (1) Accelerator Project; (2) Biology Department; (3) Chemistry Department; (4) Instrumentation and Health Physic8 Department; (5) Medical Department; (6) Physics Department; and (7) Reactor Science and Engineering Department.« less

  13. Science in Flux: NASA's Nuclear Program at Plum Brook Station 1955-2005

    NASA Technical Reports Server (NTRS)

    Bowles, Mark D.

    2006-01-01

    Science in Flux traces the history of one of the most powerful nuclear test reactors in the United States and the only nuclear facility ever built by NASA. In the late 1950's NASA constructed Plum Brook Station on a vast tract of undeveloped land near Sandusky, Ohio. Once fully operational in 1963, it supported basic research for NASA's nuclear rocket program (NERVA). Plum Brook represents a significant, if largely forgotten, story of nuclear research, political change, and the professional culture of the scientists and engineers who devoted their lives to construct and operate the facility. In 1973, after only a decade of research, the government shut Plum Brook down before many of its experiments could be completed. Even the valiant attempt to redefine the reactor as an environmental analysis tool failed, and the facility went silent. The reactors lay in costly, but quiet standby for nearly a quarter-century before the Nuclear Regulatory Commission decided to decommission the reactors and clean up the site. The history of Plum Brook reveals the perils and potentials of that nuclear technology. As NASA, Congress, and space enthusiasts all begin looking once again at the nuclear option for sending humans to Mars, the echoes of Plum Brook's past will resonate with current policy and space initiatives.

  14. Thermal-Hydraulic Analysis of an Experimental Reactor Cavity Cooling System with Air. Part I: Experiments; Part II: Separate Effects Tests and Modeling

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Corradin, Michael; Anderson, M.; Muci, M.

    This experimental study investigates the thermal hydraulic behavior and the heat removal performance for a scaled Reactor Cavity Cooling System (RCCS) with air. A quarter-scale RCCS facility was designed and built based on a full-scale General Atomics (GA) RCCS design concept for the Modular High Temperature Gas Reactor (MHTGR). The GA RCCS is a passive cooling system that draws in air to use as the cooling fluid to remove heat radiated from the reactor pressure vessel to the air-cooled riser tubes and discharged the heated air into the atmosphere. Scaling laws were used to preserve key aspects and to maintainmore » similarity. The scaled air RCCS facility at UW-Madison is a quarter-scale reduced length experiment housing six riser ducts that represent a 9.5° sector slice of the full-scale GA air RCCS concept. Radiant heaters were used to simulate the heat radiation from the reactor pressure vessel. The maximum power that can be achieved with the radiant heaters is 40 kW with a peak heat flux of 25 kW per meter squared. The quarter-scale RCCS was run under different heat loading cases and operated successfully. Instabilities were observed in some experiments in which one of the two exhaust ducts experienced a flow reversal for a period of time. The data and analysis presented show that the RCCS has promising potential to be a decay heat removal system during an accident scenario.« less

  15. Synthoil hydrodynamics. Combined third and fourth quarterly report, December 1, 1975--May 31, 1976

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Brenner, H.; Prieve, D.C.; Fitch, B.

    1977-08-01

    This report deals with two-phase flow (gas and liquid) in a packed bed in the synthoil process reactor and preheater; in particular, nonuniform radial distribution of the liquid phase is studied. In addition, temperature profiles and possible instability of control due to the exothermic reactions are studied with respect to the synthoil reactor. This factor may limit the reactor diameter to about six inches. (LTN)

  16. METALLURGY DIVISION QUARTERLY REPORT FOR JULY, AUGUST, AND SEPTEMBER 1957

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    None

    1958-10-01

    Advanced Water Reactor Program. Three firings were made of initial closed-porosity fuel pellet bodies. Each firing coatained pellets of the composition 90 wt.% ThO/sub 2/-10 wt.%fl U0/sub 2/ with various additives and firing variables. Fast Power Breeder Reactor Program. To determine the potential usefulness of a Zr-5 wt. % Pu alloy, the fabricability of the alloy was tested. The manufacture of rod stock from which fuel and blanket elements for the Mark III loading of the EBR-1 were prcduced has been completed. The effect of irradiation on extruded and heat-treated U-2 wt.% Zr alloy for the EBR- 1 is reported.more » Fabrication procedures for making graphite-U/sub 3/O/sub 8/ test specimens for the TREAT Reactor were investigated. Advanced Engineering and Development. Ultrasonic bond tests were conducted on 590 EBR-1 Mark III blanket fuel elemeats. The blanket rods and part of the fuel rcds for the EBR-1 Mark III loading are being checked for cladding thickness by an eddy current system. Investigations of corrosionresistant Zr-Nb alloy were coatinued. Corrosion of MR alloys is being studied Ln support of the Mighty Mouse reactor program. Dynamic corrosion tests were performed on aluminum alloys, and results are included. Prcduction, Treatment, and Properties of Materials. The progress of the program of preparing highpurity Pu by fused salt electrolysis is summarized. Velocities of ultrasonic waves propagated in directions suitable for determining the room- temperature elastic moduli C/sub 12/, C/sub 13/, and C/sub 23/ of alpha U were determined. investigation of recrystallization in heavily coldrolled alpha- uranium sheet without a texture change was essentially concluded during this quarter. Selfdiffasion runs in polycrystalline uranium in the gamma phase, using the sputtering technique, have yielded a tentative value for the diffusion coefficient between 10/sup -8/ and 10/sup -7/ cm/sup 2/second. The preparation of high-purity U-Pan alloys is reponted. The data for the alpha-tobeta transformation temperatures in high-purity U and U-C alloys were confirmed by experiments on new specimens. Microstructure, density, and thermal arrest data were obtained for several injection cast, nominal U-5 wt.%fl fissium and U-8 wt.%fl fissium alloys. Phase diagrams are preseated for U-Mo and U-Ru alloys. Alloy Theory and The Nature of Solids. Four new isomorphs of Ti/sub 2/Ni have been discovered. Effects of Irradiation on Materials. The experimental and analytical work on the radial distribution of thermal neutrons within cylindrically shaped fuel specimens during irradiation was completed. (For preceding period see ANL-5790.) (W.L.H.)« less

  17. THE ARMOUR DUST FUELED REACTOR (ADFR). Quarterly Progress Report No. 2 For the Period May 21, 1958 to August 21, 1958

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Loewe, W.E.; Krucoff, D.

    1958-10-31

    Study of the ADFR concept included experimental work on fuel dust suspension stability and redispersibility, erosion, and dust deposition using the fuel dust circulation loop. Some theoretical work was done in the areas of reactor safety and breeding. (For preceding period -see AECU-3827.) (auth)

  18. Method of operating a neutronic reactor

    DOEpatents

    Woods, Wallace K.

    1976-05-25

    1. A method of operating a reactor having an active portion of a given length between a charging end and a discharging end, a first end region of the reactor extending from the charging end for one-quarter to one-third of said given length, a second end region extending from the discharging end for one-quarter to one-third of said given length, and a middle region extending between said end regions, said method comprising the steps of inserting end to end in the active region through the charging end a first group of bodies filling the middle region and a second group of bodies filling the first end region, irradiating the first and second groups of bodies while in the middle and first end regions, removing the first group from the reactor through the second end region, shifting the second group through the middle region to the second end region, inserting new first and second groups of bodies through the charging face into the middle and first end regions of the reactor, respectively, and irradiating the original second group and the new first and second groups while in the second end, middle, and first end regions, respectively, removing the original second group and the new first group from the reactor through the second end region, shifting the new second group through the middle region to the second end region, and irradiating the new second group again, whereby the first groups of bodies are irradiated only once and the second groups are irradiated twice.

  19. Computational modeling and experimental studies on NO{sub x} reduction under pulverized coal combustion conditions. Seventh quarterly technical progress report, July 1, 1996--September 30, 1996

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kumpaty, S.K.; Subramanian, K.; Nokku, V.P.

    1996-12-31

    During this quarter (July-August 1996), the experiments for nitric oxide reburning with a combination of methane and ammonia were conducted successfully. This marked the completion of gaseous phase experiments. Preparations are underway for the reburning studies with coal. A coal feeder was designed to suit our reactor facility which is being built by MK Fabrication. The coal feeder should be operational in the coming quarter. Presented here are the experimental results of NO reburning with methane/ammonia. The results are consistent with the computational work submitted in previous reports.

  20. THE ARMOUR DUST FUELED REACTOR (ADFR). Quarterly Progress Report No. 1 for the Period February 21, 1958 to May 21, 1958

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Loewe, W.E.; Krucoff, D.

    1958-10-31

    Work has begun on the ADFR, a reactor using a new fuel form -- fissionable dust carried in an inent gas. Temperatures in the range 2,000 to 3,000 deg F appear feasible in an all-ceramic system. Experimental study of the fuel form was initiated, and a loop to circulate the fuel dust was constructed. Initial operation is encouraging. Theoretical studies were carried on in the areas of reactor physics, heat transfer, and safety. (auth)

  1. Almost twenty years' search of transuranium isotopes in effluents discharged to air from nuclear power plants with VVER reactors.

    PubMed

    Hölgye, Z; Filgas, R

    2006-04-01

    Airborne effluents of 5 stacks (stacks 1-5) of three nuclear power plants, with 9 pressurized water reactors VVER of 4,520 MWe total power, were searched for transuranium isotopes in different time periods. The search started in 1985. The subject of this work is a presentation of discharge data for the period of 1998-2003 and a final evaluation. It was found that 238Pu, 239,240Pu, 241Am, 242Cm, and 244Cm can be present in airborne effluents. Transuranium isotope contents in most of the quarterly effluent samples from stacks 2, 4 and 5 were not measurable. Transuranium isotopes were present in the effluents from stack l during all 9 years of the study and from stack 3 since the 3rd quarter of 1996 as a result of a defect in the fuel cladding. A relatively high increase of transuranium isotopes in effluents from stack 3 occurred in the 3rd quarter of 1999, and a smaller increase occurred in the 3rd quarter of 2003. In each instance 242Cm prevailed in the transuranium isotope mixtures. 238Pu/239,240Pu, 241Am/239,240Pu, 242Cm/239,240Pu, and 244Cm/239,240Pu ratios in fuel for different burn-up were calculated, and comparison of these ratios in fuel and effluents was performed.

  2. Bench-scale demonstration of hot-gas desulfurization technology. Quarterly report, April 1 - June 30, 1996

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1996-12-31

    The US Department of Energy (DOE) Morgantown Energy Technology Center (METC) is sponsoring research in advanced methods for controlling contaminants in hot coal gasifier gas (coal gas) streams of integrated gasification combined-cycle (IGCC) power systems. The programs focus on hot-gas particulate removal and desulfurization technologies that match or nearly match the temperatures and pressures of the gasifier, cleanup system, and power generator. The work seeks to eliminate the need for expensive heat recovery equipment, reduce efficiency losses due to quenching, and minimize wastewater treatment costs. The goal of this project is to continue further development of the zinc titanate desulfurizationmore » and direct sulfur recovery process (DSRP) technologies by (1) scaling up the zinc titanate reactor system; (2) developing an integrated skid-mounted zinc titanate desulfurization-DSRP reactor system; (3) testing the integrated system over an extended period with real coal-as from an operating gasifier to quantify the degradative effect, if any, of the trace contaminants present in cola gas; (4) developing an engineering database suitable for system scaleup; and (5) designing, fabricating and commissioning a larger DSRP reactor system capable of operating on a six-fold greater volume of gas than the DSRP reactor used in the bench-scale field test. The work performed during the April 1 through June 30, 1996 period is described.« less

  3. Financial Implications of the Extended School Year.

    ERIC Educational Resources Information Center

    San Diego Unified School District, CA. Administrative Research Dept.

    This report considers the costs of three types of extended school year programs--all modifications of the quarter system--and compares these costs to the regular program. Compared against the traditional approach are: (1) a quarter system in which students attend three quarters a year and are off one quarter, meaning that 75% of all students are…

  4. 76 FR 50730 - Information Collection Being Submitted to the Office of Management and Budget for Review and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-16

    ... television programming. The records must be placed in the public file quarterly. The FCC Form 398, Children's Television Programming Reports, reflecting efforts made by the licensee during the preceding quarter, and... placed in the public file quarterly [Children's Television Programming Report (OMB control number 3060...

  5. The Savannah River Site's Groundwater Monitoring Program, third quarter 1991

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site's (SRS) Groundwater Monitoring Program. During third quarter 1991, EPD/EMS conducted extensive sampling of monitoring wells. Analytical results from third quarter 1991 are listed in this report.

  6. ENHANCED PRACTICAL PHOTOSYNTHETIC CO2 MITIGATION

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Dr. Gregory Kremer; Dr. David J. Bayless; Dr. Morgan Vis

    2001-07-25

    This quarterly report documents significant achievements in the Enhanced Practical Photosynthetic CO{sub 2} Mitigation project during the period from 4/03/2001 through 7/02/2001. Most of the achievements are milestones in our efforts to complete the tasks and subtasks that constitute the project objectives. Note that this version of the quarterly technical report is a revision to add the reports from subcontractors Montana State and Oak Ridge National Laboratories The significant accomplishments for this quarter include: Development of an experimental plan and initiation of experiments to create a calibration curve that correlates algal chlorophyll levels with carbon levels (to simplify future experimentalmore » procedures); Completion of debugging of the slug flow reactor system, and development of a plan for testing the pressure drop of the slug flow reactor; Design and development of a new bioreactor screen design which integrates the nutrient delivery drip system and the harvesting system; Development of an experimental setup for testing the new integrated drip system/harvesting system; Completion of model-scale bioreactor tests examining the effects of CO{sub 2} concentration levels and lighting levels on Nostoc 86-3 growth rates; Completion of the construction of a larger model-scale bioreactor to improve and expand testing capabilities and initiation of tests; Substantial progress on construction of a pilot-scale bioreactor; and Preliminary economic analysis of photobioreactor deployment. Plans for next quarter's work are included in the conclusions. A preliminary economic analysis is included as an appendix.« less

  7. The Savannah River Site`s Groundwater Monitoring Program, third quarter 1991

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During third quarter 1991, EPD/EMS conducted extensive sampling of monitoring wells. Analytical results from third quarter 1991 are listed in this report.

  8. 47 CFR 79.3 - Video description of video programming.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... programming distributor. (8) Children's Programming. Television programming directed at children 16 years of... provide 50 hours of video description per calendar quarter, either during prime time or on children's... calendar quarter, either during prime time or on children's programming, on each programming stream on...

  9. 47 CFR 79.3 - Video description of video programming.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... programming distributor. (8) Children's Programming. Television programming directed at children 16 years of... provide 50 hours of video description per calendar quarter, either during prime time or on children's... calendar quarter, either during prime time or on children's programming, on each programming stream on...

  10. Non-Intrusive Velocity Measurements with MTV During DCC Event in the HTTF

    NASA Technical Reports Server (NTRS)

    Andre, M. A.; Bardet, P. M.; Cadell, S. R.; Woods, B.; Burns, R. A.; Danehy, P. M.

    2017-01-01

    Velocity profiles are measured using molecular tagging velocimetry (MTV) in the high temperature test facility (HTTF) at Oregon State University during a depressurized conduction cooldown (DCC) event. The HTTF is a quarter scale electrically heated nuclear reactor simulator designed to replicate various accident scenarios. During a DCC, a double ended guillotine break results in the reactor pressure vessel (RPV) depressurizing into the reactor cavity and ultimately leading to air ingress in the reactor core (lock-exchange and gas diffusion). It is critical to understand the resulting buoyancy-driven flow to characterize the reactor self-cooling capacity through natural circulation. During tests conducted at ambient pressure and temperature, the RPV containing helium is opened (via the hot and cold legs) to a large vessel filled with nitrogen to simulate the atmosphere. The velocity profile on the hot leg pipe centerline is recorded at 10 Hz with MTV based on NO tracers. The precision of the velocimetry was measured to be 0.02 m/s in quiescent flow prior to the tests. A helium flow from the RPV is initially observed in the top quarter of the pipe. During the first 20 seconds of the event, helium flows out of the RPV with a maximum velocity below 2 m/s. The velocity profile transitions from parabolic to linear in character and decays slowly over the rest of the recording; peak velocities of 0.2 m/s are observed after 30 min. A counter-flow of nitrogen is also observed intermittently, which occurs at lower velocities (>0.1 m/s).

  11. 42 CFR 433.10 - Rates of FFP for program services.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ...; (B) 95 percent, for calendar quarters in CY 2017; (C) 94 percent, for calendar quarters in CY 2018... quarters in CY 2018; and (F) 100 percent, for calendar quarters in CY 2019 and all subsequent calendar...

  12. Environmental Hazards Assessment Program. Quarterly report, January 1994--March 1994

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1994-05-04

    The objectives of the EHAP program are to: Develop a holistic, national basis for risk assessment, risk management and risk communication; Develop a pool of talented scientists and experts in cleanup activities, especially in human health aspects, and; Identify needs and develop programs addressing the critical shortage of well-educated, highly-skilled technical and scientific personnel to address the health oriented aspects of environmental restoration and waste management. This report describes activities and reports on progress for the third quarter of year two (January-March, 1994) of the grant. To better accomplish objectives, grant efforts are organized into three major elements: The Crossroadsmore » of Humanity Series; Research, Science and Education Programs; and Program Management. The Crossroads of Humanity Series charted a new course, incorporating lessons learned during previous quarters into a series of programs designed to address environmental issues in a real world setting. Reports are included on the various research programs with milestones and deliverables from the third quarter.« less

  13. Direct coal liquefaction baseline design and system analysis. Quarterly report, January--March 1991

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1991-04-01

    The primary objective of the study is to develop a computer model for a base line direct coal liquefaction design based on two stage direct coupled catalytic reactors. This primary objective is to be accomplished by completing the following: a base line design based on previous DOE/PETC results from Wilsonville pilot plant and other engineering evaluations; a cost estimate and economic analysis; a computer model incorporating the above two steps over a wide range of capacities and selected process alternatives; a comprehensive training program for DOE/PETC Staff to understand and use the computer model; a thorough documentation of all underlyingmore » assumptions for baseline economics; and a user manual and training material which will facilitate updating of the model in the future.« less

  14. Chemistry Division. Quarterly progress report for period ending June 30, 1949

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1949-09-14

    Progress reports are presented for the following tasks: (1) nuclear and chemical properties of heavy elements (solution chemistry, phase rule studies); (2) nuclear and chemical properties of elements in the fission product region; (3) general nuclear chemistry; (4) radio-organic chemistry; (5) chemistry of separations processes; (6) physical chemistry and chemical physics; (7) radiation chemistry; (8) physical measurements and instrumentation; and (9) analytical chemistry. The program of the chemistry division is divided into two efforts of approximately equal weight with respect to number of personnel, chemical research, and analytical service for the Laboratory. The various research problems fall into the followingmore » classifications: (1) chemical separation processes for isolation and recovery of fissionable material, production of radioisotopes, and military applications; (2) reactor development; and (3) fundamental research.« less

  15. The Savannah River Site`s Groundwater Monitoring Program. First quarter 1992

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted during the first quarter of 1992. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program`s activities; and serves as an official document of the analytical results.

  16. 77 FR 14340 - Proposed Information Collection; Comment Request; Broadband Technology Opportunities Program...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-03-09

    ... (PPRs) to capture quarterly and annual reports for each project type (Infrastructure, Public Computer... Information Collection; Comment Request; Broadband Technology Opportunities Program (BTOP) Quarterly and..., which included competitive grants to expand public computer center capacity and innovative programs to...

  17. 47 CFR 79.3 - Video description of video programming.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... description per calendar quarter, either during prime time or on children's programming; (2) Television... technical capability necessary to pass through the video description, unless using the technology for... video description per calendar quarter during prime time or on children's programming, on each channel...

  18. 47 CFR 79.3 - Video description of video programming.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... description per calendar quarter, either during prime time or on children's programming; (2) Television... technical capability necessary to pass through the video description, unless using the technology for... video description per calendar quarter during prime time or on children's programming, on each channel...

  19. The Savannah River Site`s groundwater monitoring program. First quarter 1991

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted by EPD/EMS in the first quarter of 1991. In includes the analytical data, field data, data review, quality control, and other documentation for this program, provides a record of the program`s activities and rationale, and serves as an official document of the analytical results.

  20. H-division quarterly report, October--December 1977. [Lawrence Livermore Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1978-02-10

    The Theoretical EOS Group develops theoretical techniques for describing material properties under extreme conditions and constructs equation-of-state (EOS) tables for specific applications. Work this quarter concentrated on a Li equation of state, equation of state for equilibrium plasma, improved ion corrections to the Thomas--Fermi--Kirzhnitz theory, and theoretical estimates of high-pressure melting in metals. The Experimental Physics Group investigates properties of materials at extreme conditions of pressure and temperature, and develops new experimental techniques. Effort this quarter concerned the following: parabolic projectile distortion in the two-state light-gas gun, construction of a ballistic range for long-rod penetrators, thermodynamics and sound velocities inmore » liquid metals, isobaric expansion measurements in Pt, and calculation of the velocity--mass profile of a jet produced by a shaped charge. Code development was concentrated on the PELE code, a multimaterial, multiphase, explicit finite-difference Eulerian code for pool suppression dynamics of a hypothetical loss-of-coolant accident in a nuclear reactor. Activities of the Fluid Dynamics Group were directed toward development of a code to compute the equations of state and transport properties of liquid metals (e.g. Li) and partially ionized dense plasmas, jet stability in the Li reactor system, and the study and problem application of fluid dynamic turbulence theory. 19 figures, 5 tables. (RWR)« less

  1. ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. Quarterly Progress Report, October 1-December 31, 1963

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    None

    1964-02-15

    The ML-1 power plant did not operate during the report period; low power reactor physics and shielding experiments were conducted with the ML-1 reactor. Evaluation of moderate corrosion observed on aluminum parts exposed to the ML-1 shield solution indicated no loss of performance capability. Preliminary tests showed that the corrosion probably was caused by heavy metal ions or chlorides in the solution, Massive corrosion observed on the ML-1 fuel element lower spiders was attributed to sub-standard material; failure of some spiders was attributed to a combination of corrosion and sub-standard fabrication. Evaluation indicated that the upper spiders will perform satisfactorilymore » for the design lifetime. Modification, repair, and reassembly of the CSN-1A t-c set was completed. Operation demonstrated bearing stability, but showed that the turbine effective flow area was too large. A bypass flow path in the turbine was being corrected. The TCS-670 t-c set will be stored indefinitely. Since a commercial alternator will be used for the ML-1A, further development of the brushless alternator was postponed indefinitely. Evaluation revealed that the ML-1 improved precooler design was not compatible with ML-1A requirements. Operntion of the IB-17R-2 and -3 test elements in the GETR continued without incident. Preliminary design of the ML-1A power plant was initiated. Design of modifications to the GCRE facility to adapt it to testing the ML-1 reactor skid was initiated. (auth)« less

  2. ENVIRONMENTAL TECHNOLOGY VERIFICATION PROGRAM QUARTERLY REPORT - OCTOBER 2003

    EPA Science Inventory

    The U.S. EPA Environmental Technology Verification (ETV) Program provides credible performance data for commercial-ready environmental technologies to speed their implementation for the benefit of vendors, purchasers, permitters, and the public. The ETV Quarterly Reports provide...

  3. Status Report on NEAMS System Analysis Module Development

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hu, R.; Fanning, T. H.; Sumner, T.

    2015-12-01

    Under the Reactor Product Line (RPL) of DOE-NE’s Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, an advanced SFR System Analysis Module (SAM) is being developed at Argonne National Laboratory. The goal of the SAM development is to provide fast-running, improved-fidelity, whole-plant transient analyses capabilities. SAM utilizes an object-oriented application framework MOOSE), and its underlying meshing and finite-element library libMesh, as well as linear and non-linear solvers PETSc, to leverage modern advanced software environments and numerical methods. It also incorporates advances in physical and empirical models and seeks closure models based on information from high-fidelity simulations and experiments. This reportmore » provides an update on the SAM development, and summarizes the activities performed in FY15 and the first quarter of FY16. The tasks include: (1) implement the support of 2nd-order finite elements in SAM components for improved accuracy and computational efficiency; (2) improve the conjugate heat transfer modeling and develop pseudo 3-D full-core reactor heat transfer capabilities; (3) perform verification and validation tests as well as demonstration simulations; (4) develop the coupling requirements for SAS4A/SASSYS-1 and SAM integration.« less

  4. AR and TD Fossil Energy Materials Program. Quarterly progress report for the period ending December 31, 1981

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1982-04-01

    The ORNL Fossil Energy Materials Program Office compiles and issues this combined quarterly progress report from camera-ready copies submitted by each of the participating subcontractor organizations. This report of activities on the program is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FY 1982-1986 in which projects are organized according to fossil energy technologies. This report is divided into parts and chapters with each part describing projects related to a particular fossil energy technology. Chapters within a part provide details of the various projects associated with that technology.more » We hope this series of AR and TD Fossil Energy Materials Program quarterly progress reports will aid in the dissemination of information developed on the program. Plans for the program will be issued annually. A draft of the program plan for FY 1982 to 1986 has been prepared and is in the review process. The implementation of these plans will be reflected by these quarterly progress reports, and this dissemination of information will bw augmented by topical or final reports as appropriate.« less

  5. Assigning a Thesis Project In the Two-Year Architectural Technology Program

    ERIC Educational Resources Information Center

    Obermeyer, Thomas

    1977-01-01

    The "thesis project" assigned in the sixth quarter of the eight-quarter architectural technology program at the Dakota County Area Vocational-Technical Institute in Rosemont, Minnesota, requires the students to design a building for a local public service organization or government agency. The complete project will include a program, a…

  6. DESIGNING AN OPPORTUNITY FUEL WITH BIOMASS AND TIRE-DERIVED FUEL FOR COFIRING AT WILLOW ISLAND GENERATING STATION

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    K. Payette; D. Tillman

    During the period January 1, 2001-March 31, 2001, Allegheny Energy Supply Co., LLC (Allegheny) finalized the engineering of the Willow Island cofiring project, completed the fuel characterizations for both the Willow Island and Albright Generating Station projects, and initiated construction of both projects. Allegheny and its contractor, Foster Wheeler, selected appropriate fuel blends and issued purchase orders for all processing and mechanical equipment to be installed at both sites. This report summarizes the activities associated with the Designer Opportunity Fuel program, and demonstrations at Willow Island and Albright Generating Stations. The third quarter of the project involved completing the detailedmore » designs for the Willow Island Designer Fuel project. It also included complete characterization of the coal and biomass fuels being burned, focusing upon the following characteristics: proximate and ultimate analysis; higher heating value; carbon 13 nuclear magnetic resonance testing for aromaticity, number of aromatic carbons per cluster, and the structural characteristics of oxygen in the fuel; drop tube reactor testing for high temperature devolatilization kinetics and generation of fuel chars; thermogravimetric analyses (TGA) for char oxidation kinetics; and related testing. The construction at both sites commenced during this quarter, and was largely completed at the Albright Generating Station site.« less

  7. 7 CFR Exhibit E to Subpart N of... - Guide For Quarterly Performance Report

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 7 Agriculture 13 2012-01-01 2012-01-01 false Guide For Quarterly Performance Report E Exhibit E to.... 1944, Subpt. N, Exh. E Exhibit E to Subpart N of Part 1944—Guide For Quarterly Performance Report...: (___% Rate) ___ This Quarter Total ___ B. Use of Program Funds: Budgeted Amount ___ Expended Thru Last...

  8. 7 CFR Exhibit E to Subpart N of... - Guide For Quarterly Performance Report

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 7 Agriculture 13 2013-01-01 2013-01-01 false Guide For Quarterly Performance Report E Exhibit E to.... 1944, Subpt. N, Exh. E Exhibit E to Subpart N of Part 1944—Guide For Quarterly Performance Report...: (___% Rate) ___ This Quarter Total ___ B. Use of Program Funds: Budgeted Amount ___ Expended Thru Last...

  9. 7 CFR Exhibit E to Subpart N of... - Guide For Quarterly Performance Report

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 7 Agriculture 13 2014-01-01 2013-01-01 true Guide For Quarterly Performance Report E Exhibit E to.... 1944, Subpt. N, Exh. E Exhibit E to Subpart N of Part 1944—Guide For Quarterly Performance Report...: (___% Rate) ___ This Quarter Total ___ B. Use of Program Funds: Budgeted Amount ___ Expended Thru Last...

  10. 76 FR 36121 - Recent Posting to the Applicability Determination Index (ADI) Database System of Agency...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-21

    ..., and regulatory interpretations, and posts them on the ADI on a quarterly basis. In addition, the ADI... NSPS A, AAa Installation of a Capacitor Bank and Tuned Reactor 1000019 NSPS AAAA Conversion of Post... WWW Amended Design Capacity Reports A100001 Asbestos M Removal of Asbestos Containing Coating...

  11. Automotive Stirling engine development program

    NASA Technical Reports Server (NTRS)

    Ernst, W.; Richey, A.; Farrell, R.; Riecke, G.; Smith, G.; Howarth, R.; Cronin, M.; Simetkosky, M.; Meacher, J.

    1986-01-01

    This is the ninth Semiannual Technical Progress Report prepared under the Automotive Stirling Engine Development Program. It covers the twenty-eighth and twenty-ninth quarters of activity after award of the contract. Quarterly Technical Progress Reports related program activities from the first through the thirteenth quarters; thereafter, reporting was changed to a Semiannual format. This report summarizes the study of higher-power kinematic Stirling engines for transportation use, development testing of Mod I Stirling engines, and component development activities. Component development testing included successful conical fuel nozzle testing and functional checkout of Mod II controls and auxiliaries on Mod I engine test beds. Overall program philosophy is outlined and data and test results are presented.

  12. Impact of a telehealth and care management program for patients with chronic obstructive pulmonary disease.

    PubMed

    Au, David H; Macaulay, Dendy S; Jarvis, John L; Desai, Urvi S; Birnbaum, Howard G

    2015-03-01

    Improving outcomes and health resource use for patients with chronic obstructive pulmonary disease (COPD) care is a priority for health systems. The Health Buddy Program, a content-driven telehealth system coupled with care management, is designed to enhance patient education, self-management, and timely access to care. To examine the effects of the Health Buddy Program on resource use among Medicare patients with COPD who participated in a Centers for Medicare and Medicaid Services demonstration project from 2006 to 2010. Medicare fee-for-service beneficiaries with COPD who enrolled in the intervention at two participating clinics were propensity-score matched to similar patients with COPD identified from a 5% random sample of Medicare patients. Difference-in-difference analyses descriptively compared the program's effect on quarterly healthcare resource use over the 3-year study period compared with baseline. Negative binomial models estimated the association of the program with healthcare resource outcomes adjusting for significant (P<0.05) baseline differences post matching. The effect of the Health Buddy Program on quarterly all-cause and respiratory-related hospital admissions, hospital admissions for COPD exacerbations, and all-cause emergency department use was assessed after matching. Intervention (n=619) and matched control subjects (n=619) had similar baseline characteristics after matching. The Health Buddy Program was associated with 23% lower quarterly all-cause hospital admissions and 40% lower quarterly respiratory-related hospital admissions compared with baseline for intervention beneficiaries versus control subjects. In subgroup analyses, patients who engaged in the intervention during the study period (n=247) demonstrated significantly lower quarterly hospital admissions for COPD exacerbations. The Health Buddy Program was not associated with reductions in quarterly emergency department use. Results were robust in analyses that adjusted for significant differences in baseline characteristics after matching. A content-driven telehealth system combined with care management has the potential to improve health outcomes in Medicare beneficiaries with COPD.

  13. Calorimetry exchange program amendment to 3rd quarter CY92 report LLNL isotopic data

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Barnett, T.M.

    1996-08-01

    This report is a series of ammendments to the Calorimetry Exchange Quarterly Data Report for third quarter CY1992. The ammendment is needed due to reporting errors encountered in the Lawrence Livermore National Laboratory isotopic data.

  14. 77 FR 70165 - Proposed Information Collection Activity; Comment Request

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-23

    ... Quarterly Financial Report. OMB No.: 0970-0205. Description: This is a financial report submitted following... Programs Quarterly 62 4 20 4,960 Financial Report Estimated Total Annual Burden Hours: 4,960. In compliance... requirement to report program expenditures made in the [[Page 70166

  15. The Savannah River Site`s Groundwater Monitoring Program: Third quarter 1992

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rogers, C.D.

    1993-02-04

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During third quarter 1992, EPD/EMS conducted extensive sampling of monitoring wells. Table 1 lists those well series with constituents in the groundwater above Flag 2 during third quarter 1992, organized by location. Results from all laboratory analyses are used to generate this table. Specific conductance and pH data from the field also are included in this table.

  16. 45 CFR 265.1 - What does this part cover?

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ...), section 405 (administrative provisions), section 411(b) (report to Congress), and section 413 (annual... oversight responsibilities. (b) This part describes the information in the quarterly and annual reports that... quarterly Data Report, the quarterly Financial Report, and the Annual Report on State MOE Programs, as well...

  17. 45 CFR 265.1 - What does this part cover?

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... quarterly Data Report, the quarterly Financial Report, and the Annual Report on State MOE Programs, as well... data in the quarterly TANF Financial Report (or, as applicable, the Territorial Financial Report); and...), section 405 (administrative provisions), section 411(b) (report to Congress), and section 413 (annual...

  18. Expansion of high-temperature; high-pressure data set for coal gasification: Sixth quarterly report, December 28, 1985-March 28, 1986

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Solomon, P.R.; Serio, M.A.; Hamblen, D.G.

    1986-01-01

    During the sixth quarter, work was completed on modifications of the high pressure reactor (HPR) system for higher pressure (600 psig) operation. A series of pyrolysis experiments was completed in the HPR using mixtures of nitrogen and oxygen at various pressures and compositions. The original intention of the O/sub 2//N/sub 2/ experiments was to examine the effects of oxygen on the pyrolysis product distribution and the char reactivity. Unfortunately, at the temperature, residence time and pressure used for most of the experiments in this series (817/sup 0/C, 0.47 s, 26 psig) nearly complete oxidation of the char and volatile productsmore » occurred. Additional CO/sub 2/ gasification experiments were done to provide a database for revising the test plan. These were done at a variety of temperatures, pressures and CO/sub 2/ concentrations. The reactor was then switched back to nitrogen and additional pyrolysis experiments were done at high pressure (300 psig). When it was observed that the material balance was falling off slightly, it was decided to repeat some of the previous pyrolysis experiments at low pressure. There appeared to be a small, but systematic, reduction in char recovery. We continued to do char reactivity and surface area measurements for chars using the new non-isothermal technique described in the Fifth Quarterly report. A comparison was made of the results for char, tar, and gas yields for 1 atm and 5 atm (60 psig) experiments in the HTR. The asymptotic yield of about 10% was similar for both sets of experiments. A comparison was also made of tar yields for the Montana Rosebud coal from experiments in the HPR and HTR. The observed tar yields were in good agreement for similar experimental conditions. A preliminary version of a particle temperature model for the HPR was completed during the past quarter. 9 refs., 2 figs., 3 tabs.« less

  19. Surfactant studies for bench-scale operation

    NASA Technical Reports Server (NTRS)

    Hickey, Gregory S.; Sharma, Pramod K.

    1992-01-01

    A phase 2 study was initiated to investigate surfactant-assisted coal liquefaction, with the objective of quantifying the enhancement in liquid yields and product quality. This publication covers the first quarter of work. The major accomplishments were: the refurbishment of the high-pressure, high-temperature reactor autoclave, the completion of four coal liquefaction runs with Pittsburgh #8 coal, two each with and without sodium lignosulfonate surfactant, and the development of an analysis scheme for the product liquid filtrate and filter cake. Initial results at low reactor temperatures show that the addition of the surfactant produces an improvement in conversion yields and an increase in lighter boiling point fractions for the filtrate.

  20. Tribal Colleges Initiative project. Quarterly report, April 1--June 30, 1998

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1998-07-01

    The Tribal Colleges Initiative (TCI) grant is in the second year of funding from the US Department of Energy Environmental Management program. This quarterly report includes activities for the first three months (April 1--June 30, 1998) of the Year 2 funding period. The TCI program office requested each Tribal College to write a quarterly report of activities at their respective institutions. These reports are attached. These institutions are Southwestern Indian Polytechnic Institute (SIPI), Crownpoint Institute of Technology (CIT) and the Dine` College (DC, formerly Navajo Community College). The purpose of this program is to offer educational opportunities to Native Americansmore » in the environmental field.« less

  1. Oak Ridge Reservation Federal Facility Agreement. Quarterly report for the Environmental Restoration Program. Volume 4, July 1995--September 1995

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    This quarterly progress report satisfies requirements for the Environmental Restoration (ER) Program that are specified in the Oak Ridge Reservation Federal Facility Agreement (FFA) established between the U.S. Department of Energy (DOE), the U.S. Environmental Protection Agency (EPA), and the Tennessee Department of Environment and Conservation (TDEC). The reporting period covered herein is July through September 1995 (fourth quarter of FY 1995). Sections 1.1 and 1.2 provide respectively the milestones scheduled for completion during the reporting period and a list of documents that have been proposed for transmittal during the following quarter but have not been approved as FY 1995more » commitments.« less

  2. Coupled Neutronics Thermal-Hydraulic Solution of a Full-Core PWR Using VERA-CS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Clarno, Kevin T; Palmtag, Scott; Davidson, Gregory G

    2014-01-01

    The Consortium for Advanced Simulation of Light Water Reactors (CASL) is developing a core simulator called VERA-CS to model operating PWR reactors with high resolution. This paper describes how the development of VERA-CS is being driven by a set of progression benchmark problems that specify the delivery of useful capability in discrete steps. As part of this development, this paper will describe the current capability of VERA-CS to perform a multiphysics simulation of an operating PWR at Hot Full Power (HFP) conditions using a set of existing computer codes coupled together in a novel method. Results for several single-assembly casesmore » are shown that demonstrate coupling for different boron concentrations and power levels. Finally, high-resolution results are shown for a full-core PWR reactor modeled in quarter-symmetry.« less

  3. Implementation of a Systematic Accountability Framework in 2014 to Improve the Performance of the Nigerian Polio Program

    PubMed Central

    Tegegne, Sisay G.; MKanda, Pascal; Yehualashet, Yared G.; Erbeto, Tesfaye B.; Touray, Kebba; Nsubuga, Peter; Banda, Richard; Vaz, Rui G.

    2016-01-01

    Background. An accountability framework is a central feature of managing human and financial resources. One of its primary goals is to improve program performance through close monitoring of selected priority activities. The principal objective of this study was to determine the contribution of a systematic accountability framework to improving the performance of the World Health Organization (WHO)–Nigeria polio program staff, as well as the program itself. Methods. The effect of implementation of the accountability framework was evaluated using data on administrative actions and select process indicators associated with acute flaccid paralysis (AFP) surveillance, routine immunization, and polio supplemental immunization activities. Data were collected in 2014 during supportive supervision, using Magpi software (a company that provides service to collect data using mobile phones). A total of 2500 staff were studied. Results. Data on administrative actions and process indicators from quarters 2–4 in 2014 were compared. With respect to administrative actions, 1631 personnel (74%) received positive feedback (written or verbal commendation) in quarter 4 through the accountability framework, compared with 1569 (73%) and 1152 (61%) during quarters 3 and 2, respectively. These findings accorded with data on process indicators associated with AFP surveillance and routine immunization, showing statistically significant improvements in staff performance at the end of quarter 4, compared with other quarters. Conclusions. Improvements in staff performance and process indicators were observed for the WHO-Nigeria polio program after implementation of a systematic accountability framework. PMID:26823334

  4. 7 CFR 1435.301 - Annual estimates and quarterly re-estimates.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... CORPORATION, DEPARTMENT OF AGRICULTURE LOANS, PURCHASES, AND OTHER OPERATIONS SUGAR PROGRAM Flexible Marketing Allotments For Sugar § 1435.301 Annual estimates and quarterly re-estimates. (a) Not later than August 1... later than the beginning of each quarter of such crop year, the: (1) Quantity of sugar that will be...

  5. 7 CFR 1435.301 - Annual estimates and quarterly re-estimates.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... CORPORATION, DEPARTMENT OF AGRICULTURE LOANS, PURCHASES, AND OTHER OPERATIONS SUGAR PROGRAM Flexible Marketing Allotments For Sugar § 1435.301 Annual estimates and quarterly re-estimates. (a) Not later than August 1... later than the beginning of each quarter of such crop year, the: (1) Quantity of sugar that will be...

  6. 7 CFR 1435.301 - Annual estimates and quarterly re-estimates.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... CORPORATION, DEPARTMENT OF AGRICULTURE LOANS, PURCHASES, AND OTHER OPERATIONS SUGAR PROGRAM Flexible Marketing Allotments For Sugar § 1435.301 Annual estimates and quarterly re-estimates. (a) Not later than August 1... later than the beginning of each quarter of such crop year, the: (1) Quantity of sugar that will be...

  7. 7 CFR 1435.301 - Annual estimates and quarterly re-estimates.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... CORPORATION, DEPARTMENT OF AGRICULTURE LOANS, PURCHASES, AND OTHER OPERATIONS SUGAR PROGRAM Flexible Marketing Allotments For Sugar § 1435.301 Annual estimates and quarterly re-estimates. (a) Not later than August 1... later than the beginning of each quarter of such crop year, the: (1) Quantity of sugar that will be...

  8. 7 CFR 1435.301 - Annual estimates and quarterly re-estimates.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... CORPORATION, DEPARTMENT OF AGRICULTURE LOANS, PURCHASES, AND OTHER OPERATIONS SUGAR PROGRAM Flexible Marketing Allotments For Sugar § 1435.301 Annual estimates and quarterly re-estimates. (a) Not later than August 1... later than the beginning of each quarter of such crop year, the: (1) Quantity of sugar that will be...

  9. 78 FR 57885 - Report on the Criteria and Methodology for Determining the Eligibility of Candidate Countries for...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-20

    ...: Sources: Sources: Quarterly reporting Indicator tracking Quarterly tables reporting. Survey of MCC staff Quarterly reporting GAO Audits. Impact evaluations Survey of MCC staff. Similarly, the Board may consider a... reporting, documentation of changes in timing or scope of a threshold program in implementation, a survey of...

  10. Investigation of induced unimolecular decomposition for development of visible chemical lasers. Quarterly progress report, 1 August 1976--30 October 1976

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Piper, L G; Taylor, R L

    This report summarizes progress during the second quarterly period of the subject contract. The methods available for the production of excited electronic states following azide decomposition are summarized. It is concluded that an experiment designed to study the kinetics of and branching ratios for electronically excited products from azide radicals reactions will be most productive in elucidating excitation mechanisms for potential chemical lasers. A flow reactor is described in which these studies may be undertaken. The major feature of this apparatus is a clean azide radical source based upon the thermal decomposition of solid, ionic azides. The contruction of themore » experimental apparatus has been started.« less

  11. World Energy Data System (WENDS). Volume XI. Nuclear fission program summaries

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1979-06-01

    Brief management and technical summaries of nuclear fission power programs are presented for nineteen countries. The programs include the following: fuel supply, resource recovery, enrichment, fuel fabrication, light water reactors, heavy water reactors, gas cooled reactors, breeder reactors, research and test reactors, spent fuel processing, waste management, and safety and environment. (JWR)

  12. Nuclear Reactor Physics

    NASA Astrophysics Data System (ADS)

    Stacey, Weston M.

    2001-02-01

    An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.

  13. The Savannah River Site`s Groundwater Monitoring Program. Fourth quarter, 1989

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1989-12-31

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site`s Groundwater Monitoring Program. During fourth quarter 1989 (October--December), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. An explanation of flagging criteria for the fourth quarter is presented in the Flagging Criteria sectionmore » of this document. All analytical results from fourth quarter 1989 are listed in this report, which is distributed to all waste-site custodians.« less

  14. Correlation between quarter-point angle and nuclear radius

    NASA Astrophysics Data System (ADS)

    Ma, Wei-Hu; Wang, Jian-Song; Mukherjee, S.; Wang, Qi; Patel, D.; Yang, Yan-Yun; Ma, Jun-Bing; Ma, Peng; Jin, Shi-Lun; Bai, Zhen; Liu, Xing-Quan

    2017-04-01

    The correlation between quarter-point angle of elastic scattering and nuclear matter radius is studied systematically. Various phenomenological formulae with parameters for nuclear radius are adopted and compared by fitting the experimental data of quarter point angle extracted from nuclear elastic scattering reaction systems. A parameterized formula related to binding energy is recommended, which gives a good reproduction of nuclear matter radii of halo nuclei. It indicates that the quarter-point angle of elastic scattering is quite sensitive to the nuclear matter radius and can be used to extract the nuclear matter radius. Supported by National Natural Science Foundation of China (U1432247, 11575256), National Basic Research Program of China (973 Program)(2014CB845405 and 2013CB83440x) and (SM) Chinese Academy of Sciences President’s International Fellowship Initiative (2015-FX-04)

  15. FETC/EPRI Biomass Cofiring Cooperative Agreement. Quarterly technical report, April 1-June 30, 1997

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hughes, E.; Tillman, D.

    1997-12-01

    The FETC/EPRI Biomass Cofiring Program has accelerated the pace of cofiring development by increasing the testing activities plus the support activities for interpreting test results. Past tests conducted and analyzed include the Allen Fossil Plant and Seward Generating Station programs. On-going tests include the Colbert Fossil Plant precommercial test program, the Greenidge Station commercialization program, and the Blount St. Station switchgrass program. Tests in the formative stages included the NIPSCO cofiring test at Michigan City Generating Station. Analytical activities included modeling and related support functions required to analyze the cofiring test results, and to place those results into context. Amongmore » these activities is the fuel availability study in the Pittsburgh, PA area. This study, conducted for Duquesne Light, supports their initial investigation into reburn technology using wood waste as a fuel. This Quarterly Report, covering the third quarter of the FETC/EPRI Biomass Cofiring Program, highlights the progress made on the 16 projects funded under this cooperative agreement.« less

  16. Four-Quarter School Year. Results of an Exploratory Study of the Four-Quarter School Year in Metropolitan Atlanta.

    ERIC Educational Resources Information Center

    Bentley, Ernest L; And Others

    Six Atlanta, Georgia, school systems initiated a four-quarter school year program in 1968-69. An exploratory study was conducted to develop procedures and instruments for a comprehensive examination of the plan. Strong support exists in all groups interviewed -- superintendents and steering committee members, students, parents, teachers,…

  17. Defense Attache Saigon: RNAVF Quarterly Assessment. 2nd Quarter FY74.

    DTIC Science & Technology

    1974-02-01

    Military Assistance Command Vietnam MAP Military Assistance Program UNCLASSIFIED F IUNCLASSIFIES MASI Military Assistance Service Funded MATT Military Air...8217 operating the school. The average yearly budget is 2,~4oo,000 piasters, whiuh averages out to less than five cents per student per day. This is... average daily cargo handling rate of 959 M/T for the 2nd quarter FY711 shows continued improvement over the 773 M/T rate attained during the 1st quarter

  18. Accelerator driven reactors and nuclear waste management projects in the Czech Republic

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Janouch, Frantisek; Mach, Rostislav; Institute of Nuclear Physics, Rez near Prague

    1995-09-15

    The Czech Republic is almost the only country in the central Europe which continues with the construction of nuclear power reactors. Its small territory and dense population causes public worries concerning the disposal of the spent nuclear fuel. The Czech nuclear scientists and the power companies and the nuclear industries are therefore looking for alterative solutions. The Los Alamos ATW project had received a positive response in the Czech mass-media and even in the industrial and governmental quarters. The recent scientific symposium ''Accelerator driven reactors and nuclear waste management'' convened at the Liblice castle near Prague, 27-29.6. 1994 and sponsoredmore » by the Czech Energy Company CEZ, reviewed the competencies and experimental basis in the Czech republic and made the first attempt to formulate the national approach and to establish international collaboration in this area.« less

  19. Accelerator driven reactors and nuclear waste management projects in the Czech Republic

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Janouch, F.; Mach, R.

    1995-10-01

    The Czech Republic is almost the only country in the central Europe which continues with the construction of nuclear power reactors. Its small territory and dense population causes public worries concerning the disposal of the spent nuclear fuel. The Czech nuclear scientists and the power companies and the nuclear industries are therefore looking for alternative solutions. The Los Alamos ATW project had received a positive response in the Czech mass-media and even in the industrial and governmental quarters. The recent scientific symposium {open_quotes}Accelerator driven reactors and nuclear waste management{close_quotes} convened at the Liblice castle near Prague, 27-29. 6. 1994 andmore » sponsored by the Czech Energy Company CEZ, reviewed the competencies and experimental basis in the Czech republic and made the first attempt to formulate the national approach and to establish international collaboration in this area.« less

  20. 78 FR 77191 - Self-Regulatory Organizations; Chicago Board Options Exchange, Incorporated; Notice of Filing and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-20

    ... Effectiveness of a Proposed Rule Relating to the Quarterly Option Series Program December 16, 2013. Pursuant to... the Quarterly Options Series (``QOS'') Program to eliminate the cap on the number of additional series... eliminate the cap on the number of additional series that may be listed per expiration month for each QOS in...

  1. Impact of community tracer teams on treatment outcomes among tuberculosis patients in South Africa.

    PubMed

    Bronner, Liza E; Podewils, Laura J; Peters, Annatjie; Somnath, Pushpakanthi; Nshuti, Lorna; van der Walt, Martie; Mametja, Lerole David

    2012-08-07

    Tuberculosis (TB) indicators in South Africa currently remain well below global targets. In 2008, the National Tuberculosis Program (NTP) implemented a community mobilization program in all nine provinces to trace TB patients that had missed a treatment or clinic visit. Implementation sites were selected by TB program managers and teams liaised with health facilities to identify patients for tracing activities. The objective of this analysis was to assess the impact of the TB Tracer Project on treatment outcomes among TB patients. The study population included all smear positive TB patients registered in the Electronic TB Registry from Quarter 1 2007-Quarter 1 2009 in South Africa. Subdistricts were used as the unit of analysis, with each designated as either tracer (standard TB program plus tracer project) or non-tracer (standard TB program only). Mixed linear regression models were utilized to calculate the percent quarterly change in treatment outcomes and to compare changes in treatment outcomes from Quarter 1 2007 to Quarter 1 2009 between tracer and non-tracer subdistricts. For all provinces combined, the percent quarterly change decreased significantly for default treatment outcomes among tracer subdistricts (-0.031%; p < 0.001) and increased significantly for successful treatment outcomes among tracer subdistricts (0.003%; p = 0.03). A significant decrease in the proportion of patient default was observed for all provinces combined over the time period comparing tracer and non-tracer subdistricts (p = 0.02). Examination in stratified models revealed the results were not consistent across all provinces; significant differences were observed between tracer and non-tracer subdistricts over time in five of nine provinces for treatment default. Community mobilization of teams to trace TB patients that missed a clinic appointment or treatment dose may be an effective strategy to mitigate default rates and improve treatment outcomes. Additional information is necessary to identify best practices and elucidate discrepancies across provinces; these findings will help guide the NTP in optimizing the adoption of tracing activities for TB control.

  2. The magnetohydrodynamics coal-fired flow facility

    NASA Astrophysics Data System (ADS)

    1995-01-01

    In this quarterly technical progress report, UTSI reports on the status of a multitask contract to develop the technology for the steam bottoming portion of a MHD Steam Combined Cycle Power Plant. The report describes the facility maintenance and environmental work completed, status of completing technical reports and certain key administrative actions occurring during the quarter. With program resources at a minimum to closeout the MHD program, no further testing occurred during the quarter, but the DOE CFFF facility was maintained in a standby status with winterization, preventive maintenance and repairs accomplished as needed. Plans and preparations progressed for environmental actions needed at the site to investigate and characterize the groundwater and for removal/disposal of asbestos in the cooling tower. Work continued to progress on archiving the results of the MHD program.

  3. DOE Office of Scientific and Technical Information (OSTI.GOV)

    None

    Progress is reported on fundamental research in: crystal physics, reactions at metal surfaces, spectroscopy of ionic media, structure of metals, theory of alloying, physical properties, sintering, deformation of crystalline solids, x ray diffraction, metallurgy of superconducting materials, and electron microscope studies. Long-randge applied research studies were conducted for: zirconium metallurgy, materials compatibility, solid reactions, fuel element development, mechanical properties, non-destructive testing, and high-temperature materials. Reactor development support work was carried out for: gas-cooled reactor program, molten-salt reactor, high-flux isotope reactor, space-power program, thorium-utilization program, advanced-test reactor, Army Package Power Reactor, Enrico Fermi fast-breeder reactor, and water desalination program. Other programmore » activities, for which research was conducted, included: thermonuclear project, transuraniunn program, and post-irradiation examination laboratory. Separate abstracts were prepared for 30 sections of the report. (B.O.G.)« less

  4. The selective treatment of clinical mastitis based on on-farm culture results: II. Effects on lactation performance, including clinical mastitis recurrence, somatic cell count, milk production, and cow survival.

    PubMed

    Lago, A; Godden, S M; Bey, R; Ruegg, P L; Leslie, K

    2011-09-01

    The objective of this multi-state, multi-herd clinical trial was to report on the efficacy of using an on-farm culture system to guide strategic treatment decisions in cows with clinical mastitis. The study was conducted in 8 commercial dairy farms ranging in size from 144 to 1,795 cows from Minnesota, Wisconsin, and Ontario, Canada. A total of 422 cows affected with mild or moderate clinical mastitis in 449 quarters were randomly assigned to either (1) a positive-control treatment program or (2) an on-farm culture-based treatment program. Quarter cases assigned to the positive-control group received immediate on-label intramammary treatment with cephapirin sodium. Quarters assigned to the culture-based treatment program were not treated until the results of on-farm culture were determined after 18 to 24h of incubation. Quarters in the culture-based treatment program that had gram-positive growth or a mixed infection were treated according to label instruction using intramammary cephapirin sodium. Quarters assigned to the culture-based treatment program that had gram-negative or no-growth did not receive intramammary therapy. It was already reported in a companion paper that the selective treatment of clinical mastitis based on on-farm culture results decreases antibiotic use by half and tends to decrease milk withholding time without affecting short-term clinical and bacteriological outcomes. The present article reports on long-term outcomes of the aforementioned study. No statistically significant differences existed between cases assigned to the positive-control program and cases assigned to the culture-based treatment program in risk and days for recurrence of clinical mastitis in the same quarter (35% and 78 d vs. 43% and 82 d), linear somatic cell count (4.2 vs. 4.4), daily milk production (30.0 vs. 30.7 kg), and risk and days for culling or death events (28% and 160 d vs. 32% and 137 d) for the rest of the lactation after enrollment of the clinical mastitis case. In summary, the selective treatment of clinical mastitis based on on-farm culture resulted in no differences in long-term outcomes, such as recurrence of clinical mastitis in the same quarter, somatic cell count, milk production, and cow survival for the rest of the lactation after clinical mastitis. Copyright © 2011 American Dairy Science Association. Published by Elsevier Inc. All rights reserved.

  5. Lawrence Livermore National Laboratory safeguards and security quarterly progress report to the US Department of Energy quarter ending September 30, 1994

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Davis, G.; Mansur, D.L.; Ruhter, W.D.

    1994-10-01

    This report presents the details of the Lawrence Livermore National Laboratory safeguards and securities program. This program is focused on developing new technology, such as x- and gamma-ray spectrometry, for measurement of special nuclear materials. This program supports the Office of Safeguards and Securities in the following five areas; safeguards technology, safeguards and decision support, computer security, automated physical security, and automated visitor access control systems.

  6. NAWIG News: The Quarterly Newsletter of the Native American Wind Interest Group, Summer 2007

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    DOE's Wind Powering America program has initiated a quarterly NAWIG newsletter to present Native American wind information, including projects, interviews with pioneers, issues, WPA activities, and related events.

  7. 78 FR 26038 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-January Through March 2013

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-03

    ... provisions of the Social Security Act (the Act) and Public Health Service Act. We also issue various manuals...-month period along with a hyperlink to the full listing that is available on the CMS Web site or the... information and will be available earlier than we publish our quarterly notice. We believe the Web site list...

  8. 78 FR 67153 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-July Through September 2013

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-08

    ... provisions of the Social Security Act (the Act) and Public Health Service Act. We also issue various manuals...-month period along with a hyperlink to the full listing that is available on the CMS Web site or the... information and will be available earlier than we publish our quarterly notice. We believe the Web site list...

  9. 78 FR 45233 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-April Through June 2013

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-26

    ... provisions of the Social Security Act (the Act) and Public Health Service Act. We also issue various manuals...-month period along with a hyperlink to the full listing that is available on the CMS Web site or the... information and will be available earlier than we publish our quarterly notice. We believe the Web site list...

  10. Amarillo National Resource Center for Plutonium quarterly technical progress report, August 1, 1997--October 31, 1997

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    This report summarizes activities of the Amarillo National Resource Center for Plutonium during the quarter. The report describes the Electronic Resource Library; DOE support activities; current and future environmental health and safety programs; pollution prevention and pollution avoidance; communication, education, training, and community involvement programs; and nuclear and other material studies, including plutonium storage and disposition studies.

  11. ITS at a glance, volume 1, number 1.

    DOT National Transportation Integrated Search

    1996-04-01

    ITS at a glance is a quarterly newsletter produced by the U.S. Department of Transportation's Intelligent Transportation Systems (ITS) Joint Program Office (JPO). This quarterly publication will highlight and share major ITS developments within USDOT...

  12. The Savannah River Site`s Groundwater Monitoring Program, first quarter 1989

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site`s Groundwater Monitoring Program. During first quarter 1989 (January--March), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking watermore » standards. An explanation of flagging criteria for the first quarter is presented in the Flagging Criteria section of this document. All analytical results from first quarter 1989 are listed in this report, which is distributed to all waste-site custodians.« less

  13. The Savannah River Site`s Groundwater Monitoring Program, third quarter 1989

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site`s Groundwater Monitoring Program. During third quarter 1989 (July--September), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, backgroundmore » levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the third quarter is presented in the Flagging Criteria section of this document. All analytical results from third quarter 1989 are listed in this report, which is distributed to all waste-site custodians.« less

  14. The Savannah River Site's Groundwater Monitoring Program, third quarter 1989

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site's Groundwater Monitoring Program. During third quarter 1989 (July--September), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, backgroundmore » levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the third quarter is presented in the Flagging Criteria section of this document. All analytical results from third quarter 1989 are listed in this report, which is distributed to all waste-site custodians.« less

  15. The Savannah River Site's Groundwater Monitoring Program, first quarter 1989

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site's Groundwater Monitoring Program. During first quarter 1989 (January--March), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking watermore » standards. An explanation of flagging criteria for the first quarter is presented in the Flagging Criteria section of this document. All analytical results from first quarter 1989 are listed in this report, which is distributed to all waste-site custodians.« less

  16. Cigarette continuity programs and social support for smoking.

    PubMed

    Sumner, W; Dunaway, M; Dillman, D G

    1998-01-01

    To describe smokers' participation in cigarette continuity programs and the prevalence and structure of cooperative teams of smokers. Cross-sectional survey of smoking histories and continuity-program participation by individuals and their family members in a convenience sample of 176 current smokers at the University of Kentucky Chandler Medical Center, Lexington. Fisher exact test or chi2 tests were used to compare proportions. One of 3 smokers collected coupons for a continuity program. Three quarters of the collectors redeemed their own coupons, and one quarter gave coupons to another collector. Coupon collectors reported an average team size of more than 2 members. One fifth of collectors were teammates with another generation of family members, and one quarter of collectors aged 24 to 35 years were teammates with their children. Smokers were often aware of their relatives' coupon-collecting habits. Continuity programs have been a popular means of reinforcing smoking, especially within families and groups of friends. Continuity programs are novel in encouraging smoking and brand loyalty between generations. Continuity-program participants need to be aware of the risk of promoting smoking initiation by their children. Health advocates could use similar strategies to promote smoking cessation and prevention within families and other social groups.

  17. SP-100 Program: space reactor system and subsystem investigations

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Harty, R.B.

    1983-09-30

    For a space reactor power system, a comprehensive safety program will be required to assure that no undue risk is present. This report summarizes the nuclear safety review/approval process that will be required for a space reactor system. The documentation requirements are presented along with a summary of the required contents of key documents. Finally, the aerospace safety program conducted for the SNAP-10A reactor system is summarized. The results of this program are presented to show the type of program that can be expected and to provide information that could be usable in future programs.

  18. SP-100 program: Space reactor system and subsystem investigations

    NASA Astrophysics Data System (ADS)

    Harty, R. B.

    1983-09-01

    For a space reactor power system, a comprehensive safety program will be required to assure that no undue risk is present. The nuclear safety review/approval process that is required for a space reactor system is summarized. The documentation requirements are presented along with a summary of the required contents of key documents. Finally, the aerospace safety program conducted for the SNAP-10A reactor system is summarized. The results of this program are presented to show the type of program that is expected and to provide information that could be usable in future programs.

  19. Visualizing Coolant Flow in Sodium Reactor Subassemblies

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    None

    2010-01-01

    Uniformity of temperature controls peak power output. Interchannel cross-flow is the principal cross-assembly energy transport mechanism. The areas of fastest flow all occur at the exterior of the assembly. Further, the fast moving region winds around the assembly in a continuous swath. This Nek5000 simulation uses an unstructured mesh with over one billion grid points, resulting in five billion degrees of freedom per time slice. High speed patches of turbulence due to vertex shedding downstream of the wires persist for about a quarter of the wire-wrap periodic length. Credits: Science: Paul Fisher and Aleks Obabko, Argonne National Laboratory. Visualization: Hankmore » Childs and Janet Jacobsen, Lawrence Berkeley National Laboratory. This research used resources of the Argonne Leadership Computing Facility at Argonne National Laboratory, which is supported by the Office of Science of the U.S. Dept. of Energy under contract DE-AC02-06CH11357. This research was sponsored by the Department of Energy's Office of Nuclear Energy's NEAMS program.« less

  20. Impact of community tracer teams on treatment outcomes among tuberculosis patients in South Africa

    PubMed Central

    2012-01-01

    Background Tuberculosis (TB) indicators in South Africa currently remain well below global targets. In 2008, the National Tuberculosis Program (NTP) implemented a community mobilization program in all nine provinces to trace TB patients that had missed a treatment or clinic visit. Implementation sites were selected by TB program managers and teams liaised with health facilities to identify patients for tracing activities. The objective of this analysis was to assess the impact of the TB Tracer Project on treatment outcomes among TB patients. Methods The study population included all smear positive TB patients registered in the Electronic TB Registry from Quarter 1 2007-Quarter 1 2009 in South Africa. Subdistricts were used as the unit of analysis, with each designated as either tracer (standard TB program plus tracer project) or non-tracer (standard TB program only). Mixed linear regression models were utilized to calculate the percent quarterly change in treatment outcomes and to compare changes in treatment outcomes from Quarter 1 2007 to Quarter 1 2009 between tracer and non-tracer subdistricts. Results For all provinces combined, the percent quarterly change decreased significantly for default treatment outcomes among tracer subdistricts (−0.031%; p < 0.001) and increased significantly for successful treatment outcomes among tracer subdistricts (0.003%; p = 0.03). A significant decrease in the proportion of patient default was observed for all provinces combined over the time period comparing tracer and non-tracer subdistricts (p = 0.02). Examination in stratified models revealed the results were not consistent across all provinces; significant differences were observed between tracer and non-tracer subdistricts over time in five of nine provinces for treatment default. Conclusions Community mobilization of teams to trace TB patients that missed a clinic appointment or treatment dose may be an effective strategy to mitigate default rates and improve treatment outcomes. Additional information is necessary to identify best practices and elucidate discrepancies across provinces; these findings will help guide the NTP in optimizing the adoption of tracing activities for TB control. PMID:22871071

  1. 45 CFR 308.2 - Required program compliance criteria.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ..., State employment security agency, employment data, Department of Motor Vehicles, and credit bureaus... vehicles, and credit bureaus; (ii) Repeating attempts to locate quarterly and when new information is..., Department of Motor Vehicles, and credit bureaus; (ii) Repeating location attempts quarterly and when new...

  2. Summary of NR Program Prometheus Efforts

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    J Ashcroft; C Eshelman

    2006-02-08

    The Naval Reactors Program led work on the development of a reactor plant system for the Prometheus space reactor program. The work centered on a 200 kWe electric reactor plant with a 15-20 year mission applicable to nuclear electric propulsion (NEP). After a review of all reactor and energy conversion alternatives, a direct gas Brayton reactor plant was selected for further development. The work performed subsequent to this selection included preliminary nuclear reactor and reactor plant design, development of instrumentation and control techniques, modeling reactor plant operational features, development and testing of core and plant material options, and development ofmore » an overall project plan. Prior to restructuring of the program, substantial progress had been made on defining reference plant operating conditions, defining reactor mechanical, thermal and nuclear performance, understanding the capabilities and uncertainties provided by material alternatives, and planning non-nuclear and nuclear system testing. The mission requirements for the envisioned NEP missions cannot be accommodated with existing reactor technologies. Therefore concurrent design, development and testing would be needed to deliver a functional reactor system. Fuel and material performance beyond the current state of the art is needed. There is very little national infrastructure available for fast reactor nuclear testing and associated materials development and testing. Surface mission requirements may be different enough to warrant different reactor design approaches and development of a generic multi-purpose reactor requires substantial sacrifice in performance capability for each mission.« less

  3. 78 FR 35056 - Effectiveness of the Reactor Oversight Process Baseline Inspection Program

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-11

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0125] Effectiveness of the Reactor Oversight Process... the effectiveness of the reactor oversight process (ROP) baseline inspection program with members of... Nuclear Reactor Regulations, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301...

  4. Timing and effect of a safe routes to school program on child pedestrian injury risk during school travel hours: Bayesian changepoint and difference-in-differences analysis.

    PubMed

    DiMaggio, Charles; Chen, Qixuan; Muennig, Peter A; Li, Guohua

    2014-12-01

    In 2005, the US Congress allocated $612 million for a national Safe Routes to School (SRTS) program to encourage walking and bicycling to schools. We evaluated the effectiveness of a SRTS in controlling pedestrian injuries among school-age children. Bayesian changepoint analysis was applied to model the quarterly counts of pedestrian injuries among 5- to 19-year old children in New York City between 2001 and 2010 during school-travel hours in census tracts with and without SRTS. Overdispersed Poisson model was used to estimate difference-in-differences in injury risk between census tracts with and without SRTS following the changepoint. In SRTS-intervention census tracts, a change point in the quarterly counts of injuries was identified in the second quarter of 2008, which was consistent with the timing of the implementation of SRTS interventions. In census tracts with SRTS interventions, the estimated quarterly rates of pedestrian injury per 10,000 population among school-age children during school-travel hours were 3.47 (95% Credible Interval [CrI] 2.67, 4.39) prior to the changepoint, and 0.74 (95% CrI 0.30, 1.50) after the changepoint. There was no change in the average number of quarterly injuries in non-SRTS census tracts. Overdispersed Poisson modeling revealed that SRTS implementation was associated with a 44% reduction (95% Confidence Interval [CI] 87% decrease to 130% increase) in school-age pedestrian injury risk during school-travel hours. Bayesian changepoint analysis of quarterly counts of school-age pedestrian injuries successfully identified the timing of SRTS intervention in New York City. Implementation of the SRTS program in New York City appears to be effective in reducing school-age pedestrian injuries during school-travel hours.

  5. The Savannah River Site`s Groundwater Monitoring Program. Second quarter, 1991

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1992-01-10

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During second quarter 1991 EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Beginning in 1991, the flagging criteria are based on EPA drinking water standards and method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document.more » Analytical results from second quarter 1991 are listed in this report.« less

  6. The Savannah River Site's Groundwater Monitoring Program: Second quarter 1992

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rogers, C.D.

    1992-10-07

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site's (SRS) Groundwater Monitoring Program. During second quarter 1992, EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of criteria to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Since 1991, the flagging criteria have been based on the federal Environmental Protection Agency (EPA) drinking water standards and on method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria sectionmore » of this document. Analytical results from second quarter 1992 are listed in this report.« less

  7. A Review of Gas-Cooled Reactor Concepts for SDI Applications

    DTIC Science & Technology

    1989-08-01

    710 program .) Wire- Core Reactor (proposed by Rockwell). The wire- core reactor utilizes thin fuel wires woven between spacer wires to form an open...reactor is based on results of developmental studies of nuclear rocket propulsion systems. The reactor core is made up of annular fuel assemblies of...XE Addendum to Volume II. NERVA Fuel Development , Westinghouse Astronuclear Laboratory, TNR-230, July 15’ 1972. J I8- Rover Program Reactor Tests

  8. Special Inspector General for Iraq Reconstruction. Quarterly Report and Semiannual Report to the United States Congress

    DTIC Science & Technology

    2008-01-30

    Energy Fusion Cell, and allocations include $110 million for oil pipeline exclusion zones—which aim to prevent illegal tapping and sabotage of...sectors in Iraq. This quarter SIGIR highlights two of these programs: the electronic funds transfer ( EFT ) system and U.S. advisory support provided to...the Iraq Stock Exchange. eleCTroniC funds Transfer SIGIR noted last quarter that Iraq finally acti- vated an electronic funds transfer ( EFT ) system

  9. Special Inspector General for Iraq Reconstruction: Quarterly Report and Semiannual Report to the United States Congress

    DTIC Science & Technology

    2008-01-30

    Cell, and allocations include $110 million for oil pipeline exclusion zones—which aim to prevent illegal tapping and sabotage of pipelines—$51...This quarter SIGIR highlights two of these programs: the electronic funds transfer ( EFT ) system and U.S. advisory support provided to the Iraq Stock...Exchange. eleCTroniC funds Transfer SIGIR noted last quarter that Iraq finally acti- vated an electronic funds transfer ( EFT ) system. The United

  10. 75 FR 72858 - Agency Information Collection Activities; Revision of a Currently-Approved Information Collection...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-26

    ... Safety Assistance Programs (MCSAP).'' The information required consists of grant application preparation, quarterly reports and electronic data documenting the results of driver/vehicle inspections performed by the... Time per Response: Grant application preparation: 79.5 hours each; quarterly report preparation: 8...

  11. The Washington Academy of Biomedical Engineering (WABME) Quarterly Workshops: Clinical Problems and Engineering Solutions

    DTIC Science & Technology

    2005-01-01

    bioengineering programs and activities of The Catholic University of America, Georgetown University, The George Washington University and Howard ... University . A prime component of WABME activities is a quarterly series of research workshops, which bring together problem-rich biomedical disciplines and

  12. 75 FR 3926 - Submission for OMB Emergency Review: Comment Request

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-25

    ... DEPARTMENT OF LABOR Bureau of Labor Statistics Submission for OMB Emergency Review: Comment.... Agency: Bureau of Labor Statistics. Type of Review: New collection. Title of Collection: Quarterly Census... appropriation tasks the Bureau of Labor Statistics (BLS) Quarterly Census of Employment and Wages (QCEW) program...

  13. PV Working with Industry, 2nd Quarter, 2000

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Poole, L.; Moon, S.

    2000-06-29

    NREL PV Working With Industry is a quarterly newsletter devoted to the research, development, and deployment performed by NREL staff in concert with their industry and university partners. The Second Quarter, 2000, issue is titled ``Our Shared PV Future''. It contains a review of several important PV-related meetings held in the prior three months: the NCPV Program Review, the 16 European PV Conference, and year-2000 Earth Day activities in Denver, CO. The editorialist is Paul Maycock, Publisher of PV News.

  14. 78 FR 63516 - Initial Test Program of Emergency Core Cooling Systems for New Boiling-Water Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-24

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0134] Initial Test Program of Emergency Core Cooling....79.1, ``Initial Test Program of Emergency Core Cooling Systems for New Boiling-Water Reactors.'' This... emergency core cooling systems (ECCSs) for boiling- water reactors (BWRs) whose licenses are issued after...

  15. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mulder, R. U.; Benneche, P. E.; Hosticka, B.

    The objective of the DOE supported Reactor Sharing Program is to increase the availability of university nuclear reactor facilities to non-reactor-owning educational institutions. The educational and research programs of these users institutions is enhanced by the use of the nuclear facilities.

  16. Department of Defense Companies Participating in the Department of Defense Subcontracting Program. First Three Quarters Fiscal Year 1990

    DTIC Science & Technology

    1990-01-01

    This report presents a variety of subcontract data collected from Department of Defense (DOD) large business firms that have received at least one...award in excess of $500,000 ($1,000,000 for construction). Public Law 95-507 requires that these contractors establish a small business and small...disadvantaged business subcontracting program and report to DOD quarterly, using Standard Form 295, on subcontract awards made to these types of firms

  17. The United States Naval Nuclear Propulsion Program - Over 151 Million Miles Safely Steamed on Nuclear Power

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    None, None

    NNSA’s third mission pillar is supporting the U.S. Navy’s ability to protect and defend American interests across the globe. The Naval Reactors Program remains at the forefront of technological developments in naval nuclear propulsion and ensures a commanding edge in warfighting capabilities by advancing new technologies and improvements in naval reactor performance and reliability. In 2015, the Naval Nuclear Propulsion Program pioneered advances in nuclear reactor and warship design – such as increasing reactor lifetimes, improving submarine operational effectiveness, and reducing propulsion plant crewing. The Naval Reactors Program continued its record of operational excellence by providing the technical expertise requiredmore » to resolve emergent issues in the Nation’s nuclear-powered fleet, enabling the Fleet to safely steam more than two million miles. Naval Reactors safely maintains, operates, and oversees the reactors on the Navy’s 82 nuclear-powered warships, constituting more than 45 percent of the Navy’s major combatants.« less

  18. NEAMS Update. Quarterly Report for January - March 2014

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Stan, Marius

    2014-08-01

    This quarterly report covers the following points: A fully three-dimensional smeared cracking model has been implemented and tested in BISON; DAKOTA-BISON was used to study the parameters that govern heat transfer across the fuel-cladding; Calculations of grain boundary mobility in UO 2 have been extended to high temperatures; Mesh adaptivity is being employed in MARMOT simulations to increase computational efficiency; Molecular dynamics simulations have shown correlation between atomic displacements and the anisotropic thermal conductivity in UO 2; The SHARP team continues to address the application of the toolkit to assembly deformations driven by reactivity feedback; The Nek5000 team has extendedmore » the low-Machnumber capability to mixtures with multiple species; The generalized cross section library has been tested for various fuel assemblies and reactor types; and The subgroup cross-section interface was successfully implemented in PROTEUS-SN (page 6).« less

  19. Companies Participating in the Department of Defense Subcontracting Program. First Quarter, Fiscal Year 1995.

    DTIC Science & Technology

    1995-01-01

    disadvantaged businesses. Approximately 1,000 companies report these data each quarter during a fiscal year. The report has a section for each of the...subcontracting surveillance review, net value of subcontract awards, and the amount and percent of awards to small and disadvantaged businesses. The

  20. A Quarter Century of TV Food Advertising Targeted at Children.

    ERIC Educational Resources Information Center

    Gamble, Margaret; Cotugna, Nancy

    1999-01-01

    Analyzed current trends in television advertising targeting children, comparing results to the historical perspective of the last quarter century. Researchers evaluated 16 hours of Saturday morning children's programming on four network channels for commercial content based on Food Guide Pyramid and USDA Child Nutrition criteria. Overall,…

  1. 10 CFR 420.5 - Reports.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 3 2011-01-01 2011-01-01 false Reports. 420.5 Section 420.5 Energy DEPARTMENT OF ENERGY... § 420.5 Reports. (a) Each State receiving financial assistance under this part shall submit to the cognizant Regional Office Director a quarterly program performance report and a quarterly financial status...

  2. 75 FR 39619 - Proposed Information Collection (Quarterly Report of State Approving Agency) Activities Activity...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-09

    ... information needed to accurately reimburse State Approving Agencies (SAAs) for expenses incurred in the... reimburses SAAs for expenses incurred in the approval and supervision of education and training programs. SAAs are required to report their activities to VA quarterly and provide notices regarding which...

  3. 40 CFR 85.1904 - Voluntary emissions recall report; quarterly reports.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 40 Protection of Environment 19 2012-07-01 2012-07-01 false Voluntary emissions recall report; quarterly reports. 85.1904 Section 85.1904 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) CONTROL OF AIR POLLUTION FROM MOBILE SOURCES Emission Defect Reporting Requirements § 85.1904 Voluntary emissions...

  4. 40 CFR 85.1904 - Voluntary emissions recall report; quarterly reports.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 40 Protection of Environment 19 2014-07-01 2014-07-01 false Voluntary emissions recall report; quarterly reports. 85.1904 Section 85.1904 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) CONTROL OF AIR POLLUTION FROM MOBILE SOURCES Emission Defect Reporting Requirements § 85.1904 Voluntary emissions...

  5. 40 CFR 85.1904 - Voluntary emissions recall report; quarterly reports.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 18 2011-07-01 2011-07-01 false Voluntary emissions recall report; quarterly reports. 85.1904 Section 85.1904 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) CONTROL OF AIR POLLUTION FROM MOBILE SOURCES Emission Defect Reporting Requirements § 85.1904 Voluntary emissions...

  6. 40 CFR 85.1904 - Voluntary emissions recall report; quarterly reports.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 40 Protection of Environment 19 2013-07-01 2013-07-01 false Voluntary emissions recall report; quarterly reports. 85.1904 Section 85.1904 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) CONTROL OF AIR POLLUTION FROM MOBILE SOURCES Emission Defect Reporting Requirements § 85.1904 Voluntary emissions...

  7. Seasons: The National Native American AIDS Prevention Center Quarterly. Summer 1990-Autumn 1992.

    ERIC Educational Resources Information Center

    Rush, Andrea Green, Ed.

    1992-01-01

    Nine issues of this quarterly periodical examine AIDS prevention, education, and health care services for Native Americans and their communities. Major articles include personal narratives, interviews, roundtable discussions, program descriptions, guidelines for physicians and educators, and overviews of available services, and cover the following…

  8. 42 CFR 408.8 - Grace period and termination date.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... MEDICARE PROGRAM PREMIUMS FOR SUPPLEMENTARY MEDICAL INSURANCE General Provisions § 408.8 Grace period and termination date. (a) Grace period. (1) For all initial premium payments (monthly or quarterly), and subsequent monthly or quarterly payments, the grace period ends with the last day of the third month after...

  9. The Savannah River Site's Groundwater Monitoring Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1989-01-01

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site's Groundwater Monitoring Program. During fourth quarter 1989 (October--December), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. An explanation of flagging criteria for the fourth quarter is presented in the Flagging Criteria sectionmore » of this document. All analytical results from fourth quarter 1989 are listed in this report, which is distributed to all waste-site custodians.« less

  10. Research Program of a Super Fast Reactor

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Oka, Yoshiaki; Ishiwatari, Yuki; Liu, Jie

    2006-07-01

    Research program of a supercritical-pressure light water cooled fast reactor (Super Fast Reactor) is funded by MEXT (Ministry of Education, Culture, Sports, Science and Technology) in December 2005 as one of the research programs of Japanese NERI (Nuclear Energy Research Initiative). It consists of three programs. (1) development of Super Fast Reactor concept; (2) thermal-hydraulic experiments; (3) material developments. The purpose of the concept development is to pursue the advantage of high power density of fast reactor over thermal reactors to achieve economic competitiveness of fast reactor for its deployment without waiting for exhausting uranium resources. Design goal is notmore » breeding, but maximizing reactor power by using plutonium from spent LWR fuel. MOX will be the fuel of the Super Fast Reactor. Thermal-hydraulic experiments will be conducted with HCFC22 (Hydro chlorofluorocarbons) heat transfer loop of Kyushu University and supercritical water loop at JAEA. Heat transfer data including effect of grid spacers will be taken. The critical flow and condensation of supercritical fluid will be studied. The materials research includes the development and testing of austenitic stainless steel cladding from the experience of PNC1520 for LMFBR. Material for thermal insulation will be tested. SCWR (Supercritical-Water Cooled Reactor) of GIF (Generation-4 International Forum) includes both thermal and fast reactors. The research of the Super Fast Reactor will enhance SCWR research and the data base. The research period will be until March 2010. (authors)« less

  11. High-temperature gas-cooled reactor technology development program. Annual progress report for period ending December 31, 1982

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kasten, P.R.; Rittenhouse, P.L.; Bartine, D.E.

    1983-06-01

    During 1982 the High-Temperature Gas-Cooled Reactor (HTGR) Technology Program at Oak Ridge National Laboratory (ORNL) continued to develop experimental data required for the design and licensing of cogeneration HTGRs. The program involves fuels and materials development (including metals, graphite, ceramic, and concrete materials), HTGR chemistry studies, structural component development and testing, reactor physics and shielding studies, performance testing of the reactor core support structure, and HTGR application and evaluation studies.

  12. NASA-EPA automotive thermal reactor technology program

    NASA Technical Reports Server (NTRS)

    Blankenship, C. P.; Hibbard, R. R.

    1972-01-01

    The status of the NASA-EPA automotive thermal reactor technology program is summarized. This program is concerned primarily with materials evaluation, reactor design, and combustion kinetics. From engine dynamometer tests of candidate metals and coatings, two ferritic iron alloys (GE 1541 and Armco 18-SR) and a nickel-base alloy (Inconel 601) offer promise for reactor use. None of the coatings evaluated warrant further consideration. Development studies on a ceramic thermal reactor appear promising based on initial vehicle road tests. A chemical kinetic study has shown that gas temperatures of at least 900 K to 1000 K are required for the effective cleanup of carbon monoxide and hydrocarbons, but that higher temperatures require shorter combustion times and thus may permit smaller reactors.

  13. Coal desulfurization in a rotary kiln combustor

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cobb, J.T. Jr.

    1991-04-22

    The focus of our work during the first quarter of 1991 was on combustion tests at the PEDCO rotary kiln reactor at North American Rayon (NARCO) plant in Elizabethton, TN. The tests had essentially tow related objectives: (a) to obtain basic data on the combustion of anthracite culm in a rotary kiln reactor, and (b) upon the test results, determine how best to proceed with our own planned program at the Humphrey Charcoal kiln in Brookville, PA. The rationale for the tests at PEDCO arose from process analysis which posted red flags on the feasibility of burning low-grade, hard-to-burn fuelsmore » like anthracite culms, in the rotary kiln. The PEDCO unit afforded a unique opportunity to obtain some quick answers at low cost. Two different anthracite culm fuels were tested: a so-called Jeddo culm with an average heating value of 7000 Btu/lb, and a relatively poorer culm, and Emerald'' culm, with an average heating value of 5000 Btu/lb. An attempt was also made to burn a blend of the Emerald culm with bituminous coal in 75/25 percent proportions. This report describes the tests, their chronology, and preliminary results. As it turned out, the PEDCO unit is not configured properly for the combustion of anthracite culm. As a result, it proved difficult to achieve a sustained period of steady-state combustion operation, and combustion efficiencies were low even when supplemental fuel was used to aid combustion of the culm. 1 fig., 2 tabs.« less

  14. Pre-Licensing Evaluation of Legacy SFR Metallic Fuel Data

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Yacout, A. M.; Billone, M. C.

    2016-09-16

    The US sodium cooled fast reactor (SFR) metallic fuel performance data that are of interest to advanced fast reactors applications, can be attributed mostly to the Integral Fast Reactor (IFR) program between 1984 and 1994. Metallic fuel data collected prior to the IFR program were associated with types of fuel that are not of interest to future advanced reactors deployment (e.g., previous U-Fissium alloy fuel). The IFR fuels data were collected from irradiation of U-Zr based fuel alloy, with and without Pu additions, and clad in different types of steels, including HT9, D9, and 316 stainless-steel. Different types of datamore » were generated during the program, and were based on the requirements associated with the DOE Advanced Liquid Metal Cooled Reactor (ALMR) program.« less

  15. Expanded scope of training and education programs at the UFTR

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Vernetson, W.G.; Whaley, P.M.

    1985-01-01

    Historically, the University of Florida Training Reactor (UFTR) has been used to train both hot and cold license reactor operator candidates in intensive two- and three-week training programs consisting of a correlated set of classroom lectures, hands-on reactor operations, and laboratory exercises. These training programs provide nuclear plant operating staff with fundamental operational experience in understanding, controlling, and evaluating subcritical multiplication, reactivity effects, reactivity manipulations, and reactor operations; a sufficient number of startups and shutdowns is also assured. The UDTR is also used in a nuclear engineering course entitled ''Principles of Nuclear Reactor Operations.'' The purpose of this paper ismore » to report the results of efforts to redirect and refine tractor operations educational and training programs at the UFTR.« less

  16. Retaining minorities in engineering: Assessment of a program prototype

    NASA Astrophysics Data System (ADS)

    Good, Jennifer Marie (Phillips)

    Program assessment is an essential part of healthy program development. Assessment should include multiple considerations, dimensions, and outcomes that match the program's objectives. As a newly formed retention program, the Auburn University Minority Engineering Program, designed to help pre-engineering minority students make the transition into their freshman year of university studies, incorporated evaluation and assessment into all three components of the program (the interactive learning laboratory, critical-thinking workshops, and Sunday-evening tutorials) from the program's inception. If students successfully adapted to the university environment and the demands of the pre-engineering course of study, then retention of minority students in the College of Engineering should improve. Data were gathered on the students involved in the various program components. Students who entered the Minority Engineering Program were pre- and posttested on three standardized subtests (critical thinking, mathematics, and science reasoning) of the Collegiate Assessment of Academic Proficiency. The first-quarter grade-point averages of the students were also gathered to compare their grades to freshman students in previous quarters within the College of Engineering. Qualitative data were also gathered on this same group of students. An analysis of the data revealed that student achievement is affected by involvement in the Minority Engineering Program. Specifically, the first quarter grade point averages of students involved in the program exceeded those of their peers in earlier years of study prior to the program's existence. In addition, mathematics and science reasoning scores on standardized tests increased pre- to postintervention. Comments collected in journals and files also demonstrated use of critical-thinking and problem-solving skills employed by the students. Recommendations for alterations of the program were made based on the outcome of the program evaluation. Further suggestions for research in minority engineering program development and evaluation were also discussed.

  17. Engineering and Physics Optimization of Breed and Burn Fast Reactor Systems; NUCLEAR ENERGY RESEARCH INITIATIVE (NERI) QUARTERLY PROGRESS REPORT

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pavel Hejzlar, Peter Yarsky, Mike Driscoll, Dan Wachs, Kevan Weaver, Ken Czerwinski, Mike Pope, James Parry, Theron D. Marshall, Cliff B. Davis, Dustin Crawford, Thomas Hartmann, Pradip Saha; Hejzlar, Pavel; Yarsky, Peter

    2005-01-31

    This project is organized under four major tasks (each of which has two or more subtasks) with contributions among the three collaborating organizations (MIT, INEEL and ANL-West): Task A: Core Physics and Fuel Cycle; Task B: Core Thermal Hydraulics; Task C: Plant Design; Task D: Fuel Design The lead PI, Michael J. Driscoll, has consolidated and summarized the technical progress submissions provided by the contributing investigators from all sites, under the above principal task headings.

  18. Regulation of coal polymer degradation by fungi. Eighth quarterly report, [January--March 1996

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Irvine, R.L.; Bumpus, J.A.

    1996-07-28

    Progress is reported on solubilization of low-rank coal by enzyme activity derived from Trametes versicolor or P. chrysosporium. Specifically during the reporting period efforts were directed towards the determining the effect of pH on solubilization of leonardite, the role of laccase in low coal solubilization and metabolism, the decolorization of soluble coal macromolecule by P. chrysosprium and T. versicolor in solid agar gel, and the solubilization of low rank coal in slurry cultures and solid phase reactors.

  19. The RERTR Program status and progress

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Travelli, A.

    1995-12-01

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. The major events, findings, and activities of 1995 are reviewed after a brief summary of the results which the RERTR Program had achieved by the end of 1994. The revelation that Iraq was on the verge of developing a nuclear weapon at the time of the Gulf War, and that it was planning to do so by extracting HEU from the fuel of its research reactors, has given new impetus and urgency to the RERTR commitment of eliminating HEU use in research and test reactors worldwide.more » Development of advanced LEU research reactor fuels is scheduled to begin in October 1995. The Russian RERTR program, which aims to develop and demonstrate within the next five years the technical means needed to convert Russian-supplied research reactors to LEU fuels, is now in operation. A Statement of Intent was signed by high US and Chinese officials, endorsing cooperative activities between the RERTR program and Chinese laboratories involved in similar activities. Joint studies of LEU technical feasibility were completed for the SAFARI-I reactor in South Africa and for the ANS reactor in the US. A new study has been initiated for the FRM-II reactor in Germany. Significant progress was made on several aspects of producing {sup 99}Mo from fission targets utilizing LEU instead of HEU. A cooperation agreements is in place with the Indonesian BATAN. The first prototypical irradiation of an LEU metal-foil target for {sup 99}Mo production was accomplished in Indonesia. The TR-2 reactor, in Turkey, began conversion. SAPHIR, in Switzerland, was shut down. LEU fuel fabrication has begun for the conversion of two more US reactors. Twelve foreign reactors and nine domestic reactors have been fully converted. Approximately 60 % of the work required to eliminate the use of HEU in US-supplied research reactors has been accomplished.« less

  20. 10 CFR Appendix D to Part 73 - Physical Protection of Irradiated Reactor Fuel in Transit, Training Program Subject Schedule

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Physical Protection of Irradiated Reactor Fuel in Transit... Irradiated Reactor Fuel in Transit, Training Program Subject Schedule Pursuant to the provision of § 73.37 of... reactor fuel is required to assure that individuals used as shipment escorts have completed a training...

  1. 10 CFR Appendix D to Part 73 - Physical Protection of Irradiated Reactor Fuel in Transit, Training Program Subject Schedule

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Physical Protection of Irradiated Reactor Fuel in Transit... Irradiated Reactor Fuel in Transit, Training Program Subject Schedule Pursuant to the provision of § 73.37 of... reactor fuel is required to assure that individuals used as shipment escorts have completed a training...

  2. Quarter Scale RLV Multi-Lobe LH2 Tank Test Program

    NASA Technical Reports Server (NTRS)

    Blum, Celia; Puissegur, Dennis; Tidwell, Zeb; Webber, Carol

    1998-01-01

    Thirty cryogenic pressure cycles have been completed on the Lockheed Martin Michoud Space Systems quarter scale RLV composite multi-lobe liquid hydrogen propellant tank assembly, completing the initial phases of testing and demonstrating technologies key to the success of large scale composite cryogenic tankage for X33, RLV, and other future launch vehicles.

  3. Illinois Association for Counseling and Development (IACD) Quarterly, 1990.

    ERIC Educational Resources Information Center

    Illovsky, Michael E., Ed.

    1990-01-01

    This document consists of the four issues of the "IACD Quarterly" published in 1990. Articles in this volume include: (1) "A Comprehensive Program for Reducing School Anxieties in College Students" (David Ross); (2) "Issues in Child Custody Determination in Illinois" (Amy Jo Buwick); (3) "Finding Meaning in the Here and Now Through Gestalt Therapy…

  4. Drinking by University Dormitory Residents: Its Prediction and Amelioration.

    ERIC Educational Resources Information Center

    Schall, Mathew; And Others

    1991-01-01

    College students (n=200) in 2 university dormitories completed alcohol and drug use survey in fall quarter and 130 students were readministered questionnaire at end of spring quarter after peer-directed alcohol awareness program was implemented in a particular dormitory. Retest results showed no difference in drinking behavior of residents in…

  5. Department of Defense Companies Participating in the Department of Defense Subcontracting Program, First Quarter Fiscal Year 1994

    DTIC Science & Technology

    1994-01-01

    disadvantaged businesses. Approximately 1,000 companies report these data each quarter during a fiscal year. The report has section for each of the Military...subcontracting surveillance review, net value of subcontract awards, and the amount and percent of awards to small and small disadvantaged businesses. The

  6. Straight Talk on Student Loans. PPI Policy Brief

    ERIC Educational Resources Information Center

    Shireman, Robert

    2004-01-01

    The federal government provides student loans for college and graduate school in two ways: by: (1) guaranteeing bank loans; and (2) by lending directly to students. Approximately three-quarters of federal student loans are guaranteed and one-quarter are direct. In the guaranteed loan program, a 40-year-old system, banks lend students money and…

  7. 45 CFR 286.265 - When are quarterly reports due?

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... shall begin collecting financial data for the TANF Financial Report as of the initial effective date of its TANF program. (b) Each Tribe must submit its TANF Data Report and TANF Financial Report within 45... 45 Public Welfare 2 2010-10-01 2010-10-01 false When are quarterly reports due? 286.265 Section...

  8. Pittsburgh Technical Health Training Institute Demonstration Project; Quarterly Report.

    ERIC Educational Resources Information Center

    Kishkunas, Louis J.

    This fifth quarterly report covers the period June 15, 1967 to December 15, 1967 of a project aimed at demonstrating a faster method of training higly qualified workers for the health field. During this period, nurse aides were trained in a pilot program based upon the educational objectives derived from entry level behavioral specifications…

  9. PFBC HGCU Test Facility. Technical progress report No. 24, Third quarter, CY 1995

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    This is the twenty-fourth and final Technical Progress Report submitted to the Department of Energy (DOE) in connection with the cooperative agreement between the DOE and Ohio Power Company for the Tidd PFBC Hot Gas Clean Up Test Facility. This report covers the work completed during the Third Quarter of CY 1995. All activity this quarter was directed toward the completion of the program final report. A draft copy of the final report was forwarded to DOE during this quarter, and DOE submitted their comments on the report to AEPSC. DOE requested that Westinghouse write an appendix to the reportmore » covering the performance of the fail-safe regenerator devices during Tad operation, and Westinghouse subsequently prepared the appendix. Additional DOE comments were incorporated into the report, and it will be issued in camera-ready form by the end of October, 1995, which is the program end date. Appendix 1 presents the results of filter candle posttest examination by Westinghouse performed on selected filter candles following final shutdown of the system.« less

  10. SNAP (Space Nuclear Auxiliary Power) reactor overview. Final report, June 1982-December 1983

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Voss, S.S.

    1984-08-01

    The SNAP reactor programs are outlined in this report. A summary of the program is included along with a technical outline of the SER, S2DR, SNAP 10A/SNAPSHOT, S8ER, and S8DR reactor systems. Specifications of the designs, the design logic and a conclusion outlining some of the program weaknesses are given.

  11. [Development of cell content and shedding of Prototheca spp. in milk from infected udder quarters of cows].

    PubMed

    Tenhagen, B A; Hille, A; Schmidt, A; Heuwieser, W

    2005-02-01

    It was the objective of this study to analyse shedding patterns and somatic cell counts in cows and quarters infected with Prototheca spp. and to evaluate two approaches to identify infected animals by somatic cell count (SCC) or by bacteriological analysis of pooled milk samples. Five lactating dairy cows, chronically infected with Prototheca spp. in at least one quarter were studied over 11 weeks to 13 months. Quarter milk samples and a pooled milk sample from 4 quarters were collected aseptically from all quarters of the cows on a weekly basis. Culture results of quarter milk and pooled samples were compared using cross tabulation. SCC of quarter milk samples and of pooled samples were related to the probability of detection in the infected quarters and cows, respectively. Shedding of Prototheca spp. was continuous in 2 of 8 quarters. In the other quarters negative samples were obtained sporadically or over a longer period (1 quarter). Overall, Prototheca spp. were isolated from 83.6% of quarter milk samples and 77.0% of pooled milk samples of infected quarters and cows. Somatic cell counts were higher in those samples from infected quarters that contained the algae than in negative samples (p < 0.0001). The same applied for composite samples from infected cows. Positive samples had higher SCC than negative samples. However, Prototheca spp. were also isolated from quarter milk and pooled samples with physiological SCC (i.e. < 10(5)/ml). Infected quarters that were dried off did not develop acute mastitis. However, drying off had no effect on the infection, i.e. samples collected at calving or 8 weeks after dry off still contained Prototheca spp. Results indicate that pre-selection of cows to be sampled for Prototheca spp. by SCC and the use of composite samples are probably inadequate in attempts to eradicate the disease. However, due to intermittent shedding of the algae in some cows, single herd sampling using quarter milk samples probably also fails to detect all infected cases. Therefore, continuous monitoring of problem cows with clinical mastitis or increased SCC in herds during eradication programs is recommended.

  12. QUARTERLY TECHNICAL PROGRESS REPORT, JULY, AUGUST, SEPTEMBER 1967.

    DTIC Science & Technology

    Contents: Circuit research program; Hardware systems research; Computer system software research; Illinois pattern recognition computer: ILLIAC II... service , use, and program development; IBM 7094/1401 service , use, and program development; Problem specifications; General laboratory information.

  13. Establishing the SECME model in the District of Columbia. Quarterly report, 1 January 1994--31 March 1994

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Vikers, R.G.

    1994-05-01

    During this quarter, many program activities were held to help SECME teachers and counselors implement, improve and strengthen SECME school programs in the District of Columbia. Teachers were actively engaged in enhanced instructional techniques, ideas, processes and resources to help them enrich their students` learning experience. Students are busily participating in hands-on instructional activities and preparing for the SECME competition where they are learning to excel in a competitive environment designed to help them make the most of their school experience.

  14. Advanced Small Modular Reactor Economics Status Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Harrison, Thomas J.

    2014-10-01

    This report describes the data collection work performed for an advanced small modular reactor (AdvSMR) economics analysis activity at the Oak Ridge National Laboratory. The methodology development and analytical results are described in separate, stand-alone documents as listed in the references. The economics analysis effort for the AdvSMR program combines the technical and fuel cycle aspects of advanced (non-light water reactor [LWR]) reactors with the market and production aspects of SMRs. This requires the collection, analysis, and synthesis of multiple unrelated and potentially high-uncertainty data sets from a wide range of data sources. Further, the nature of both economic andmore » nuclear technology analysis requires at least a minor attempt at prediction and prognostication, and the far-term horizon for deployment of advanced nuclear systems introduces more uncertainty. Energy market uncertainty, especially the electricity market, is the result of the integration of commodity prices, demand fluctuation, and generation competition, as easily seen in deregulated markets. Depending on current or projected values for any of these factors, the economic attractiveness of any power plant construction project can change yearly or quarterly. For long-lead construction projects such as nuclear power plants, this uncertainty generates an implied and inherent risk for potential nuclear power plant owners and operators. The uncertainty in nuclear reactor and fuel cycle costs is in some respects better understood and quantified than the energy market uncertainty. The LWR-based fuel cycle has a long commercial history to use as its basis for cost estimation, and the current activities in LWR construction provide a reliable baseline for estimates for similar efforts. However, for advanced systems, the estimates and their associated uncertainties are based on forward-looking assumptions for performance after the system has been built and has achieved commercial operation. Advanced fuel materials and fabrication costs have large uncertainties based on complexities of operation, such as contact-handled fuel fabrication versus remote handling, or commodity availability. Thus, this analytical work makes a good faith effort to quantify uncertainties and provide qualifiers, caveats, and explanations for the sources of these uncertainties. The overall result is that this work assembles the necessary information and establishes the foundation for future analyses using more precise data as nuclear technology advances.« less

  15. QUARTERLY TECHNICAL PROGRESS REPORT, JULY, AUGUST, SEPTEMBER 1966.

    DTIC Science & Technology

    Contents: Circuit research program; Hardware systems research; Software systems research program; Numerical methods, computer arithmetic and...artificial languages; Library automation; Illiac II service , use, and program development; IBM service , use, and program development; Problem specifications; Switching theory and logical design; General laboratory information.

  16. 34 CFR 668.9 - Relationship between clock hours and semester, trimester, or quarter hours in calculating Title...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 34 Education 3 2010-07-01 2010-07-01 false Relationship between clock hours and semester, trimester, or quarter hours in calculating Title IV, HEA program assistance. 668.9 Section 668.9 Education Regulations of the Offices of the Department of Education (Continued) OFFICE OF POSTSECONDARY EDUCATION...

  17. 78 FR 46905 - Tobacco Transition Program; Final Assessment Procedures

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-02

    ... adjusted market share for the 39th and 40th quarterly assessment payments due on September 30, 2014, will be based on the assessed entity's market activity during April 1 to June 30, 2014. The 40th quarterly assessment will be initially determined by using the same adjusted market share of an entity that was used to...

  18. 34 CFR 690.63 - Calculation of a Federal Pell Grant for a payment period.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... fall through the following spring, or three quarters in the fall, winter, and spring, none of which... program using an academic calendar that includes two semesters or trimesters in the fall through the following spring, or three quarters in the fall, winter, and spring; and (B) Does not provide at least 30...

  19. 45 CFR 265.4 - When are quarterly reports due?

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 45 Public Welfare 2 2013-10-01 2012-10-01 true When are quarterly reports due? 265.4 Section 265.4 Public Welfare Regulations Relating to Public Welfare OFFICE OF FAMILY ASSISTANCE (ASSISTANCE PROGRAMS), ADMINISTRATION FOR CHILDREN AND FAMILIES, DEPARTMENT OF HEALTH AND HUMAN SERVICES DATA COLLECTION AND REPORTING REQUIREMENTS § 265.4 When are...

  20. Peach Bottom Atomic Power Station recirc pipe dose rates with zinc injection and condenser replacement

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    DiCello, D.C.; Odell, A.D.; Jackson, T.J.

    1995-03-01

    Peach Bottom Atomic Power Station (PBAPS) is located near the town of Delta, Pennsylvania, on the west bank of the Susquehanna River. It is situated approximately 20 miles south of Lancaster, Pennsylvania. The site contains two boiling water reactors of General Electric design and each rated at 3,293 megawatts thermal. The units are BWR 4s and went commercial in 1977. There is also a decommissioned high temperature gas-cooled reactor on site, Unit 1. PBAPS Unit 2 recirc pipe was replaced in 1985 and Unit 3 recirc pipes replaced in 1988 with 326 NGSS. The Unit 2 replacement pipe was electropolished,more » and the Unit 3 pipe was electropolished and passivated. The Unit 2 brass condenser was replaced with a Titanium condenser in the first quarter of 1991, and the Unit 3 condenser was replaced in the fourth quarter of 1991. The admiralty brass condensers were the source of natural zinc in both units. Zinc injection was initiated in Unit 2 in May 1991, and in Unit 3 in May 1992. Contact dose rate measurements were made in standard locations on the 28-inch recirc suction and discharge lines to determine the effectiveness of zinc injection and to monitor radiation build-up in the pipe. Additionally, HPGe gamma scans were performed to determine the isotopic composition of the oxide layer inside the pipe. In particular, the specific ({mu}Ci/cm{sup 2}) of Co-60 and Zn-65 were analyzed.« less

  1. NEAMS Update. Quarterly Report for October - December 2011.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bradley, K.

    2012-02-16

    The Advanced Modeling and Simulation Office within the DOE Office of Nuclear Energy (NE) has been charged with revolutionizing the design tools used to build nuclear power plants during the next 10 years. To accomplish this, the DOE has brought together the national laboratories, U.S. universities, and the nuclear energy industry to establish the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program. The mission of NEAMS is to modernize computer modeling of nuclear energy systems and improve the fidelity and validity of modeling results using contemporary software environments and high-performance computers. NEAMS will create a set of engineering-level codes aimedmore » at designing and analyzing the performance and safety of nuclear power plants and reactor fuels. The truly predictive nature of these codes will be achieved by modeling the governing phenomena at the spatial and temporal scales that dominate the behavior. These codes will be executed within a simulation environment that orchestrates code integration with respect to spatial meshing, computational resources, and execution to give the user a common 'look and feel' for setting up problems and displaying results. NEAMS is building upon a suite of existing simulation tools, including those developed by the federal Scientific Discovery through Advanced Computing and Advanced Simulation and Computing programs. NEAMS also draws upon existing simulation tools for materials and nuclear systems, although many of these are limited in terms of scale, applicability, and portability (their ability to be integrated into contemporary software and hardware architectures). NEAMS investments have directly and indirectly supported additional NE research and development programs, including those devoted to waste repositories, safeguarded separations systems, and long-term storage of used nuclear fuel. NEAMS is organized into two broad efforts, each comprising four elements. The quarterly highlights October-December 2011 are: (1) Version 1.0 of AMP, the fuel assembly performance code, was tested on the JAGUAR supercomputer and released on November 1, 2011, a detailed discussion of this new simulation tool is given; (2) A coolant sub-channel model and a preliminary UO{sub 2} smeared-cracking model were implemented in BISON, the single-pin fuel code, more information on how these models were developed and benchmarked is given; (3) The Object Kinetic Monte Carlo model was implemented to account for nucleation events in meso-scale simulations and a discussion of the significance of this advance is given; (4) The SHARP neutronics module, PROTEUS, was expanded to be applicable to all types of reactors, and a discussion of the importance of PROTEUS is given; (5) A plan has been finalized for integrating the high-fidelity, three-dimensional reactor code SHARP with both the systems-level code RELAP7 and the fuel assembly code AMP. This is a new initiative; (6) Work began to evaluate the applicability of AMP to the problem of dry storage of used fuel and to define a relevant problem to test the applicability; (7) A code to obtain phonon spectra from the force-constant matrix for a crystalline lattice has been completed. This important bridge between subcontinuum and continuum phenomena is discussed; (8) Benchmarking was begun on the meso-scale, finite-element fuels code MARMOT to validate its new variable splitting algorithm; (9) A very computationally demanding simulation of diffusion-driven nucleation of new microstructural features has been completed. An explanation of the difficulty of this simulation is given; (10) Experiments were conducted with deformed steel to validate a crystal plasticity finite-element code for bodycentered cubic iron; (11) The Capability Transfer Roadmap was completed and published as an internal laboratory technical report; (12) The AMP fuel assembly code input generator was integrated into the NEAMS Integrated Computational Environment (NiCE). More details on the planned NEAMS computing environment is given; and (13) The NEAMS program website (neams.energy.gov) is nearly ready to launch.« less

  2. N Reactor Deactivation Program Plan. Revision 4

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Walsh, J.L.

    1993-12-01

    This N Reactor Deactivation Program Plan is structured to provide the basic methodology required to place N Reactor and supporting facilities {center_dot} in a radiologically and environmentally safe condition such that they can be decommissioned at a later date. Deactivation will be in accordance with facility transfer criteria specified in Department of Energy (DOE) and Westinghouse Hanford Company (WHC) guidance. Transition activities primarily involve shutdown and isolation of operational systems and buildings, radiological/hazardous waste cleanup, N Fuel Basin stabilization and environmental stabilization of the facilities. The N Reactor Deactivation Program covers the period FY 1992 through FY 1997. The directivemore » to cease N Reactor preservation and prepare for decommissioning was issued by DOE to WHC on September 20, 1991. The work year and budget data supporting the Work Breakdown Structure in this document are found in the Activity Data Sheets (ADS) and the Environmental Restoration Program Baseline, that are prepared annually.« less

  3. Experiences in utilization of research reactors in Yugoslavia

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Copic, M.; Gabrovsek, Z.; Pop-Jordanov, J.

    1971-06-15

    The nuclear institutes in Yugoslavia possess three research reactors. Since 1958, two heavy-water reactors have been in operation at the 'Boris Kidric' Institute, a zero-power reactor RB and a 6. 5-MW reactor RA. At the Jozef Stefan Institute, a 250-kW TRIGA Mark II reactor has been operating since 1966. All reactors are equipped with the necessary experimental facilities. The main activities based on these reactors are: (1) fundamental research in solid-state and nuclear physics; (2) R and D activities related to nuclear power program; and (3) radioisotope production. In fundamental physics, inelastic neutron scattering and diffraction phenomena are studied bymore » means of the neutron beam tubes and applied to investigations of the structures of solids and liquids. Valuable results are also obtained in n - γ reaction studies. Experiments connected with the fuel -element development program, owing to the characteristics of the existing reactors, are limited to determination of the fuel element parameters, to studies on the purity of uranium, and to a small number of capsule irradiations. All three reactors are also used for the verification of different methods applied in the analysis of power reactors, particularly concerning neutron flux distributions, the optimization of reactor core configurations and the shielding effects. An appreciable irradiation space in the reactors is reserved for isotope production. Fruitful international co-operation has been established in all these activities, on the basis of either bilateral or multilateral arrangements. The paper gives a critical analysis of the utilization of research reactors in a developing country such as Yugoslavia. The investments in and the operational costs of research reactors are compared with the benefits obtained in different areas of reactor application. The impact on the general scientific, technological and educational level in the country is also considered. In particular, an attempt is made ro envisage the role of research reactors in the promotion of nuclear power programs in relation to the size of the program, the competence of domestic industries and the degree of independence where fuel supply is concerned. (author)« less

  4. Inertial Confinement Fusion Annual Report 1997

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Correll, D

    The ICF Annual Report provides documentation of the achievements of the LLNL ICF Program during the fiscal year by the use of two formats: (1) an Overview that is a narrative summary of important results for the fiscal year and (2) a compilation of the articles that previously appeared in the ICF Quarterly Report that year. Both the Overview and Quarterly Report are also on the Web at http://lasers.llnl.gov/lasers/pubs/icfq.html. Beginning in Fiscal Year 1997, the fourth quarter issue of the ICF Quarterly was no longer printed as a separate document but rather included in the ICF Annual. This change providedmore » a more efficient process of documenting our accomplishments with-out unnecessary duplication of printing. In addition we introduced a new document, the ICF Program Monthly Highlights. Starting with the September 1997 issue and each month following, the Monthly Highlights will provide a brief description of noteworthy activities of interest to our DOE sponsors and our stakeholders. The underlying theme for LLNL's ICF Program research continues to be defined within DOE's Defense Programs missions and goals. In support of these missions and goals, the ICF Program advances research and technology development in major interrelated areas that include fusion target theory and design, target fabrication, target experiments, and laser and optical science and technology. While in pursuit of its goal of demonstrating thermonuclear fusion ignition and energy gain in the laboratory, the ICF Program provides research and development opportunities in fundamental high-energy-density physics and supports the necessary research base for the possible long-term application of inertial fusion energy for civilian power production. ICF technologies continue to have spin-off applications for additional government and industrial use. In addition to these topics, the ICF Annual Report covers non-ICF funded, but related, laser research and development and associated applications. We also provide a short summary of the quarterly activities within Nova laser operations, Beamlet laser operations, and National Ignition Facility laser design. LLNL's ICF Program falls within DOE's national ICF program, which includes the Nova and Beamlet (LLNL), OMEGA (University of Rochester Laboratory for Laser Energetics), Nike (Naval Research Laboratory), and Trident (Los Alamos National Laboratory) laser facilities. The Particle Beam Fusion Accelerator (Z) and Saturn pulsed-power facilities are at Sandia National Laboratories. General Atomics, Inc., develops and provides many of the targets for the above experimental facilities. Many of the ICF Annual Report articles are co-authored with our colleagues from these other ICF institutions.« less

  5. The U.S. Evolved Expendable Launch Vehicle (EELV) programs : Quarterly Launch Report : special report

    DOT National Transportation Integrated Search

    1997-01-01

    The Evolved Expendable Launch Vehicle (EELV) Program is a Department of Defense technology-development program managed by the Air Force. The program is intended to produce an improved launch vehicle family for government use. The EELV will replace th...

  6. A liquid-metal filling system for pumped primary loop space reactors

    NASA Astrophysics Data System (ADS)

    Crandall, D. L.; Reed, W. C.

    Some concepts for the SP-100 space nuclear power reactor use liquid metal as the primary coolant in a pumped loop. Prior to filling ground engineering test articles or reactor systems, the liquid metal must be purified and circulated through the reactor primary system to remove contaminants. If not removed, these contaminants enhance corrosion and reduce reliability. A facility was designed and built to support Department of Energy Liquid Metal Fast Breeder Reactor tests conducted at the Idaho National Engineering Laboratory. This test program used liquid sodium to cool nuclear fuel in in-pile experiments; thus, a system was needed to store and purify sodium inventories and fill the experiment assemblies. This same system, with modifications and potential changeover to lithium or sodium-potassium (NaK), can be used in the Space Nuclear Power Reactor Program. This paper addresses the requirements, description, modifications, operation, and appropriateness of using this liquid-metal system to support the SP-100 space reactor program.

  7. F Reactor Inspection

    ScienceCinema

    Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

    2018-01-16

    Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F Reactor before stepping inside the reactor to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the reactor open since 2008. The F Reactor is one of nine reactors along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned reactors periodically to evaluate the structural integrity of the safe storage enclosure and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."

  8. F Reactor Inspection

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

    2014-10-29

    Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F Reactor before stepping inside the reactor to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the reactor open since 2008. The F Reactor is one of nine reactors along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned reactors periodically to evaluate the structural integrity of the safe storage enclosuremore » and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."« less

  9. 78 FR 25787 - Community Connect Broadband Grant Program

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-03

    ... Learning and Telemedicine Grant Program) during its quarterly Tribal Consultation webinar and... accommodate distance learning, telework, e-government and telemedicine, rural America will see improving... through and beyond completion. 3. Scoring Simplification. The current program scores and ranks...

  10. 78 FR 69493 - Self-Regulatory Organizations; NYSE Arca, Inc.; Notice of Filing and Immediate Effectiveness of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-19

    ... additions are made. The total number of Quarterly Options Series that can be listed at any one time is.... To help ensure that only active options series are listed, Exchange procedures are designed to delist... Change Amending Commentary .08 to Rule 6.4 To Modify the Quarterly Option Series Program To Eliminate the...

  11. The Amarillo National Resource Center for Plutonium. Quarterly progress detailed report, 1 November 1996--31 January 1997

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    Progress for this quarter is given for each of the following Center programs: (1) plutonium information resource; (2) advisory function (DOE and state support); (3) environmental, public health and safety; (3) communication, education, and training; and (4) nuclear and other material studies. Both summaries of the activities and detailed reports are included.

  12. Q4 2016/Q1 2017 Solar Industry Update

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Margolis, Robert; Feldman, David; Boff, Daniel

    2017-05-17

    This technical presentation provides an update on the major trends that occurred in the solar industry in the fourth quarter of 2016 and the first quarter of 2017. Major topics of focus include global and U.S. supply and demand, module and system price, investment trends and business models, and updates on U.S. government programs supporting the solar industry.

  13. The Structure and Dynamics of the Solar Corona and Inner Heliosphere-First Quarter First Year Progress Report

    NASA Technical Reports Server (NTRS)

    Mikic, Zoran; Grebowsky, J. (Technical Monitor)

    2000-01-01

    This report details progress during the first quarter of the first year of our Sun-Earth Connections Theory Program (SECTP) contract. Science Applications International Corporation (SAIC) and the University of California, Irvine (UCI) have conducted research into theoretical modeling of active regions, the solar corona, and the inner heliosphere, using the MHD model.

  14. 45 CFR 265.3 - What reports must the State file on a quarterly basis?

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 45 Public Welfare 2 2013-10-01 2012-10-01 true What reports must the State file on a quarterly basis? 265.3 Section 265.3 Public Welfare Regulations Relating to Public Welfare OFFICE OF FAMILY ASSISTANCE (ASSISTANCE PROGRAMS), ADMINISTRATION FOR CHILDREN AND FAMILIES, DEPARTMENT OF HEALTH AND HUMAN SERVICES DATA COLLECTION AND REPORTING...

  15. Increase in Naloxone Prescriptions Dispensed in US Retail Pharmacies Since 2013.

    PubMed

    Jones, Christopher M; Lurie, Peter G; Compton, Wilson M

    2016-04-01

    Distribution of naloxone, traditionally through community-based naloxone programs, is a component of a comprehensive strategy to address the epidemic of prescription opioid and heroin overdose deaths in the United States. Recently, there has been increased focus on naloxone prescription in the outpatient setting, particularly through retail pharmacies, yet data on this practice are sparse. We found an 1170% increase in naloxone dispensing from US retail pharmacies between the fourth quarter of 2013 and the second quarter of 2015. These findings suggest that prescribing naloxone in the outpatient setting complements traditional community-based naloxone programs.

  16. Regulation of coal polymer degradation by fungi. Eighth quarterly report, [April--June 1996

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Irvine, R.L.; Bumpus, J.A.

    1996-07-28

    This project addresses the solubilization of low-rank coal (leonardite) by lignin degrading fungi. During this reporting period efforts were focused on determining the effect of pH on coal solubilization by oxalate ion and other biologically important compounds that might function as metal chelators, on the role of laccase in coal solubilization and metabolism, on decolorization of soluble coal macromolecule by Phanerochaete chrysosporium and T. versicolor in solid agar media, and on solubilization of coal in slurry cultures and solid phase reactors.

  17. Reactor engineering support of operations at the Davis-Besse nuclear power station

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kelley, D.B.

    1995-12-31

    Reactor engineering functions differ greatly from unit to unit; however, direct support of the reactor operators during reactor startups and operational transients is common to all units. This paper summarizes the support the reactor engineers provide the reactor operators during reactor startups and power changes through the use of automated computer programs at the Davis-Besse nuclear power station.

  18. The Savannah River Site's Groundwater Monitoring Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted during the first quarter of 1992. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official document of the analytical results.

  19. 78 FR 11189 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-October Through December 2012

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-15

    ... beneficiaries, health care providers, and the public; and (2) maintaining effective communications with CMS... Cantwell, Director, Office of Strategic Operations and Regulatory Affairs. [[Page 11191

  20. The AMTEX Partnership{trademark}. Fourth quarter FY95 report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1995-09-01

    The AMTEX Partnership{trademark} is a collaborative research and development program among the US Integrated Textile Industry, the Department of Energy (DOE), the national laboratories, other federal agencies and laboratories, and universities. The goal of AMTEX is to strengthen the competitiveness of this vital industry, thereby preserving and creating US jobs. The operations and program management of the AMTEX Partnership{trademark} is provided by the Program Office. This report is produced by the Program Office on a quarterly basis and provides information on the progress, operations, and project management of the partnership. Progress is reported on the following projects: computer-aided fabric evaluation;more » cotton biotechnology; demand activated manufacturing architecture; electronic embedded fingerprints; on-line process control for flexible fiber manufacturing; rapid cutting; sensors for agile manufacturing; and textile resource conservation.« less

  1. Academic Leadership Development: A Case Study.

    PubMed

    Berman, Audrey

    2015-01-01

    A dean at a private school of nursing implemented a leadership development program for early- to mid-career nursing faculty consisting of one 4-hour evening session per academic quarter for 7 quarters. Eight faculty members who had expressed interest in assuming a leadership role or been recommended by their supervisors as having strong leadership potential were invited to join. Program topics included leadership pathways, legal issues, budgeting and governance, diversity, the political arena, human resources, and student issues. Interviews with participants revealed 6 themes: the support a peer cohort provided, a desire for real-life application, a lack of previous exposure to related content or experiences, new perceptions of themselves as academic nurse leaders, the value of the program as preparation for academic nursing leadership roles, and broad program applicability. Copyright © 2015 Elsevier Inc. All rights reserved.

  2. Automatic reactor model synthesis with genetic programming.

    PubMed

    Dürrenmatt, David J; Gujer, Willi

    2012-01-01

    Successful modeling of wastewater treatment plant (WWTP) processes requires an accurate description of the plant hydraulics. Common methods such as tracer experiments are difficult and costly and thus have limited applicability in practice; engineers are often forced to rely on their experience only. An implementation of grammar-based genetic programming with an encoding to represent hydraulic reactor models as program trees should fill this gap: The encoding enables the algorithm to construct arbitrary reactor models compatible with common software used for WWTP modeling by linking building blocks, such as continuous stirred-tank reactors. Discharge measurements and influent and effluent concentrations are the only required inputs. As shown in a synthetic example, the technique can be used to identify a set of reactor models that perform equally well. Instead of being guided by experience, the most suitable model can now be chosen by the engineer from the set. In a second example, temperature measurements at the influent and effluent of a primary clarifier are used to generate a reactor model. A virtual tracer experiment performed on the reactor model has good agreement with a tracer experiment performed on-site.

  3. Utility Tax Relief Program in the Netherlands

    DTIC Science & Technology

    2010-01-06

    Management Command, Europe Region LQA Living Quarters Allowance VAT Value Added Tax INSPECTOR GENERAL DEPARTMENT OF DEFENSE 400 ARMY NAVY DRIVE...savings on their utility bills. However, for DOD civilians receiving Living Quarters Allowance ( LQA ),2 DOD realizes the cost savings through reduced... LQA payments, unless the civilian’s housing expenses exceed the maximum allowable LQA . 1 For the purpose of this report, DOD personnel refers to

  4. Global Positioning System: Observations on Quarterly Reports from the Air Force

    DTIC Science & Technology

    2016-10-17

    Positioning System : Observations on Quarterly Reports from the Air Force The satellite-based Global Positioning System (GPS) provides positioning, navigation...infrastructure, and transportation safety. The Department of Defense (DOD)—specifically, the Air Force—develops and operates the GPS system , which...programs, including the most recent detailed assessment of the next generation operational control system (OCX) and development of military GPS

  5. The AMTEX Partnership{sup trademark}. Second quarter report. Fiscal year 1996

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Lemon, D.K.; Quisenberry, R.K.

    1996-03-01

    This quarterly report details activities of the AMTEX Partnership {sup TM} which is a collaborative research and development program among the U.S. Integrated Textile Industry, the Department of Energy (DOE), the national laboratories, other federal agencies and laboratories, and universities. The goal of AMTEX is to strengthen the competitiveness of this vital industry, thereby preserving and creating U.S. jobs.

  6. Integrated Marketing Communications: A New Master's Degree Concept.

    ERIC Educational Resources Information Center

    Caywood, Clarke; Ewing, Raymond

    1991-01-01

    Describes how separate graduate degree programs have been fused into an integrated marketing communications program at Northwestern University. Discusses the five-quarter program that includes a core of new marketing communications planning and management classes, professional specialization classes in corporate public relations, advertising, and…

  7. 42 CFR 456.652 - Requirements for an effective utilization control program.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... To Make a Satisfactory Showing of an Effective Institutional Utilization Control Program § 456.652... reduction in FFP, the Medicaid agency must make a satisfactory showing to the Administrator, in each quarter...

  8. Production assurance program strategy for N Reactor balance of plant systems

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    House, R.D.; Bitten, E.J.; Keenan, J.P.

    1986-03-18

    A production assurance program has been established for N Reactor, a dual purpose reactor plant, operated to produce special nuclear materials and steam for electricity. N Reactor, which began operation in December 1963, is now approaching the end of its design life. This paper describes the two phase program for Balance of Plant (BOP) systems. The Phase I evaluation has been completed and indications are that the lifetime of systems and components could be extended by implementing appropriate surveillance, operations and maintenance strategies. In Phase II, a thorough evaluation of components and systems is underway and action items are beingmore » identified which will allow component and system extended operation.« less

  9. Proceedings of the 1994 international meeting on reduced enrichment for research and test reactors

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1997-08-01

    This meeting brought together participants in the international effort to minimize and eventually eliminate the use of highly enriched uranium in civilian nuclear programs. Papers cover the following topics: National programs; fuel cycle; nuclear fuels; analyses; advanced reactors; and reactor conversions. Selected papers have been indexed separately for inclusion to the Energy Science and Technology Database.

  10. Advance High Temperature Inspection Capabilities for Small Modular Reactors: Part 1 - Ultrasonics

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bond, Leonard J.; Bowler, John R.

    The project objective was to investigate the development non-destructive evaluation techniques for advanced small modular reactors (aSMR), where the research sought to provide key enabling inspection technologies needed to support the design and maintenance of reactor component performance. The project tasks for the development of inspection techniques to be applied to small modular reactor are being addressed through two related activities. The first is focused on high temperature ultrasonic transducers development (this report Part 1) and the second is focused on an advanced eddy current inspection capability (Part 2). For both inspection techniques the primary aim is to develop in-servicemore » inspection techniques that can be carried out under standby condition in a fast reactor at a temperature of approximately 250°C in the presence of liquid sodium. The piezoelectric material and the bonding between layers have been recognized as key factors fundamental for development of robust ultrasonic transducers. Dielectric constant characterization of bismuth scantanate-lead titanate ((1-x)BiScO 3-xPbTiO 3) (BS-PT) has shown a high Curie temperature in excess of 450°C , suitable for hot stand-by inspection in liquid metal reactors. High temperature pulse-echo contact measurements have been performed with BS-PT bonded to 12.5 mm thick 1018-low carbon steel plate from 20C up to 260 C. High temperature air-backed immersion transducers have been developed with BS-PT, high temperature epoxy and quarter wavlength nickel plate, needed for wetting ability in liquid sodium. Ultrasonic immersion measurements have been performed in water up to 92C and in silicone oil up to 140C. Physics based models have been validated with room temperature experimental data with benchmark artifical defects.« less

  11. Quail Egg compared to a quarter

    NASA Technical Reports Server (NTRS)

    2003-01-01

    Quail eggs are small (shown here with a quarter for scale) and develop quickly, making them ideal for space experiments. The Avian Development Facility (ADF) supports 36 eggs in two carousels (below), one of which rotates to provide a 1-g control for comparing to eggs grown in microgravity. The ADF originated in NASA's Shuttle Student Involvement program in the 1980s and was developed under the NASA Small Business Irnovation Research program. In late 2001, the ADF made its first flight and carried eggs used in two investigations, Development and function of the inner-ear balance system in normal and altered gravity environments, and Skeletal development in embryonic quail.

  12. Excore Modeling with VERAShift

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pandya, Tara M.; Evans, Thomas M.

    It is important to be able to accurately predict the neutron flux outside the immediate reactor core for a variety of safety and material analyses. Monte Carlo radiation transport calculations are required to produce the high fidelity excore responses. Under this milestone VERA (specifically the VERAShift package) has been extended to perform excore calculations by running radiation transport calculations with Shift. This package couples VERA-CS with Shift to perform excore tallies for multiple state points concurrently, with each component capable of parallel execution on independent domains. Specifically, this package performs fluence calculations in the core barrel and vessel, or, performsmore » the requested tallies in any user-defined excore regions. VERAShift takes advantage of the general geometry package in Shift. This gives VERAShift the flexibility to explicitly model features outside the core barrel, including detailed vessel models, detectors, and power plant details. A very limited set of experimental and numerical benchmarks is available for excore simulation comparison. The Consortium for the Advanced Simulation of Light Water Reactors (CASL) has developed a set of excore benchmark problems to include as part of the VERA-CS verification and validation (V&V) problems. The excore capability in VERAShift has been tested on small representative assembly problems, multiassembly problems, and quarter-core problems. VERAView has also been extended to visualize these vessel fluence results from VERAShift. Preliminary vessel fluence results for quarter-core multistate calculations look very promising. Further development is needed to determine the details relevant to excore simulations. Validation of VERA for fluence and excore detectors still needs to be performed against experimental and numerical results.« less

  13. HTR-PROTEUS pebble bed experimental program cores 9 & 10: columnar hexagonal point-on-point packing with a 1:1 moderator-to-fuel pebble ratio

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bess, John D.

    2014-03-01

    PROTEUS is a zero-power research reactor based on a cylindrical graphite annulus with a central cylindrical cavity. The graphite annulus remains basically the same for all experimental programs, but the contents of the central cavity are changed according to the type of reactor being investigated. Through most of its service history, PROTEUS has represented light-water reactors, but from 1992 to 1996 PROTEUS was configured as a pebble-bed reactor (PBR) critical facility and designated as HTR-PROTEUS. The nomenclature was used to indicate that this series consisted of High Temperature Reactor experiments performed in the PROTEUS assembly. During this period, seventeen criticalmore » configurations were assembled and various reactor physics experiments were conducted. These experiments included measurements of criticality, differential and integral control rod and safety rod worths, kinetics, reaction rates, water ingress effects, and small sample reactivity effects (Ref. 3). HTR-PROTEUS was constructed, and the experimental program was conducted, for the purpose of providing experimental benchmark data for assessment of reactor physics computer codes. Considerable effort was devoted to benchmark calculations as a part of the HTR-PROTEUS program. References 1 and 2 provide detailed data for use in constructing models for codes to be assessed. Reference 3 is a comprehensive summary of the HTR-PROTEUS experiments and the associated benchmark program. This document draws freely from these references. Only Cores 9 and 10 are evaluated in this benchmark report due to similarities in their construction. The other core configurations of the HTR-PROTEUS program are evaluated in their respective reports as outlined in Section 1.0. Cores 9 and 10 were evaluated and determined to be acceptable benchmark experiments.« less

  14. HTR-PROTEUS PEBBLE BED EXPERIMENTAL PROGRAM CORES 5, 6, 7, & 8: COLUMNAR HEXAGONAL POINT-ON-POINT PACKING WITH A 1:2 MODERATOR-TO-FUEL PEBBLE RATIO

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    John D. Bess

    2013-03-01

    PROTEUS is a zero-power research reactor based on a cylindrical graphite annulus with a central cylindrical cavity. The graphite annulus remains basically the same for all experimental programs, but the contents of the central cavity are changed according to the type of reactor being investigated. Through most of its service history, PROTEUS has represented light-water reactors, but from 1992 to 1996 PROTEUS was configured as a pebble-bed reactor (PBR) critical facility and designated as HTR-PROTEUS. The nomenclature was used to indicate that this series consisted of High Temperature Reactor experiments performed in the PROTEUS assembly. During this period, seventeen criticalmore » configurations were assembled and various reactor physics experiments were conducted. These experiments included measurements of criticality, differential and integral control rod and safety rod worths, kinetics, reaction rates, water ingress effects, and small sample reactivity effects (Ref. 3). HTR-PROTEUS was constructed, and the experimental program was conducted, for the purpose of providing experimental benchmark data for assessment of reactor physics computer codes. Considerable effort was devoted to benchmark calculations as a part of the HTR-PROTEUS program. References 1 and 2 provide detailed data for use in constructing models for codes to be assessed. Reference 3 is a comprehensive summary of the HTR-PROTEUS experiments and the associated benchmark program. This document draws freely from these references. Only Cores 9 and 10 are evaluated in this benchmark report due to similarities in their construction. The other core configurations of the HTR-PROTEUS program are evaluated in their respective reports as outlined in Section 1.0. Cores 9 and 10 were evaluated and determined to be acceptable benchmark experiments.« less

  15. HTR-PROTEUS PEBBLE BED EXPERIMENTAL PROGRAM CORES 9 & 10: COLUMNAR HEXAGONAL POINT-ON-POINT PACKING WITH A 1:1 MODERATOR-TO-FUEL PEBBLE RATIO

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    John D. Bess

    2013-03-01

    PROTEUS is a zero-power research reactor based on a cylindrical graphite annulus with a central cylindrical cavity. The graphite annulus remains basically the same for all experimental programs, but the contents of the central cavity are changed according to the type of reactor being investigated. Through most of its service history, PROTEUS has represented light-water reactors, but from 1992 to 1996 PROTEUS was configured as a pebble-bed reactor (PBR) critical facility and designated as HTR-PROTEUS. The nomenclature was used to indicate that this series consisted of High Temperature Reactor experiments performed in the PROTEUS assembly. During this period, seventeen criticalmore » configurations were assembled and various reactor physics experiments were conducted. These experiments included measurements of criticality, differential and integral control rod and safety rod worths, kinetics, reaction rates, water ingress effects, and small sample reactivity effects (Ref. 3). HTR-PROTEUS was constructed, and the experimental program was conducted, for the purpose of providing experimental benchmark data for assessment of reactor physics computer codes. Considerable effort was devoted to benchmark calculations as a part of the HTR-PROTEUS program. References 1 and 2 provide detailed data for use in constructing models for codes to be assessed. Reference 3 is a comprehensive summary of the HTR-PROTEUS experiments and the associated benchmark program. This document draws freely from these references. Only Cores 9 and 10 are evaluated in this benchmark report due to similarities in their construction. The other core configurations of the HTR-PROTEUS program are evaluated in their respective reports as outlined in Section 1.0. Cores 9 and 10 were evaluated and determined to be acceptable benchmark experiments.« less

  16. The Savannah River Site`s groundwater monitoring program. Third quarter 1990

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1991-05-06

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During third quarter 1990 (July through September) EPD/EMS conducted routine sampling of monitoring wells and drinking water locations. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. All analytical results from third quarter 1990 are listed in thismore » report, which is distributed to all site custodians. One or more analytes exceeded Flag 2 in 87 monitoring well series. Analytes exceeded Flat 2 for the first since 1984 in 14 monitoring well series. In addition to groundwater monitoring, EPD/EMS collected drinking water samples from SRS drinking water systems supplied by wells. The drinking water samples were analyzed for radioactive constituents.« less

  17. New method of metallization for silicon solar cells. First quarterly report, December 15, 1978-March 31, 1979

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Macha, M.

    1979-01-01

    The objective of this program is to develop a low-cost ohmic contact on silicon solar cells based on molybdenum tin metal system. The approach is based on the formulation of a screenable ink composed from molybdenum oxide and tin mixture. The first quarter of this program involved the study of the reduction of MoO/sub 3/ into Mo and the establishing of MoO/sub 3/:Sn ratio. Both tasks have been done in an experimental station constructed for this purpose. The results showed that molybdenum was formed from its oxide at 800/sup 0/C and improved in bonding to silicon at 900/sup 0/C. Amore » 20% MoO/sub 3/-80% Sn mixture was converted into a metallic coating within this temperature range. The next quarter will be concerned with the formulation of screenable ink, calibration of a tube furnace for the firing cycle and evaluation of the metal contact on solar cell structures.« less

  18. 75 FR 56057 - Proposed Information Collection; Comment Request; Broadband Technology Opportunities Program Post...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-15

    ... Information Collection; Comment Request; Broadband Technology Opportunities Program Post-Award Quarterly and... (Recovery Act) establishes and provides $4.7 billion for the Broadband Technology Opportunities Program... million will be made available for competitive grants to expand public computer center capacity; at least...

  19. Making IT Work

    DTIC Science & Technology

    2015-10-01

    system (MAIS) program failed to “achieve a Full Deployment Decision ( FDD ) within five years after funds were first obligated for the program.”14 A...Quarterly Report dated 31 October 2010, highlighted that the MDA had not approved a FDD for ECSS by 31 August 2010, and determined that the program

  20. NRC TLD Direct Radiation Monitoring Network. Volume 15, No. 4: Quarterly progress report, October--December 1995

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Struckmeyer, R.

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1995. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program.

  1. Utility Tax Avoidance Program in Germany

    DTIC Science & Technology

    2010-09-29

    Defense Education Activity IMCOM-E Installation Management Command - Europe Region LQA Living Quarters Allowance TRO Tax Relief Office USD(P&R) Under...receive Living Quarters Allowance ( LQA ), which is designed to cover the actual cost for rent, utilities, and other expenses required by law or custom up...to the maximum allowable LQA amount. Benefits of Participation in the UTAP Participation in UTAP allows DOD personnel to avoid paying VAT on their

  2. Joint Force Quarterly, Issue 49, 2nd Quarter 2008: Focus on Airpower

    DTIC Science & Technology

    2008-04-01

    that the next space age will produce wealth (from tourism , energy, mining, and manufacturing) is correct, “the next space age will be marked by a...wealth frontiers include tourism , energy, mining, and manu- facturing. Beyond the impact that space has in supporting earthly economic enterprises, the... tourism , military exchanges, student scholarships, partner city programs, and unrestricted mutual media access and transparency. In sum, we will

  3. Our First Quarter Century of Achievement... Just the Beginning

    NASA Technical Reports Server (NTRS)

    1983-01-01

    Space flight, space science, space applications, aeronautics, tracking and data acquisition, international programs, technology utilization, NASA installations, the NASA launch record, astronauts, and the fine arts program are reviewed in light of NASA's 25th anniversary.

  4. 77 FR 49799 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-April Through June 2012

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-17

    ...-Approved Lung JoAnna Baldwin, MS.. (410) 786-7205 Volume Reduction Surgery Facilities. XIV Medicare-Approved Kate Tillman, RN, (410) 786-9252 Bariatric Surgery MAS. Facilities. XV Fluorodeoxyglucose Stuart...

  5. 77 FR 29648 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-January Through March 2012

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-18

    ... (Destination Therapy) Facilities. XIII Medicare-Approved Lung Volume Reduction Surgery JoAnna Baldwin, MS (410) 786-7205 Facilities. XIV Medicare-Approved Bariatric Surgery Facilities........ Kate Tillman, RN, MAS...

  6. 76 FR 68467 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-April Through June 2011

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-04

    ...-Approved Lung JoAnna Baldwin, (410) 786-7205 Volume Reduction Surgery MS. Facilities. XIV Medicare-Approved Kate Tillman, RN, (410) 786-9252 Bariatric Surgery Facilities. MAS. XV Fluorodeoxyglucose Positron...

  7. MONTE CARLO SIMULATIONS OF PERIODIC PULSED REACTOR WITH MOVING GEOMETRY PARTS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cao, Yan; Gohar, Yousry

    2015-11-01

    In a periodic pulsed reactor, the reactor state varies periodically from slightly subcritical to slightly prompt supercritical for producing periodic power pulses. Such periodic state change is accomplished by a periodic movement of specific reactor parts, such as control rods or reflector sections. The analysis of such reactor is difficult to perform with the current reactor physics computer programs. Based on past experience, the utilization of the point kinetics approximations gives considerable errors in predicting the magnitude and the shape of the power pulse if the reactor has significantly different neutron life times in different zones. To accurately simulate themore » dynamics of this type of reactor, a Monte Carlo procedure using the transfer function TRCL/TR of the MCNP/MCNPX computer programs is utilized to model the movable reactor parts. In this paper, two algorithms simulating the geometry part movements during a neutron history tracking have been developed. Several test cases have been developed to evaluate these procedures. The numerical test cases have shown that the developed algorithms can be utilized to simulate the reactor dynamics with movable geometry parts.« less

  8. Environmental Hazards Assessment Program. Quarterly report, July--September 1995

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    This report describes activities and reports on progress for the first quarter (July--September) of the fourth year of the grant to support the Environmental Hazards Assessment Program (EHAP) at the Medical University of South Carolina. It reports progress against the grant objectives and the Program Implementation Plan published at the end of the first year of the grant. The objectives of EHAP stated in the proposal to DOE are to: (1) develop a holistic, national basis for risk assessment, risk management, and risk communication that recognizes the direct impact of environmental hazards on the health and well-being of all; (2)more » develop a pool of talented scientists and experts in cleanup activities, especially in human health aspects; and (3) identify needs and develop programs addressing the critical shortage of well-educated, highly-skilled technical and scientific personnel to address the health-oriented aspects of environmental restoration and waste management.« less

  9. Observed Changes in As-Fabricated U-10Mo Monolithic Fuel Microstructures After Irradiation in the Advanced Test Reactor

    NASA Astrophysics Data System (ADS)

    Keiser, Dennis; Jue, Jan-Fong; Miller, Brandon; Gan, Jian; Robinson, Adam; Madden, James

    2017-12-01

    A low-enriched uranium U-10Mo monolithic nuclear fuel is being developed by the Material Management and Minimization Program, earlier known as the Reduced Enrichment for Research and Test Reactors Program, for utilization in research and test reactors around the world that currently use high-enriched uranium fuels. As part of this program, reactor experiments are being performed in the Advanced Test Reactor. It must be demonstrated that this fuel type exhibits mechanical integrity, geometric stability, and predictable behavior to high powers and high fission densities in order for it to be a viable fuel for qualification. This paper provides an overview of the microstructures observed at different regions of interest in fuel plates before and after irradiation for fuel samples that have been tested. These fuel plates were fabricated using laboratory-scale fabrication methods. Observations regarding how microstructural changes during irradiation may impact fuel performance are discussed.

  10. Progress in space nuclear reactor power systems technology development - The SP-100 program

    NASA Technical Reports Server (NTRS)

    Davis, H. S.

    1984-01-01

    Activities related to the development of high-temperature compact nuclear reactors for space applications had reached a comparatively high level in the U.S. during the mid-1950s and 1960s, although only one U.S. nuclear reactor-powered spacecraft was actually launched. After 1973, very little effort was devoted to space nuclear reactor and propulsion systems. In February 1983, significant activities toward the development of the technology for space nuclear reactor power systems were resumed with the SP-100 Program. Specific SP-100 Program objectives are partly related to the determination of the potential performance limits for space nuclear power systems in 100-kWe and 1- to 100-MW electrical classes. Attention is given to potential missions and applications, regimes of possible space power applicability, safety considerations, conceptual system designs, the establishment of technical feasibility, nuclear technology, materials technology, and prospects for the future.

  11. NEAMS update quarterly report for January - March 2012.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bradley, K.S.; Hayes, S.; Pointer, D.

    Quarterly highlights are: (1) The integration of Denovo and AMP was demonstrated in an AMP simulation of the thermo-mechanics of a complete fuel assembly; (2) Bison was enhanced with a mechanistic fuel cracking model; (3) Mechanistic algorithms were incorporated into various lower-length-scale models to represent fission gases and dislocations in UO2 fuels; (4) Marmot was improved to allow faster testing of mesoscale models using larger problem domains; (5) Component models of reactor piping were developed for use in Relap-7; (6) The mesh generator of Proteus was updated to accept a mesh specification from Moose and equations were formulated for themore » intermediate-fidelity Proteus-2D1D module; (7) A new pressure solver was implemented in Nek5000 and demonstrated to work 2.5 times faster than the previous solver; (8) Work continued on volume-holdup models for two fuel reprocessing operations: voloxidation and dissolution; (9) Progress was made on a pyroprocessing model and the characterization of pyroprocessing emission signatures; (10) A new 1D groundwater waste transport code was delivered to the used fuel disposition (UFD) campaign; (11) Efforts on waste form modeling included empirical simulation of sodium-borosilicate glass compositions; (12) The Waste team developed three prototypes for modeling hydride reorientation in fuel cladding during very long-term fuel storage; (13) A benchmark demonstration problem (fission gas bubble growth) was modeled to evaluate the capabilities of different meso-scale numerical methods; (14) Work continued on a hierarchical up-scaling framework to model structural materials by directly coupling dislocation dynamics and crystal plasticity; (15) New 'importance sampling' methods were developed and demonstrated to reduce the computational cost of rare-event inference; (16) The survey and evaluation of existing data and knowledge bases was updated for NE-KAMS; (17) The NEAMS Early User Program was launched; (18) The Nuclear Regulatory Commission (NRC) Office of Regulatory Research was introduced to the NEAMS program; (19) The NEAMS overall software quality assurance plan (SQAP) was revised to version 1.5; and (20) Work continued on NiCE and its plug-ins and other utilities, such as Cubit and VisIt.« less

  12. The United Arab Emirates Nuclear Program and Proposed U.S. Nuclear Cooperation

    DTIC Science & Technology

    2009-10-28

    global efforts to prevent nuclear proliferation” and, “the establishment of reliable sources of nuclear fuel for future civilian light water reactors ...nuclear reactor or on handling spent reactor fuel. (...continued) May 4, 2008; and, Chris...related to the UAE’s proposed nuclear program has already taken place. In August 2008, Virginia’s Thorium Power Ltd. signed two consulting and

  13. The United Arab Emirates Nuclear Program and Proposed U.S. Nuclear Cooperation

    DTIC Science & Technology

    2009-07-17

    global efforts to prevent nuclear proliferation” and, “the establishment of reliable sources of nuclear fuel for future civilian light water reactors ...planned nuclear reactor or on handling spent reactor fuel. (...continued) May 4, 2008...contracting between U.S. firms and the UAE related to the UAE’s proposed nuclear program has already taken place. In August 2008, Virginia’s Thorium Power

  14. The United Arab Emirates Nuclear Program and Proposed U.S. Nuclear Cooperation

    DTIC Science & Technology

    2009-12-23

    reactors deployed” in the UAE. Some Members of Congress had welcomed the UAE government’s stated commitments not to pursue proliferation-sensitive...for the planned nuclear reactor or on handling spent reactor fuel. (...continued) May...firms and the UAE related to the UAE’s proposed nuclear program has already taken place. In August 2008, Virginia’s Thorium Power Ltd. signed two

  15. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bess, John D.; Sterbentz, James W.; Snoj, Luka

    PROTEUS is a zero-power research reactor based on a cylindrical graphite annulus with a central cylindrical cavity. The graphite annulus remains basically the same for all experimental programs, but the contents of the central cavity are changed according to the type of reactor being investigated. Through most of its service history, PROTEUS has represented light-water reactors, but from 1992 to 1996 PROTEUS was configured as a pebble-bed reactor (PBR) critical facility and designated as HTR-PROTEUS. The nomenclature was used to indicate that this series consisted of High Temperature Reactor experiments performed in the PROTEUS assembly. During this period, seventeen criticalmore » configurations were assembled and various reactor physics experiments were conducted. These experiments included measurements of criticality, differential and integral control rod and safety rod worths, kinetics, reaction rates, water ingress effects, and small sample reactivity effects (Ref. 3). HTR-PROTEUS was constructed, and the experimental program was conducted, for the purpose of providing experimental benchmark data for assessment of reactor physics computer codes. Considerable effort was devoted to benchmark calculations as a part of the HTR-PROTEUS program. References 1 and 2 provide detailed data for use in constructing models for codes to be assessed. Reference 3 is a comprehensive summary of the HTR-PROTEUS experiments and the associated benchmark program. This document draws freely from these references. Only Cores 9 and 10 are evaluated in this benchmark report due to similarities in their construction. The other core configurations of the HTR-PROTEUS program are evaluated in their respective reports as outlined in Section 1.0. Cores 9 and 10 were evaluated and determined to be acceptable benchmark experiments.« less

  16. Testimony of Fred R. Mynatt before the Energy Research and Development Subcommittee of the Committee on Science, Space, and Technology, US House of Representatives. [Advanced fuel technology, gas-cooled reactor technology, and liquid metal-cooled reactor technology programs

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mynatt, F.R.

    1987-03-18

    This report provides a description of the statements submitted for the record to the committee on Science, Space, and Technology of the United States House of Representatives. These statements describe three principal areas of activity of the Advanced Reactor Technology Program of the Department of Energy (DOE). These areas are advanced fuel cycle technology, modular high-temperature gas-cooled reactor technology, and liquid metal-cooled reactor. The areas of automated reactor control systems, robotics, materials and structural design shielding and international cooperation were included in these statements describing the Oak Ridge National Laboratory's efforts in these areas. (FI)

  17. 75 FR 36785 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-January Through March 2010

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-06-28

    ... national coverage determinations (NCDs) affecting specific medical and health care services under Medicare... notification, such as a particular clinical trial or research study that qualifies for Medicare coverage.... 93.773, Medicare--Hospital Insurance, Program No. 93.774, Medicare-- Supplementary Medical Insurance...

  18. 78 FR 53790 - Sunshine Act Meeting; Finance, Budget and Program Committee Meeting of the Board of Directors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-30

    ... NEIGHBORHOOD REINVESTMENT CORPORATION Sunshine Act Meeting; Finance, Budget and Program Committee... PERSON FOR MORE INFORMATION: Erica Hall, Assistant Corporate Secretary (202) 220-2376; [email protected] Education & Counseling VII. Quarterly Program Reports VIII. Financial Report IX. FY13 Corporate Scorecard...

  19. 78 FR 65716 - Sunshine Act Meeting; Finance, Budget & Program Committee Meeting of the Board of Directors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-01

    ... NEIGHBORHOOD REINVESTMENT CORPORATION Sunshine Act Meeting; Finance, Budget & Program Committee Meeting of the Board of Directors TIME & DATE: 2:00 p.m., Thursday, November 7, 2013. PLACE: Telephonic.... Quarterly Program Reports C. Corporate Scorecard Report D. HUD Counseling Rule E. Grants Report VIII...

  20. Improvements in Cystic Fibrosis Quarterly Visits, Lung Function Tests, and Respiratory Cultures.

    PubMed

    Wooldridge, Jamie L; Mason, Susan; Brusatti, Judith; Albers, Gary M; Noyes, Blakeslee E

    2015-12-01

    The Cystic Fibrosis (CF) Foundation recommends patients attend clinic ≥4 times per year with 4 respiratory cultures and 2 pulmonary function tests (PFTs). However, nationally only 57.4% of patients met these guidelines in 2012. We used a quality improvement program with a goal of 75% of our patients meeting this care guideline by 2012. A 2-stage program was started in 2011. Stage 1: education of patients/caregivers on importance of quarterly visits. Stage 2: quarterly tracking system of patient appointments. Data on clinic visits, respiratory cultures, and PFTs were collected from the CF registry from January 2009 through December 2013. Statistical process control charts were used to track improvements. The average number of clinic visits increased significantly from 4.6 ± 2.3 in 2009 to 6.3 ± 4.6 in 2013 (P < .0001). The percentage of patients ages 6 through 18 completing a clinic visit, PFT, and respiratory culture per quarter increased significantly from 76.2% during 2009 to 86.4% in 2013. The percentage of patients completing ≥4 clinic visits with 4 respiratory cultures and 2 PFTs improved significantly from 47.5% in 2009 to 71.0% in 2013 (P < .0001). A tracking system of patient appointments significantly improved adherence to the care guidelines better than education alone. The multiple-stage quality improvement program we implemented may be modifiable and able to be integrated in other CF centers or other multiple disciplinary chronic illness care centers. Copyright © 2015 by the American Academy of Pediatrics.

  1. DOE Office of Scientific and Technical Information (OSTI.GOV)

    none

    This report is the first quarterly report under Contract AT(30-1)-2528 for the decontamination and recovery of precious metals from contaminated scrap. This program encompasses the recovery of gold, platinum, iridium, rhodium and palladium from scrap and contaminated laboratory ware, equipment, etc. which may be contaminated by alpha emitters (i.e., uranium, plutonium and possibly polonium or combinations of these), beta-gamma emitters such as fission products or all three sources of radiation. In addition the scrap can be chemically contaminated by base metals, graphite or other contaminants. Osmium, ruthenium or silver are not to be recovered. Since the scrap can exist inmore » such a great variety of forms such as platinum-rhodium laboratory crucibles, graphite crucibles containing platinum-base metal alloys derived from vacuum fusion baths, insulated thermocouple wires, reactor liners, porous platinum filters, alloys such as Baker alloy 413 (60 Au, 25 Pd, 15 Pt) it may be necessary to devise specific methods for a given type of scrap. Nevertheless the basic chemistry is the same and information and methods applicable to single systems will apply directly to the more complicated ones. Accordingly the relatively simple systems would be investigated first and the more complicated ones later in the program. An essential and major contribution to the success of the program is to devise or adapt accurate and precise analytical chemical techniques for scrap identification, process control, purity of the final products and accountability control. Accordingly, the emphasis on chemical analysis will be proportionally greater during the early stages of the program. The residual activity level to be attained is presently stated at twice the standard deviation obtained in low background counters (alpha {approx}0.1 c/m, beta {approx} 5 c/m) of virgin platinum.« less

  2. 77 FR 9931 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-October Through December 2011

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-21

    ... Ashby (410) 786-6322 Coverage Provisions. XI National Oncologic Positron Emission Stuart Caplan, RN, MAS... Tillman, RN, MAS (410) 786-9252 Facilities. XV Fluorodeoxyglucose Positron Emission Stuart Caplan, RN, MAS...

  3. Payload test philosophy. [to provide confidence in Shuttle structural math models

    NASA Technical Reports Server (NTRS)

    Mayhew, D.

    1979-01-01

    Shuttle payload test philosophy is discussed with reference to testing to provide confidence in Shuttle structural math models. Particular attention is given the Shuttle quarter-scale program and the Mated Vertical Ground Vibration Test Program.

  4. 77 FR 67368 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-July through September 2012

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-09

    ...) Facilities. XIII Medicare-Approved Lung JoAnna Baldwin, MS. (410) 786-7205 Volume Reduction Surgery Facilities. XIV Medicare-Approved Bariatric Kate Tillman, RN, (410) 786-9252 Surgery Facilities. MAS. XV...

  5. Prototype solar heating and hot water systems

    NASA Technical Reports Server (NTRS)

    1978-01-01

    Progress made in the development of a solar hot water and space heating system is described in four quarterly reports. The program schedules, technical status and other program activities from 6 October 1976 through 30 September 1977 are provided.

  6. Modifications to the NRAD Reactor, 1977 to present

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Weeks, A.A.; Pruett, D.P.; Heidel, C.C.

    1986-01-01

    Argonne National Laboratory-West, operated by the University of Chicago, is located near Idaho Falls, ID, on the Idaho National Engineering laboratory Site. ANL-West performs work in support of the Liquid Metal Fast Breeder Reactor Program (LMFBR) sponsored by the United States Department of Energy. The NRAD reactor is located at the Argonne Site within the Hot Fuel Examination Facility/North, a large hot cell facility where both non-destructive and destructive examinations are performed on highly irradiated reactor fuels and materials in support of the LMFBR program. The NRAD facility utilizes a 250-kW TRIGA reactor and is completely dedicated to neutron radiographymore » and the development of radiography techniques. Criticality was first achieved at the NRAD reactor in October of 1977. Since that time, a number of modifications have been implemented to improve operational efficiency and radiography production. This paper describes the modifications and changes that significantly improved operational efficiency and reliability of the reactor and the essential auxiliary reactor systems.« less

  7. Georgia Institute of Technology research on the Gas Core Actinide Transmutation Reactor (GCATR)

    NASA Technical Reports Server (NTRS)

    Clement, J. D.; Rust, J. H.; Schneider, A.; Hohl, F.

    1976-01-01

    The program reviewed is a study of the feasibility, design, and optimization of the GCATR. The program is designed to take advantage of initial results and to continue work carried out on the Gas Core Breeder Reactor. The program complements NASA's program of developing UF6 fueled cavity reactors for power, nuclear pumped lasers, and other advanced technology applications. The program comprises: (1) General Studies--Parametric survey calculations performed to examine the effects of reactor spectrum and flux level on the actinide transmutation for GCATR conditions. The sensitivity of the results to neutron cross sections are to be assessed. Specifically, the parametric calculations of the actinide transmutation are to include the mass, isotope composition, fission and capture rates, reactivity effects, and neutron activity of recycled actinides. (2) GCATR Design Studies--This task is a major thrust of the proposed research program. Several subtasks are considered: optimization criteria studies of the blanket and fuel reprocessing, the actinide insertion and recirculation system, and the system integration. A brief review of the background of the GCATR and ongoing research is presented.

  8. The Savannah River Site's groundwater monitoring program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted by EPD/EMS in the first quarter of 1991. In includes the analytical data, field data, data review, quality control, and other documentation for this program, provides a record of the program's activities and rationale, and serves as an official document of the analytical results.

  9. Creating objective and measurable postgraduate year 1 residency graduation requirements.

    PubMed

    Starosta, Kaitlin; Davis, Susan L; Kenney, Rachel M; Peters, Michael; To, Long; Kalus, James S

    2017-03-15

    The process of developing objective and measurable postgraduate year 1 (PGY1) residency graduation requirements and a progress tracking system is described. The PGY1 residency accreditation standard requires that programs establish criteria that must be met by residents for successful completion of the program (i.e., graduation requirements), which should presumably be aligned with helping residents to achieve the purpose of residency training. In addition, programs must track a resident's progress toward fulfillment of residency goals and objectives. Defining graduation requirements and establishing the process for tracking residents' progress are left up to the discretion of the residency program. To help standardize resident performance assessments, leaders of an academic medical center-based PGY1 residency program developed graduation requirement criteria that are objective, measurable, and linked back to residency goals and objectives. A system for tracking resident progress relative to quarterly progress targets was instituted. Leaders also developed a focused, on-the-spot skills assessment termed "the Thunderdome," which was designed for objective evaluation of direct patient care skills. Quarterly data on residents' progress are used to update and customize each resident's training plan. Implementation of this system allowed seamless linkage of the training plan, the progress tracking system, and the specified graduation requirement criteria. PGY1 residency requirements that are objective, that are measurable, and that attempt to identify what skills the resident must demonstrate in order to graduate from the program were developed for use in our residency program. A system for tracking the residents' progress by comparing residents' performance to predetermined quarterly benchmarks was developed. Copyright © 2017 by the American Society of Health-System Pharmacists, Inc. All rights reserved.

  10. The RERTR Program : a status report.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Travelli, A.

    1998-10-19

    This paper describes the progress achieved by the Reduced Enrichment for Research and Test Reactors (RERTR) Program in collaboration with its many international partners since its inception in 1978. A brief summary of the results that the program had attained by the end of 1997 is followed by a detailed review of the major events, findings, and activities that took place in 1998. The past year was characterized by exceptionally important accomplishments and events for the RERTR program. Four additional shipments of spent fuel from foreign research reactors were accepted by the U.S. Altogether, 2,231 spent fuel assemblies from foreignmore » research reactors have been received by the U.S. under the acceptance policy. Fuel development activities began to yield solid results. Irradiations of the first two batches of microplates were completed. Preliminary postirradiation examinations of these microplates indicate excellent irradiation behavior of some of the fuel materials that were tested. These materials hold the promise of achieving the pro am goal of developing LEU research reactor fuels with uranium density in the 8-9 g /cm{sup 3} range. Progress was made in the Russian RERTR program, which aims to develop and demonstrate the technical means needed to convert Russian-supplied research reactors to LEU fuels. Feasibility studies for converting to LEU fuel four Russian-designed research reactors (IR-8 in Russia, Budapest research reactor in Hungary, MARIA in Poland, and WWR-SM in Uzbekistan) were completed. A new program activity began to study the feasibility of converting three Russian plutonium production reactors to the use of low-enriched U0{sub 2}-Al dispersion fuel, so that they can continue to produce heat and electricity without producing significant amounts of plutonium. The study of an alternative LEU core for the FRM-II design has been extended to address, with favorable results, the transient performance of the core under hypothetical accident conditions. A major milestone was accomplished in the development of a process to produce molybdenum-99 from fission targets utilizing LEU instead of HEU. Targets containing LEU metal foils were irradiated in the RAS-GAS reactor at BATAN, Indonesia, and molybdenum-99 was successfully extracted through the ensuing process. These are exciting times for the program and for all those involved in it, and last year's successes augur well for the future. However, as in the past, the success of the RERTR program will depend on the international friendship and cooperation that have always been its trademark.« less

  11. Subgrain refinement strengthening. Second quarterly progress report, January 1, 1975-March 31, 1975. [Epsilon-Brite 26-1

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Klundt, R.; Walser, B.; Monma, Y.

    During the past quarter (January-March 1975) we have initiated mechanical properties studies on type 304 stainless steel and on a ferritic alloy, E-Brite 26-1. Purpose of these studies was to establish a sound data base from which the alloys specifically chosen for this program can be evaluated (namely, ferritic steel, precipitation hardening austenitic stainless steel and a nickel rich austenitic alloy).

  12. Occidental vertical modified in situ process for the recovery of oil from oil shale. Phase II. Quarterly progress report, September 1-November 30, 1979

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    McDermott, William F.

    1979-12-01

    The major activities at OOSI's Logan Wash site during the quarter were: driving the access drifts towards the underground locations for Retorts 7 and 8; manway raise boring; constructing the change house; rubbling the first lift of Mini-Retort (MR)1; preparing the Mini-Retorts for tracer testing; coring of Retort 3E; and beginning the DOE instrumentation program.

  13. Applying Financial Portfolio Analysis to Government Program Portfolios

    DTIC Science & Technology

    2007-06-01

    himself points out, “The Rational Man, like the unicorn , does not exist” (Markowitz, 1959). The various investor assumptions presented above break down...originally envisioned benefits quickly grow (Levine, 2005). As a recent Government Accountability Office report notes, the sheer size of IT spending in the...shows no change in EAC for the first three quarters and a decrease in the fourth quarter- although the SV and CV shrink and grow during the same period

  14. The U.S. RERTR program status and progress.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Travelli, A.

    1998-01-21

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program since its inception in 1978 is described. A brief summary of the results which the RERTR Program had achieved by the end of 1996 in collaboration with its many international partners is followed by a detailed review of the major events, findings, and activities of 1997. Significant progress has been made during the past year. In the area of U.S. acceptance of spent fuel from foreign research reactors, several shipments have taken place and additional are being planned. Intense fuel development activities are in progress, including procurement ofmore » equipment, screening of candidate materials, and production of microplates. Irradiation of the first series of microplates began in August 1997 in the Advanced Test Reactor, in Idaho. Progress has been made in the Russian RERTR program, which aims to develop and demonstrate within five years the technical means needed to convert Russian-supplied research reactors to LEU fuels. The study of an alternative LEU core for the FRM-II design has been extended to address, with favorable results, controversial performance issues which were raised at last year's meeting. Progress was also made on several aspects of producing molybdenum-99 from fission targets utilizing LEU instead of HEU. Various types of targets and processes are being pursued, with FDA approval of an LEU process projected to occur within two years. The feasibility of LEU Fuel conversion for three important DOE research reactors (BMRR, HFBR, and HFIR) has been evaluated by the RERTR program. In spite of the many momentous events which have occurred during the intervening years, and the excellent progress achieved, the most important challenges that the RERTR program faces today are not very different in type from those that were faced during the first RERTR meeting. Now, as then, the most important task is to develop new LEU fuels satisfying requirements which cannot be satisfied by any existing fuel. These new advanced fuels will enable conversion of the reactors which cannot be converted today, ensure better efficiency and performance for all research reactors, and allow the design of more powerful new advanced LEU reactors. As in the past, the success of the RERTR program will depend on free exchange of ideas and information, and on the international friendship and cooperation that have been a trademark of the RERTR program since its inception.« less

  15. Natural gas imports and exports. First quarter report 1994

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1994-08-01

    The Office of Fuels Programs Prepares quarterly reports Summarizing the data provided by companies authorized to import or export natural gas. Companies are required, as a condition of their authorizations, to file quarterly reports with the OFP. This report is for the first quarter of 1994 (January--March). Attachment A shows the percentage of takes to maximum firm contract levels and the weighted average per unit price for each of the long-term importers during the five most recent reporting quarters. Attachment B shows volumes and prices of gas purchased by long-term importers and exporters during the past twelve months. Attachment Cmore » shows volume and price information for gas imported on a short-term basis. Attachment D shows the gas exported on a short-term basis to Canada and Mexico. During the first three months of 1994, data indicates that gas imports grew by about 14 percent over the level of the first quarter of 1993 (668 vs. 586 Bcf), with Canadian and Algerian imports increasing by 12 and 53 percent, respectively. During the same time period, exports declined by 15 percent (41 vs. 48 Bcf). Exports to Canada increased by 10 percent from the 1993 level (22 vs. 20 Bcf) and exports to Mexico decreased by 64 percent (5 vs. 14 Bcf).« less

  16. Composite armored vehicle advanced technology demonstator

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ostberg, D.T.; Dunfee, R.S.; Thomas, G.E.

    1996-12-31

    Composite structures are a key technology needed to develop future lightweight combat vehicles that are both deployable and survivable. The Composite Armored Vehicle Advanced Technology Demonstrator Program that started in fiscal year 1994 will continue through 1998 to verily that composite structures are a viable solution for ground combat vehicles. Testing thus far includes material characterization, structural component tests and full scale quarter section tests. Material and manufacturing considerations, tests, results and changes, and the status of the program will be described. The structural component tests have been completed successfully, and quarter section testing is in progress. Upon completion ofmore » the critical design review, the vehicle demonstrator will be Fabricated and undergo government testing.« less

  17. Review of Transient Testing of Fast Reactor Fuels in the Transient REActor Test Facility (TREAT)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Jensen, C.; Wachs, D.; Carmack, J.

    The restart of the Transient REActor Test (TREAT) facility provides a unique opportunity to engage the fast reactor fuels community to reinitiate in-pile experimental safety studies. Historically, the TREAT facility played a critical role in characterizing the behavior of both metal and oxide fast reactor fuels under off-normal conditions, irradiating hundreds of fuel pins to support fast reactor fuel development programs. The resulting test data has provided validation for a multitude of fuel performance and severe accident analysis computer codes. This paper will provide a review of the historical database of TREAT experiments including experiment design, instrumentation, test objectives, andmore » salient findings. Additionally, the paper will provide an introduction to the current and future experiment plans of the U.S. transient testing program at TREAT.« less

  18. Technical support to the Nuclear Regulatory Commission for the boiling water reactor blowdown heat transfer program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rice, R.E.

    Results are presented of studies conducted by Aerojet Nuclear Company (ANC) in FY 1975 to support the Nuclear Regulatory Commission (NRC) on the boiling water reactor blowdown heat transfer (BWR-BDHT) program. The support provided by ANC is that of an independent assessor of the program to ensure that the data obtained are adequate for verification of analytical models used for predicting reactor response to a postulated loss-of-coolant accident. The support included reviews of program plans, objectives, measurements, and actual data. Additional activity included analysis of experimental system performance and evaluation of the RELAP4 computer code as applied to the experiments.

  19. Nuclear Engine System Simulation (NESS) version 2.0

    NASA Technical Reports Server (NTRS)

    Pelaccio, Dennis G.; Scheil, Christine M.; Petrosky, Lyman J.

    1993-01-01

    The topics are presented in viewgraph form and include the following; nuclear thermal propulsion (NTP) engine system analysis program development; nuclear thermal propulsion engine analysis capability requirements; team resources used to support NESS development; expanded liquid engine simulations (ELES) computer model; ELES verification examples; NESS program development evolution; past NTP ELES analysis code modifications and verifications; general NTP engine system features modeled by NESS; representative NTP expander, gas generator, and bleed engine system cycles modeled by NESS; NESS program overview; NESS program flow logic; enabler (NERVA type) nuclear thermal rocket engine; prismatic fuel elements and supports; reactor fuel and support element parameters; reactor parameters as a function of thrust level; internal shield sizing; and reactor thermal model.

  20. 10 CFR 1.43 - Office of Nuclear Reactor Regulation.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Office of Nuclear Reactor Regulation. 1.43 Section 1.43 Energy NUCLEAR REGULATORY COMMISSION STATEMENT OF ORGANIZATION AND GENERAL INFORMATION Headquarters Program Offices § 1.43 Office of Nuclear Reactor Regulation. The Office of Nuclear Reactor Regulation— (a...

  1. 10 CFR 1.43 - Office of Nuclear Reactor Regulation.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Office of Nuclear Reactor Regulation. 1.43 Section 1.43 Energy NUCLEAR REGULATORY COMMISSION STATEMENT OF ORGANIZATION AND GENERAL INFORMATION Headquarters Program Offices § 1.43 Office of Nuclear Reactor Regulation. The Office of Nuclear Reactor Regulation— (a...

  2. 10 CFR 1.43 - Office of Nuclear Reactor Regulation.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Office of Nuclear Reactor Regulation. 1.43 Section 1.43 Energy NUCLEAR REGULATORY COMMISSION STATEMENT OF ORGANIZATION AND GENERAL INFORMATION Headquarters Program Offices § 1.43 Office of Nuclear Reactor Regulation. The Office of Nuclear Reactor Regulation— (a...

  3. 10 CFR 1.43 - Office of Nuclear Reactor Regulation.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Office of Nuclear Reactor Regulation. 1.43 Section 1.43 Energy NUCLEAR REGULATORY COMMISSION STATEMENT OF ORGANIZATION AND GENERAL INFORMATION Headquarters Program Offices § 1.43 Office of Nuclear Reactor Regulation. The Office of Nuclear Reactor Regulation— (a...

  4. 10 CFR 1.43 - Office of Nuclear Reactor Regulation.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Office of Nuclear Reactor Regulation. 1.43 Section 1.43 Energy NUCLEAR REGULATORY COMMISSION STATEMENT OF ORGANIZATION AND GENERAL INFORMATION Headquarters Program Offices § 1.43 Office of Nuclear Reactor Regulation. The Office of Nuclear Reactor Regulation— (a...

  5. Indian Education and Training Opportunities at Columbia Jr. College, [Columbia, California.

    ERIC Educational Resources Information Center

    Columbia Junior Coll., CA.

    The purpose of this project was to develop a transitional instructional program to serve out-of-school and drop-out American Indian youth entering vocational education programs in forest technology, fire science, heavy equipment maintenance and health occupations. The project was designed to develop a 3-quarter transitional program concerned with…

  6. The University Seminar Program: A Formative Evaluation of the First Year.

    ERIC Educational Resources Information Center

    Litwin, James; And Others

    In the Fall Quarter, 1975, the University Division of General Studies introduced a University Seminar Program whose aim was to provide new students, freshmen and transfers, with a more humanistic introduction to Bowling Green State University. The results and conclusions of the evaluation study regarding the first year of the program's operation…

  7. Cooperative Education in the Associated Schools of Construction.

    ERIC Educational Resources Information Center

    Chapin, L.; Roudebush, Wilfred H.; Krone, Stephen J.

    2003-01-01

    A survey of Associated Schools of Construction construction management programs (54 of 88 responded) indicated that 91% have some type of cooperative education program; 58% require it. Most programs have two work terms (either quarters or semesters) of coop earning 3-4 credit hours per term. The level of satisfaction among students, faculty and…

  8. 76 FR 21739 - Notice of Public Information Collection(s) Being Reviewed by the Federal Communications...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-18

    ... commercial limits on children's television programming. The records must be placed in the public file quarterly. The FCC Form 398, Children's Television Programming Reports, reflecting efforts made by the... radio stations, a list of community issues addressed by the station's programming. This list is kept on...

  9. Function of university reactors in operator licensing training for nuclear utilities

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Wicks, F.

    1985-11-01

    The director of the Division of the US Nuclear Regulatory Commission in generic letter 84-10, dated April 26, 1984, spoke the requirement that applicants for senior reactor operator licenses for power reactors shall have performed then reactor startups. Simulator startups were not acknowledged. Startups performed on a university reactor are acceptable. The content and results of a five-day program combining instruction and experiments with the Rensselaer reactor are summarized.

  10. Down-selection of candidate alloys for further testing of advanced replacement materials for LWR core internals

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Was, Gary; Leonard, Keith J.; Tan, Lizhen

    Life extension of the existing nuclear reactors imposes irradiation of high fluences to structural materials, resulting in significant challenges to the traditional reactor materials such as type 304 and 316 stainless steels. Advanced alloys with superior radiation resistance will increase safety margins, design flexibility, and economics for not only the life extension of the existing fleet but also new builds with advanced reactor designs. The Electric Power Research Institute (EPRI) teamed up with Department of Energy (DOE) Light Water Reactor Sustainability Program to initiate the Advanced Radiation Resistant Materials (ARRM) program, aiming to identify and develop advanced alloys with superiormore » degradation resistance in light water reactor (LWR)-relevant environments by 2024.« less

  11. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Stillman, J. A.; Feldman, E. E.; Wilson, E. H.

    This report contains the results of reactor accident analyses for the University of Missouri Research Reactor (MURR). The calculations were performed as part of the conversion from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL), the MURR Facility, and the Nuclear Engineering Program – College of Engineering, University of Missouri-Columbia. The core conversion to LEU is being performed with financial support from the U. S. government. This report contains themore » results of reactor accident analyses for the University of Missouri Research Reactor (MURR). The calculations were performed as part of the conversion from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL), the MURR Facility, and the Nuclear Engineering Program – College of Engineering, University of Missouri-Columbia. The core conversion to LEU is being performed with financial support from the U. S. government. In the framework of non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that could be used for nuclear weapons. In this geopolitical context most research and test reactors, both domestic and international, have started a program of conversion to the use of LEU fuel. A new type of LEU fuel based on an alloy of uranium and molybdenum (U-Mo) is expected to allow the conversion of U.S. domestic high performance reactors like MURR. This report presents the results of a study of core behavior under a set of accident conditions for MURR cores fueled with HEU U-Alx dispersion fuel or LEU monolithic U-Mo alloy fuel with 10 wt% Mo (U-10Mo).« less

  12. Nuclear medicine program progress report for quarter ending September 30, 1996

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.

    1997-01-01

    The reactor production yields of tungsten-188 produced by neutron capture by enriched tungsten-186 in the HFIR and other reactors are nearly an order of magnitude lower than expected by calculation using established cross section values. Since neutron capture of tungsten-188 may be the major factor which significantly reduces the observed yields of tungsten-188, the authors have evaluated the possible burn-up cross section of the tungsten-188 product. Tungsten-189 was produced by irradiating a radioactive target containing a known amount of {sup 188}W. In order to reduce the radiation level to an acceptable level (<20% detector dead time), the authors chemically removedmore » >90% of {sup 188}Re, which is the decay product of {sup 188}W, prior to irradiation. They were able to confirm the two predominant {gamma}-rays in the decay of {sup 189}W, 260.1 {+-} 1.4 and 421.5 {+-} 1.6 keV. By following the decay of these {gamma}-rays in two sets of experiments, a half-life of 10.8 {+-} 0.3 m was obtained for {sup 189}W. Based on a knowledge of the {sup 188}W content of target (52.6 mBq), neutron flux of 5 {times} 10{sup 13} n {center_dot} s{sup {minus}1} {center_dot} cm{sup {minus}2}, irradiation time of 10 min and with the assumption of 100% intensity for 260.1 and 421.5 keV {gamma}-rays, a cross-section of 12.0 {+-} 2.5 b was calculated for burn-up cross-section of {sup 188}W, which helps explain the greatly reduced production yields of {sup 188}W.« less

  13. Alternate Fuel Cycle Technologies/Thorium Fuel Cycle Technology Programs. Quarterly report for period 1 April--30 June 1978

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Vondra, B.L.

    1978-08-01

    Voloxidation and dissolution studies: rotary-kiln heat-transfer tests are under way using a small rotary kiln along with the development of a mathematical model to determine kiln-heat-flux profiles necessary to maintain a desired temperature gradient. The erosion/corrosion test for evaluating materials of construction is operational. Fuel from a BWR (Big Rock Point) yielded more fine solid residue on dissolution than in previous tests with PWR fuel. Two additional parametric voloxidation tests with H.B. Robinson fuel compared air vs pure oxygen atmospheres at 550{sup 0}C; overall tritium release and subsequent fuel dissolution were equivalent. Thorium dissolution studies: the dissolution rate of thoriamore » in fluoride-catalyzed 8 to 14 M HNO{sub 3} (100{sup 0}C) was max between 0.04 to 0.06 M HF; at higher fluoride concentrations, ThF{sub 4}.5H{sub 2}O precipitated. The rate of zircaloy dissolution continued to increase with increasing fluoride concentration. Stainless-steel-clad (Th,U)0{sub 2} fuel rods irradiated in the NRX reactor were sheared, voloxidized, and dissolved. {le}10% of the tritium was released during voloxidation in air at 600{sup 0}C. Carbon-14 removal from off-gas and fixation: carbon dioxide removal with Linde 13X molecular sieves to less than 100 ppB was experimentally verified using 300 ppM CO in air. Decontamination factors from 3000 to 7500 were obtained for CO{sub 2} removal in the gas-slurry stirred-tank reactor with CA(OH){sub 2}.or Ba(0H){sub 2}/sup .8H2O./. With Ba(OH){sub 2}.H{sub 2}0{sup 2} in a fixed-bed column, decontamination factors of about 30,000 were obtained.« less

  14. Alloy catalysts with monolith supports for methanation of coal-derived gases. Quarterly technical progress report, September 21-December 20, 1979

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bartholomew, C.H.

    1980-01-05

    Tests for catalyst deactivation by carbon deposition in a Berty reactor showed that CO partial pressure exerted a greater influence on deactivation than H/sub 2/ partial pressure. In kinetic studies in which H/sub 2/O vapor was added to the reactant gases, H/sub 2/O was found to inhibit the methanation reaction. H/sub 2/O inhibition was found to increase with temperature and loss of activity was observed at H/sub 2/O/CO ratios greater than one. The order of methanation with respect to H/sub 2/ and CO varies over the range of temperature from 498 to 598/sup 0/K. Rate data indicate a change inmore » mechanism or rate determining step at higher temperatures. Our experience with a quartz CFSTR has shown that this reactor is very delicate and needs near constant attention to maintain proper working order.« less

  15. 7 CFR 4288.113 - Payment record requirements.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... SERVICE AND RURAL UTILITIES SERVICE, DEPARTMENT OF AGRICULTURE PAYMENT PROGRAMS Advanced Biofuel Payment... for Program payments, an advanced biofuel producer must maintain records for all relevant fiscal years and fiscal year quarters for each advanced biofuel facility indicating: (a) The type of eligible...

  16. U.S. advanced launch vehicle technology programs : Quarterly Launch Report : special report

    DOT National Transportation Integrated Search

    1996-01-01

    U.S. firms and U.S. government agencies are jointly investing in advanced launch vehicle technology. This Special Report summarizes U.S. launch vehicle technology programs and highlights the changing : roles of government and industry players in pick...

  17. 34 CFR 668.8 - Eligible program.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... least a one-academic-year training program that leads to a certificate, or other nondegree recognized... quarter hours; (iii) Must provide undergraduate training that prepares a student for gainful employment in...) Provide undergraduate training that prepares a student for gainful employment in a recognized occupation...

  18. 34 CFR 668.8 - Eligible program.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... least a one-academic-year training program that leads to a certificate, or other nondegree recognized... quarter hours; (iii) Must provide undergraduate training that prepares a student for gainful employment in...) Provide undergraduate training that prepares a student for gainful employment in a recognized occupation...

  19. 34 CFR 668.8 - Eligible program.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... least a one-academic-year training program that leads to a certificate, or other nondegree recognized... quarter hours; (iii) Must provide undergraduate training that prepares a student for gainful employment in...) Provide undergraduate training that prepares a student for gainful employment in a recognized occupation...

  20. Innovative instructional strategy using cinema films in an undergraduate nursing course.

    PubMed

    Hyde, Norlyn B; Fife, Elizabeth

    2005-01-01

    Educators can develop innovative instructional strategies to engage students within the philosophical framework of Constructivism. To that end, the authors used films--Hollywood movies--to enhance their curriculum on neurological and psychopathological illnesses. During the fourth quarter of a seven-quarter associate degree nursing program, students developed case studies of the disorders portrayed in selected films. The authors outline the methods used to implement this approach and discuss evaluations from student and faculty perspectives.

  1. Joint Force Quarterly. Issue 70, 3rd Quarter, July 2013

    DTIC Science & Technology

    2013-07-01

    such as solar panels and wind turbines for battlefield operations in Iraq. General Zilmer’s memo noted that without renewable power, U.S. forces...programs. The private sector may be leveraged through other incentives. Tax policy could encour- age the importation of solar panels, wind turbines , and...officers with infantry battalions—to name a few.31 In short, primary collection is done at the small unit level where there are “many sensors ,” and

  2. REACTOR PHYSICS CONSTANTS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    None

    1963-07-01

    This second edition is based on data available on March 15, 1961. Sections on constants necessary for the interpretation of experimental data and on digital computer programs for reactor design and reactor physics have been added. 1344 references. (D.C.W.)

  3. The selective treatment of clinical mastitis based on on-farm culture results: I. Effects on antibiotic use, milk withholding time, and short-term clinical and bacteriological outcomes.

    PubMed

    Lago, A; Godden, S M; Bey, R; Ruegg, P L; Leslie, K

    2011-09-01

    The objective of this multi-state, multi-herd clinical trial was to evaluate the efficacy of using an on-farm culture system to guide strategic treatment decisions in cows with clinical mastitis. The study was conducted in 8 commercial dairy farms ranging in size from 144 to 1,795 cows from Minnesota, Wisconsin, and Ontario, Canada. A total of 422 cows affected with mild or moderate clinical mastitis in 449 quarters were randomly assigned to either (1) a positive-control treatment program or (2) an on-farm, culture-based treatment program. Quarter cases assigned to the positive-control group received immediate on-label intramammary treatment with cephapirin sodium. Quarters assigned to the culture-based treatment program were cultured on-farm and treated with cephapirin sodium after 18 to 24h of incubation if they had gram-positive growth or a mixed infection. Quarters with gram-negative or no growth did not receive intramammary therapy. The proportion of quarter cases assigned to positive-control and culture-based treatments that received intramammary antibiotic therapy because of study assignment was 100 and 44%, respectively; the proportion of cases that received secondary antibiotic therapy was 36 and 19%, respectively; and the proportion of cases that received intramammary antibiotic therapy because of study assignment or secondary therapy was 100 and 51%, respectively. A tendency existed for a decrease in the number of days in which milk was discarded from cows assigned to the culture-based treatment program versus cows assigned to the positive-control group (5.9 vs. 5.2 d). No statistically significant differences existed between cases assigned to the positive-control and cases assigned to the culture-based treatment program in days to clinical cure (2.7 vs. 3.2 d), bacteriological cure risk within 21 d of enrollment (71 vs. 60%), new intramammary infection risk within 21 d of enrollment (50 vs. 50%), and treatment failure risk (presence of infection, secondary treatment, clinical mastitis recurrence, or removal from herd within 21 d after enrollment; 81 vs. 78%). In summary, the use of an on-farm culture system to guide the strategic treatment of clinical mastitis reduced intramammary antibiotic use by half and tended to decrease milk withholding time by 1 d, without significant differences in days to clinical cure, bacteriological cure risk, new intramammary infection risk, and treatment failure risk within 21 d after the clinical mastitis event. Copyright © 2011 American Dairy Science Association. Published by Elsevier Inc. All rights reserved.

  4. Policies and practices pertaining to the selection, qualification requirements, and training programs for nuclear-reactor operating personnel at the Oak Ridge National Laboratory

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Culbert, W.H.

    1985-10-01

    This document describes the policies and practices of the Oak Ridge National Laboratory (ORNL) regarding the selection of and training requirements for reactor operating personnel at the Laboratory's nuclear-reactor facilities. The training programs, both for initial certification and for requalification, are described and provide the guidelines for ensuring that ORNL's research reactors are operated in a safe and reliable manner by qualified personnel. This document gives an overview of the reactor facilities and addresses the various qualifications, training, testing, and requalification requirements stipulated in DOE Order 5480.1A, Chapter VI (Safety of DOE-Owned Reactors); it is intended to be in compliancemore » with this DOE Order, as applicable to ORNL facilities. Included also are examples of the documentation maintained amenable for audit.« less

  5. Neutrino Physics with Nuclear Reactors: An Overview

    NASA Astrophysics Data System (ADS)

    Ochoa-Ricoux, J. P.

    Nuclear reactors provide an excellent environment for studying neutrinos and continue to play a critical role in unveiling the secrets of these elusive particles. A rich experimental program with reactor antineutrinos is currently ongoing, and leads the way in precision measurements of several oscillation parameters and in searching for new physics, such as the existence of light sterile neutrinos. Ongoing experiments have also been able to measure the flux and spectral shape of reactor antineutrinos with unprecedented statistics and as a function of core fuel evolution, uncovering anomalies that will lead to new physics and/or to an improved understanding of antineutrino emission from nuclear reactors. The future looks bright, with an aggressive program of next generation reactor neutrino experiments that will go after some of the biggest open questions in the field. This includes the JUNO experiment, the largest liquid scintillator detector ever constructed which will push the limits of this detection technology.

  6. R and D program for French sodium fast reactor: On the description and detection of sodium boiling phenomena during sub-assembly blockages

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Vanderhaegen, M.; Laboratory of Waves and Acoustic, Institut Langevin, ESPCI ParisTech, 10 rue Vauquelin, 75005 Paris; Paumel, K.

    2011-07-01

    In support of the French ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) reactor program, which aims to demonstrate the industrial applicability of sodium fast reactors with an increased level of safety demonstration and availability compared to the past French sodium fast reactors, emphasis is placed on reactor instrumentation. It is in this framework that CEA studies continuous core monitoring to detect as early as possible the onset of sodium boiling. Such a detection system is of particular interest due to the rapid progress and the consequences of a Total Instantaneous Blockage (TIB) at a subassembly inlet, where sodium boilingmore » intervenes in an early phase. In this paper, the authors describe all the particularities which intervene during the different boiling stages and explore possibilities for their detection. (authors)« less

  7. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mulder, R.U.; Benneche, P.E.; Hosticka, B.

    The objective of the DOE supported Reactor Sharing Program is to increase the availability of university nuclear reactor facilities to non-reactor-owning educational institutions. The educational and research programs of these user institutions is enhanced by the use of the nuclear facilities. Several methods have been used by the UVA Reactor Facility to achieve this objective. First, many college and secondary school groups toured the Reactor Facility and viewed the UVAR reactor and associated experimental facilities. Second, advanced undergraduate and graduate classes from area colleges and universities visited the facility to perform experiments in nuclear engineering and physics which would notmore » be possible at the user institution. Third, irradiation and analysis services at the Facility have been made available for research by faculty and students from user institutions. Fourth, some institutions have received activated material from UVA from use at their institutions. These areas are discussed in this report.« less

  8. DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    The objective of the DOE supported Reactor Sharing Program is to increase the availability of university nuclear reactor facilities to non-reactor-owning educational institutions. The educational and research programs of these user institutions is enhanced by the use of the nuclear facilities. Several methods have been used by the UVA Reactor Facility to achieve this objective. First, many college and secondary school groups toured the Reactor Facility and viewed the UVAR reactor and associated experimental facilities. Second, advanced undergraduate and graduate classes from area colleges and universities visited the facility to perform experiments in nuclear engineering and physics which would notmore » be possible at the user institution. Third, irradiation and analysis services at the Facility have been made available for research by faculty and students from user institutions. Fourth, some institutions have received activated material from UVA for use at their institutions. These areas are discussed further in the report.« less

  9. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Mulder, R.U.; Benneche, P.E.; Hosticka, B.

    The objective of the DOE supported Reactor Sharing Program is to increase the availability of university nuclear reactor facilities to non-reactor-owning educational institutions. The educational and research programs of these user institutions is enhanced by the use of the nuclear facilities. Several methods have been used by the UVA Reactor Facility to achieve this objective. First, many college and secondary school groups toured the Reactor Facility and viewed the UVAR reactor and associated experimental facilities. Second, advanced undergraduate and graduate classes from area colleges and universities visited the facility to perform experiments in nuclear engineering and physics which would notmore » be possible at the user institution. Third, irradiation and analysis services at the Facility have been made available for research by faculty and students from user institutions. Fourth, some institutions have received activated material from UVA for use at their institutions. These areas are discussed here.« less

  10. Advanced Thermal Emission Imaging Systems Definition and Development

    NASA Technical Reports Server (NTRS)

    Blasius, Karl; Nava, David (Technical Monitor)

    2002-01-01

    Santa Barbara Remote Sensing (SBRS), Raytheon Company, is pleased to submit this quarterly progress report of the work performed in the third quarter of Year 2 of the Advanced THEMIS Project, July through September 2002. We review here progress in the proposed tasks. During July through September 2002 progress was made in two major tasks, Spectral Response Characterization and Flight Instrument Definition. Because of staffing problems and technical problems earlier in the program we have refocused the remaining time and budget on the key technical tasks. Current technical problems with a central piece of test equipment has lead us to request a 1 quarter extension to the period of performance. This request is being made through a separate letter independent of this report.

  11. Routine Leak Testing in Colorectal Surgery in the Surgical Care and Outcomes Assessment Program

    PubMed Central

    Kwon, Steve; Morris, Arden; Billingham, Richard; Frankhouse, Joseph; Horvath, Karen; Johnson, Morrie; McNevin, Shane; Simons, Anthony; Symons, Rebecca; Steele, Scott; Thirlby, Richard; Whiteford, Mark; Flum, David R.

    2014-01-01

    Objective To evaluate the effect of routine anastomotic leak testing (performed to screen for leaks) vs selective testing (performed to evaluate for a suspected leak in a higher-risk or technically difficult anastomosis) on outcomes in colorectal surgery because the value of provocative testing of colorectal anastomoses as a quality improvement metric has yet to be determined. Design Observational, prospectively designed cohort study. Setting Data from Washington state’s Surgical Care and Outcomes Assessment Program (SCOAP). Patients Patients undergoing elective left-sided colon or rectal resections at 40 SCOAP hospitals from October 1, 2005, to December 31, 2009. Interventions Use of leak testing, distinguishing procedures that were performed at hospitals where leak testing was selective (<90% use) or routine (≥90% use) in a given calendar quarter. Main Outcome Measure Adjusted odds ratio of a composite adverse event (CAE) (unplanned postoperative intervention and/or in-hospital death) at routine testing hospitals. Results Among 3449 patients (mean [SD] age, 58.8[14.8] years; 55.0% women), the CAE rate was 5.5%. Provocative leak testing increased (from 56% in the starting quarter to 76% in quarter 16) and overall rates of CAE decreased (from 7.0% in the starting quarter to 4.6% in quarter 16; both P ≤ .01) over time. Among patients at hospitals that performed routine leak testing, we found a reduction of more than 75% in the adjusted risk of CAEs (odds ratio, 0.23; 95% CI, 0.05–0.99). Conclusion Routine leak testing of left-sided colorectal anastomoses appears to be associated with a reduced rate of CAEs within the SCOAP network and meets many of the criteria of a worthwhile quality improvement metric. PMID:22508778

  12. Routine leak testing in colorectal surgery in the Surgical Care and Outcomes Assessment Program.

    PubMed

    Kwon, Steve; Morris, Arden; Billingham, Richard; Frankhouse, Joseph; Horvath, Karen; Johnson, Morrie; McNevin, Shane; Simons, Anthony; Symons, Rebecca; Steele, Scott; Thirlby, Richard; Whiteford, Mark; Flum, David R

    2012-04-01

    To evaluate the effect of routine anastomotic leak testing (performed to screen for leaks) vs selective testing (performed to evaluate for a suspected leak in a higher-risk or technically difficult anastomosis) on outcomes in colorectal surgery because the value of provocative testing of colorectal anastomoses as a quality improvement metric has yet to be determined. Observational, prospectively designed cohort study. Data from Washington state's Surgical Care and Outcomes Assessment Program (SCOAP). Patients undergoing elective left-sided colon or rectal resections at 40 SCOAP hospitals from October 1, 2005, to December 31, 2009. Use of leak testing, distinguishing procedures that were performed at hospitals where leak testing was selective (<90% use) or routine (≥ 90% use) in a given calendar quarter. Adjusted odds ratio of a composite adverse event (CAE) (unplanned postoperative intervention and/or in-hospital death) at routine testing hospitals. Among 3449 patients (mean [SD] age, 58.8 [14.8] years; 55.0% women), the CAE rate was 5.5%. Provocative leak testing increased (from 56% in the starting quarter to 76% in quarter 16) and overall rates of CAE decreased (from 7.0% in the starting quarter to 4.6% in quarter 16; both P ≤ .01) over time. Among patients at hospitals that performed routine leak testing, we found a reduction of more than 75% in the adjusted risk of CAEs (odds ratio, 0.23; 95% CI, 0.05-0.99). Routine leak testing of left-sided colorectal anastomoses appears to be associated with a reduced rate of CAEs within the SCOAP network and meets many of the criteria of a worthwhile quality improvement metric.

  13. Materials technology for an advanced space power nuclear reactor concept: Program summary

    NASA Technical Reports Server (NTRS)

    Gluyas, R. E.; Watson, G. K.

    1975-01-01

    The results of a materials technology program for a long-life (50,000 hr), high-temperature (950 C coolant outlet), lithium-cooled, nuclear space power reactor concept are reviewed and discussed. Fabrication methods and compatibility and property data were developed for candidate materials for fuel pins and, to a lesser extent, for potential control systems, reflectors, reactor vessel and piping, and other reactor structural materials. The effects of selected materials variables on fuel pin irradiation performance were determined. The most promising materials for fuel pins were found to be 85 percent dense uranium mononitride (UN) fuel clad with tungsten-lined T-111 (Ta-8W-2Hf).

  14. Turbulence coefficients and stability studies for the coaxial flow or dissimiliar fluids. [gaseous core nuclear reactors

    NASA Technical Reports Server (NTRS)

    Weinstein, H.; Lavan, Z.

    1975-01-01

    Analytical investigations of fluid dynamics problems of relevance to the gaseous core nuclear reactor program are presented. The vortex type flow which appears in the nuclear light bulb concept is analyzed along with the fluid flow in the fuel inlet region for the coaxial flow gaseous core nuclear reactor concept. The development of numerical methods for the solution of the Navier-Stokes equations for appropriate geometries is extended to the case of rotating flows and almost completes the gas core program requirements in this area. The investigations demonstrate that the conceptual design of the coaxial flow reactor needs further development.

  15. Reactor Physics Scoping and Characterization Study on Implementation of TRIGA Fuel in the Advanced Test Reactor

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Jennifer Lyons; Wade R. Marcum; Mark D. DeHart

    2014-01-01

    The Advanced Test Reactor (ATR), under the Reduced Enrichment for Research and Test Reactors (RERTR) Program and the Global Threat Reduction Initiative (GTRI), is conducting feasibility studies for the conversion of its fuel from a highly enriched uranium (HEU) composition to a low enriched uranium (LEU) composition. These studies have considered a wide variety of LEU plate-type fuels to replace the current HEU fuel. Continuing to investigate potential alternatives to the present HEU fuel form, this study presents a preliminary analysis of TRIGA® fuel within the current ATR fuel envelopes and compares it to the functional requirements delineated by themore » Naval Reactors Program, which includes: greater than 4.8E+14 fissions/s/g of 235U, a fast to thermal neutron flux ratio that is less than 5% deviation of its current value, a constant cycle power within the corner lobes, and an operational cycle length of 56 days at 120 MW. Other parameters outside those put forth by the Naval Reactors Program which are investigated herein include axial and radial power profiles, effective delayed neutron fraction, and mean neutron generation time.« less

  16. Development of advanced strain diagnostic techniques for reactor environments.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Fleming, Darryn D.; Holschuh, Thomas Vernon,; Miller, Timothy J.

    2013-02-01

    The following research is operated as a Laboratory Directed Research and Development (LDRD) initiative at Sandia National Laboratories. The long-term goals of the program include sophisticated diagnostics of advanced fuels testing for nuclear reactors for the Department of Energy (DOE) Gen IV program, with the future capability to provide real-time measurement of strain in fuel rod cladding during operation in situ at any research or power reactor in the United States. By quantifying the stress and strain in fuel rods, it is possible to significantly improve fuel rod design, and consequently, to improve the performance and lifetime of the cladding.more » During the past year of this program, two sets of experiments were performed: small-scale tests to ensure reliability of the gages, and reactor pulse experiments involving the most viable samples in the Annulated Core Research Reactor (ACRR), located onsite at Sandia. Strain measurement techniques that can provide useful data in the extreme environment of a nuclear reactor core are needed to characterize nuclear fuel rods. This report documents the progression of solutions to this issue that were explored for feasibility in FY12 at Sandia National Laboratories, Albuquerque, NM.« less

  17. Thermal energy storage subsystems. A collection of quarterly reports

    NASA Technical Reports Server (NTRS)

    1978-01-01

    The design, development, and progress toward the delivery of three subsystems is discussed. The subsystem used a salt hydrate mixture for thermal energy storage. The program schedules, technical data, and other program activities from October 1, 1976, through December 31, 1977 are presented.

  18. Developing a Taxonomy of Institutional Sponsored Work Experience.

    ERIC Educational Resources Information Center

    Heinemann, Harry N.; Wilson, James W.

    1995-01-01

    The name of the work-integrated education program, its learning objectives, and other program characteristics were gathered from 18 colleges/universities and 2 community colleges. Three-quarters use internship, practicum, or co-op. Factor analysis grouped objectives as cognitive, communication, job seeking, personal development, career…

  19. Telescience Testbed Pilot Program

    NASA Technical Reports Server (NTRS)

    Gallagher, Maria L. (Editor); Leiner, Barry M. (Editor)

    1988-01-01

    The Telescience Testbed Pilot Program is developing initial recommendations for requirements and design approaches for the information systems of the Space Station era. During this quarter, drafting of the final reports of the various participants was initiated. Several drafts are included in this report as the University technical reports.

  20. 76 FR 48563 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-January Through March 2011...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-08

    ...-7205 Ventricular Assist Device (Destination Therapy) Facilities. XIII Medicare-Approved Lung JoAnna...-Approved Ventricular Assist Device (Destination Therapy) Facilities, Addendum XIII: Lung Volume Reduction...-Approved Ventricular Assist Device (Destination Therapy) Facilities (January Through March 2011) Addendum...

  1. Marketing the Job Training Partnership Act.

    ERIC Educational Resources Information Center

    Markowicz, Arlene, Ed.; And Others

    1984-01-01

    This quarterly contains 11 bulletins that profile marketing campaigns for the Job Training Partnership Act (JTPA) that have been implemented successfully in local programs throughout the United States. For each program, the description provides information on the operator, funding, results, time span, background, marketing/public relations…

  2. (Development of advanced models of the MCC full expansion (quiet) engine): First quarterly report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    This is the first quarterly report to the Department of Energy on the progress associated with the development of advanced models of the MCC full expansion (quiet) engine. These models will be evaluated in successive steps and eventually incorporated into a lawn mower for the purpose of commercializing the engine for small wheeled lawn and garden applications. During the first three months of the program (July 1 thru Sept 30), the Phase I design was basically completed with the exception of some engine/lawn mower interface hardware which will be completed during the final stages of the development program after wemore » have selected a lawn mower deck. Rick Erickson, the design engineer for the program, completed the initial parts drawings utilizing the computer drafting system together with guidance from Fredrick Erickson, the program principal engineer and Jeff Erickson, who is in charge of manufacturing the engines. A miniature copy of these drawings is included in the appendix for your review.« less

  3. Darbepoetin alfa therapeutic interchange protocol for anemia in dialysis.

    PubMed

    Brophy, Donald F; Ripley, Elizabeth Bd; Kockler, Denise R; Lee, Seina; Proeschel, Lori A

    2005-11-01

    Erythropoiesis-stimulating proteins, such as erythropoietin alfa and darbepoetin alfa, have positively impacted anemia management. These medications improve patient outcomes and quality of life. Their costs, however, remain a major barrier for health systems. To evaluate the development, implementation, and cost-effectiveness of an inpatient therapeutic interchange protocol for erythropoiesis-stimulating proteins at a large, tertiary care, university-affiliated health system. Virginia Commonwealth University Health System (VCUHS) developed and implemented a therapeutic interchange program to convert therapy for all inpatients undergoing dialysis from erythropoietin alfa to darbepoetin alfa for treatment of chronic kidney disease-related anemia. An evaluation of the economic impact of this program on drug expenditures over a fiscal quarter (2003) was conducted using historical comparator data (2002). Preliminary evaluation of the program demonstrated cost-savings and reduced drug utilization of erythropoiesis-stimulating proteins in hospitalized dialysis patients. For the first quarter of 2003 compared with the first quarter of 2002, VCUHS realized a cost-savings of nearly 10,000 US dollars, which was related to the program's aggressive screening procedure. When these data were normalized for equal numbers of patients in each group receiving one of the drugs, the actual cost-savings was over 2000 US dollars. These cost-savings are largely due to reduced utilization of these expensive biotechnology products with implementation of a dosing protocol. VCUHS has successfully developed and implemented a darbepoetin alfa therapeutic interchange protocol for hospitalized dialysis patients. This has translated into reduced use of erythropoiesis-stimulating proteins, resulting in cost-savings for the health system.

  4. A Neutronic Program for Critical and Nonequilibrium Study of Mobile Fuel Reactors: The Cinsf1D Code

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Lecarpentier, David; Carpentier, Vincent

    2003-01-15

    Molten salt reactors (MSRs) have the distinction of having a liquid fuel that is also the coolant. The transport of delayed-neutron precursors by the fuel modifies the precursors' equation. As a consequence, it is necessary to adapt the methods currently used for solid fuel reactors to achieve critical or kinetics calculations for an MSR. A program is presented for which this adaptation has been carried out within the framework of the two-energy-group diffusion theory with one dimension of space. This program has been called Cinsf1D (Cinetique pour reacteur a sels fondus 1D)

  5. Los Angeles County Juvenile Justice Crime Prevention Act. RAND Quarterly Report, October 2008. TR-621-LACPD

    ERIC Educational Resources Information Center

    Fain, Terry; Turner, Susan; Ridgeway, Greg

    2008-01-01

    In July 2008, RAND Corporation staff conducted Correctional Program Checklist (CPC) assessments of five home-based programs (Asian Youth Center, Communities in Schools, Inter-Agency Drug Abuse Recovery Programs, Soledad Enrichment Action, and Stars Behavioral Health Group) as part of its ongoing evaluation of Juvenile Justice Crime Prevention Act…

  6. Real Estate Education: A Curriculum Guide for a Two-year Post Secondary Program.

    ERIC Educational Resources Information Center

    Overton, R. Jean

    This curriculum guide was designed to assist in the development of associate degree programs and/or options for real estate education in North Carolina community colleges. The real estate education program prescribed by this guide spans six academic quarters. The 28 courses listed cover such subject areas as real estate fundamentals, human…

  7. Global Uranium And Thorium Resources: Are They Adequate To Satisfy Demand Over The Next Half Century?

    NASA Astrophysics Data System (ADS)

    Lambert, I. B.

    2012-04-01

    This presentation will consider the adequacy of global uranium and thorium resources to meet realistic nuclear power demand scenarios over the next half century. It is presented on behalf of, and based on evaluations by, the Uranium Group - a joint initiative of the OECD Nuclear Energy Agency and the International Atomic Energy Agency, of which the author is a Vice Chair. The Uranium Group produces a biennial report on Uranium Resources, Production and Demand based on information from some 40 countries involved in the nuclear fuel cycle, which also briefly reviews thorium resources. Uranium: In 2008, world production of uranium amounted to almost 44,000 tonnes (tU). This supplied approximately three-quarters of world reactor requirements (approx. 59,000 tU), the remainder being met by previously mined uranium (so-called secondary sources). Information on availability of secondary sources - which include uranium from excess inventories, dismantling nuclear warheads, tails and spent fuel reprocessing - is incomplete, but such sources are expected to decrease in market importance after 2013. In 2008, the total world Reasonably Assured plus Inferred Resources of uranium (recoverable at less than 130/kgU) amounted to 5.4 million tonnes. In addition, it is clear that there are vast amounts of uranium recoverable at higher costs in known deposits, plus many as yet undiscovered deposits. The Uranium Group has concluded that the uranium resource base is more than adequate to meet projected high-case requirements for nuclear power for at least half a century. This conclusion does not assume increasing replacement of uranium by fuels from reprocessing current reactor wastes, or by thorium, nor greater reactor efficiencies, which are likely to ameliorate future uranium demand. However, progressively increasing quantities of uranium will need to be mined, against a backdrop of the relatively small number of producing facilities around the world, geopolitical uncertainties and strong opposition to growth of nuclear power in a number of quarters - it is vital that the market provides incentives for exploration and development of environmentally sustainable mining operations. Thorium: World Reasonably Assured plus Inferred Resources of thorium are estimated at over 2.2 million tonnes, in hard rock and heavy mineral sand deposits. At least double this amount is considered to occur in as yet undiscovered thorium deposits. Currently, demand for thorium is insignificant, but even a major shift to thorium-fueled reactors would not make significant inroads into the huge resource base over the next half century.

  8. Tory II-A: a nuclear ramjet test reactor

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hadley, J.W.

    Declassified 28 Nov 1973. The first test reactor in the Pluto program, leading to development of a nuclear ramjet engine, is called Tory II-A. While it is not an actual prototype engine, this reactor embodies a core design which is considered feasible for an engine, and operation of the reactor will provide a test of that core type as well as more generalized values in reactor design and testing. The design of Tory II-A and construction of the reactor and of its test facility are described. Operation of the Tory II-A core at a total power of 160 megawatts, withmore » 800 pounds of air per second passing through the core and emerging at a temperature of 2000 deg F, is the central objective of the test program. All other reactor and facility components exist to support operation of the core, and preliminary steps in the test program itself will be directed primarily toward ensuring attalnment of full-power operation and collection of meaningful data on core behavior during that operation. The core, 3 feet in diameter and 41/2 feet long, will be composed of bundled ceramic tubes whose central holes will provide continuous air passages from end to end of the reactor. These tubes are to be composed of a homogeneous mixture of UO/sub 2/ fuel and BeO moderator, compacted and sintered to achieve high strength and density. (30 references) (auth)« less

  9. Development of an Applied Fisheries Science Program for Native Alaskans at Sheldon Jackson College (Sitka, Alaska). Third Progress Report, 1 January 1976.

    ERIC Educational Resources Information Center

    Seifert, Mel

    Covering the period between July 1 to December 31, 1976, this third semi-annual report on the Applied Fishery Science Program operative at Sheldon Jackson College in Sitka, Alaska deals primarily with the first quarter of hatchery and educational program operation. Specifically, this report addresses the following: Program Objectives; Advisory…

  10. Determination of the Arrhenius Activation Energy Using a Temperature-Programmed Flow Reactor.

    ERIC Educational Resources Information Center

    Chan, Kit-ha C.; Tse, R. S.

    1984-01-01

    Describes a novel method for the determination of the Arrhenius activation energy, without prejudging the validity of the Arrhenius equation or the concept of activation energy. The method involves use of a temperature-programed flow reactor connected to a concentration detector. (JN)

  11. Novel experimental studies for coal liquefaction: Quarterly progress report, October 1, 1987-December 31, 1987. [In Supercritical State

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Holder, G.D.; Tierney, J.W.

    Experimental work is presently being concentrated on a two-step synthesis of methanol from CO and H/sub 2/ Which consists of the carbonylation of a molecule of methanol to methyl formate followed by hydrogenation to form two molecules of methanol. Carrying out both reactions concurrently gives different results than predicted. One explanation is interaction between the two catalysts. Since one catalyst is homogeneous and the other heterogeneous, the interaction, due to absorption of the homogeneous catalyst on the heterogeneous one, at room temperature was measured and found to be significant. Measurements of mass transfer cooefficients from gas phase to liquid phasemore » for systems containing H/sub 2/, CO, methanol and methyl formate were made to verify that the reaction rate data being obtained are not influenced by mass transfer limitations. Mass transfer rates in the experimental reactor are a least 1000 times larger than reaction rates and hence are not rate limiting. Modeling of the unsteady state slurry phase Fischer-Tropsch reaction continued in order to investigate interactions among the Fischer-Tropsch reactions, the thermal effects, and the water gas shift reaction. A computer program for solution of the reaction equations was written. Also included in this report is the entire program for evaluating mass transfer coefficients under supercritical conditions is described and a review of current knowledge and planned correlational approaches is given. 61 refs., 22 figs, 7 tabs.« less

  12. The Savannah River Site's Groundwater Monitoring Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1992-01-10

    The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site's (SRS) Groundwater Monitoring Program. During second quarter 1991 EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Beginning in 1991, the flagging criteria are based on EPA drinking water standards and method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document.more » Analytical results from second quarter 1991 are listed in this report.« less

  13. Sampling results, DNAPL monitoring well GW-729, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Annual report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Drier, R.B.; Caldanaro, A.J.

    1996-12-01

    This document, Sampling Results, DNAPL Monitoring Well G W-729, Third Quarter FY 1995 through Third Quarter FY 1996, was performed under Work Breakdown Structure 1.4.12.1.1.02 (Activity Data Sheet 2312, `Bear Creek Valley`). This document provides the Environmental Restoration Program with groundwater concentrations for nonradionuclides in the vicinity of the Y-12 Burial Grounds. These data can be used to determine reference concentrations for intermediate and deep groundwater systems.

  14. Boundary Control Systems, Assessment Remedial Investigation, Version 2. 1. Volume 1

    DTIC Science & Technology

    1988-12-01

    ALLUVIAL WELLS CALCULATED TRANSMISSIVITY VALUES. AND ALLUVIAL WELLS MONITORED. . FOR WATER LEVELS FY87 A.? WELL SITING RATIONALE 10 A-3 WELL COMPLETION...29 Contour Map of Transmissivity of the Alluvial Aquifer 3rd Quarter FY 1987 B-30 Potentiometric Surface, Denver Formation Sand Zone 4 3rd Quarter FY...Monitoring 2-10 2.2-2 Chemical Analysis - Task 25 Anal-tical Program ;-14 4.1-1 Transmissivity (T), Hydraulic Conductivity (K), and 4-12 Apparent Specific

  15. Enhanced oil recovery utilizing high-angle wells in the Frontier Formation, Badger Basin Field, Park County, Wyoming. Quarterly technical progress report, 1 March 1993--30 June 1993

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Fortmann, R.G.; Walker, J.P.

    1993-07-10

    Sierra Energy Company`s targeted goals during the third quarter of this Cooperative Agreement included the following objectives from the Statement of Work: in Phase 2A, completion of subtask 2.1.2--acquire best possible field data in the 3-D seismic program; and initiation of Subtask 2.1.3--process acquired 3-D seismic data. Technical progress is described for these tasks.

  16. Energy and Environmental Insecurity (Joint Force Quarterly, Issue 55, 4th Quarter 2009)

    DTIC Science & Technology

    2009-01-01

    Energy and Environmental Insecurity By r i c h a r D B . a n D r e s Dr. Richard B. Andres is Energy and Environment Security and Policy Chair in...security, they are as likely referring to carbon emissions as to energy self -reliance and affordable oil. Moreover, the solutions that the international...2009 4. TITLE AND SUBTITLE Energy and Environmental Insecurity 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR(S) 5d

  17. The AMTEX Partnership{trademark}. First quarter report, Fiscal year 1996

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1995-12-01

    The AMTEX Partnership is a collaborative research and development program among the US Integrated Textile Industry, DOE, the National Laboratories, other federal agencies and laboratories, and universities. The goal of AMTEX is to strengthen the competitiveness of this vital industry, thereby preserving and creating US jobs. Topics in this quarters report include: computer-aided fabric evaluation, cotton biotechnology, demand activated manufacturing architecture, electronic embedded fingerprints, on-line process control in flexible fiber manufacturing, rapid cutting, sensors for agile manufacturing, and textile resource conservation.

  18. Fatal musculoskeletal injuries of Quarter Horse racehorses: 314 cases (1990-2007).

    PubMed

    Sarrafian, Tiffany L; Case, James T; Kinde, Hailu; Daft, Barbara M; Read, Deryck H; Moore, Janet D; Uzal, Francisco A; Stover, Susan M

    2012-10-01

    To determine major causes of death and the anatomic location of musculoskeletal injuries in Quarter Horse racehorses in California. Retrospective case series. 314 Quarter Horse racehorses with musculoskeletal injuries that were necropsied through the California Horse Racing Board Postmortem Program from 1990 to 2007. Postmortem pathology reports were retrospectively reviewed. Musculoskeletal injuries were categorized by anatomic region and described. The number of Quarter Horse starts and starters for the same period of time were obtained from a commercial database for determination of fatal injury incidence. Musculoskeletal injuries accounted for 314 of the 443 (71 %) Quarter Horse racehorses that died during the 18-year study period. Fatal musculoskeletal injuries occurred at a rate of 2.0 deaths/1,000 race starts and 18.6 deaths/1,000 horses that started a race. Musculoskeletal injuries occurred predominantly during racing (84%) and in the forelimbs (81%). The most common fatal musculoskeletal injuries were metacarpophalangeal and metatarsophalangeal joint (fetlock) support injuries (40%) and carpal (24%), vertebral (10%), and scapular (8%) fractures. Proximal interphalangeal (pastern) joint luxations resulted in death of 3% of horses. Fracture configurations of some bones were consistent with those of Thoroughbred racehorses. Evidence of preexisting stress remodeling of bone was reported for some fractures. Knowledge of common locations and types of fatal musculoskeletal injuries in racing Quarter Horses may enhance practitioners' ability to detect mild injuries early, rest horses, and help prevent catastrophic injuries.

  19. Nuclear Technology Series. Nuclear Reactor (Plant) Operator Trainee. A Suggested Program Planning Guide. Revised June 80.

    ERIC Educational Resources Information Center

    Center for Occupational Research and Development, Inc., Waco, TX.

    This program planning guide for a two-year postsecondary nuclear reactor (plant) operator trainee program is designed for use with courses 1-16 of thirty-five in the Nuclear Technology Series. The purpose of the guide is to describe the nuclear power field and its job categories for specialists, technicians and operators; and to assist planners,…

  20. 47 CFR 73.6001 - Eligibility and service requirements.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 47 Telecommunication 4 2011-10-01 2011-10-01 false Eligibility and service requirements. 73.6001..., 1999, operated their stations in a manner consistent with the programming and operational standards set... programming each quarter. (c) Licensed Class A television broadcast stations shall be accorded primary status...

  1. 47 CFR 73.6001 - Eligibility and service requirements.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Eligibility and service requirements. 73.6001..., 1999, operated their stations in a manner consistent with the programming and operational standards set... programming each quarter. (c) Licensed Class A television broadcast stations shall be accorded primary status...

  2. 78 FR 24150 - Submission for OMB Review; Comment Request

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-04-24

    ... Nutrition Service Title: Supplemental Nutrition Assistance Program (SNAP) Employment and Training (E & T... that States' efforts are now focused on a particular segment of the Supplemental Nutrition Assistance... quarterly reports about their E&T Programs so that the Food and Nutrition Service (FNS) can monitor their...

  3. Gifted Education Press Quarterly. Volume 10, 1996.

    ERIC Educational Resources Information Center

    Gifted Education Press Quarterly, 1996

    1996-01-01

    This set of four newsletters discusses current issues in gifted education. The first issue includes: "The Underserved Young Gifted Child: Status of Programs and Research" (Joan Smutny); "The Home Education Model: An Alternative Program for the Gifted" (Karen Kendig) and "Jonathan Swift (1667-1745): A Need for Gifted…

  4. KiloPower Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    McClure, Patrick Ray

    2016-08-04

    These are the slides for a phone interview with Aerospace America magazine of the AIAA. It goes over the KiloPower Program at Los Alamos National Laboratory (LANL), and covers the following: 1 kWe Kilopower, 10 kWe Kilopower, Kilopower Reactor Using Stirling Technology (KRUSTY) Integration Test (DAF), Reactor Configuration, and Platen Positions.

  5. Development of a three-dimensional core dynamics analysis program for commercial boiling water reactors

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bessho, Yasunori; Yokomizo, Osamu; Yoshimoto, Yuichiro

    1997-03-01

    Development and qualification results are described for a three-dimensional, time-domain core dynamics analysis program for commercial boiling water reactors (BWRs). The program allows analysis of the reactor core with a detailed mesh division, which eliminates calculational ambiguity in the nuclear-thermal-hydraulic stability analysis caused by reactor core regional division. During development, emphasis was placed on high calculational speed and large memory size as attained by the latest supercomputer technology. The program consists of six major modules, namely a core neutronics module, a fuel heat conduction/transfer module, a fuel channel thermal-hydraulic module, an upper plenum/separator module, a feedwater/recirculation flow module, and amore » control system module. Its core neutronics module is based on the modified one-group neutron kinetics equation with the prompt jump approximation and with six delayed neutron precursor groups. The module is used to analyze one fuel bundle of the reactor core with one mesh (region). The fuel heat conduction/transfer module solves the one-dimensional heat conduction equation in the radial direction with ten nodes in the fuel pin. The fuel channel thermal-hydraulic module is based on separated three-equation, two-phase flow equations with the drift flux correlation, and it analyzes one fuel bundle of the reactor core with one channel to evaluate flow redistribution between channels precisely. Thermal margin is evaluated by using the GEXL correlation, for example, in the module.« less

  6. Evaluation of an automated milk leukocyte differential test and the California Mastitis Test for detecting intramammary infection in early- and late-lactation quarters and cows.

    PubMed

    Godden, S M; Royster, E; Timmerman, J; Rapnicki, P; Green, H

    2017-08-01

    Study objectives were to (1) describe the diagnostic test characteristics of an automated milk leukocyte differential (MLD) test and the California Mastitis Test (CMT) to identify intramammary infection (IMI) in early- (EL) and late-lactation (LL) quarters and cows when using 3 different approaches to define IMI from milk culture, and (2) describe the repeatability of MLD test results at both the quarter and cow level. Eighty-six EL and 90 LL Holstein cows were sampled from 3 Midwest herds. Quarter milk samples were collected for a cow-side CMT test, milk culture, and MLD testing. Quarter IMI status was defined by 3 methods: culture of a single milk sample, culture of duplicate samples with parallel interpretation, and culture of duplicate samples with serial interpretation. The MLD testing was completed in duplicate within 8 h of sample collection; MLD results (positive/negative) were reported at each possible threshold setting (1-18 for EL; 1-12 for LL) and CMT results (positive/negative) were reported at each possible cut-points (trace, ≥1, ≥2, or 3). We created 2 × 2 tables to compare MLD and CMT results to milk culture, at both the quarter and cow level, when using each of 3 different definitions of IMI as the referent test. Paired MLD test results were compared with evaluate repeatability. The MLD test showed excellent repeatability. The choice of definition of IMI from milk culture had minor effects on estimates of MLD and CMT test characteristics. For EL samples, when interpreting MLD and CMT results at the quarter level, and regardless of the referent test used, both tests had low sensitivity (MLD = 11.7-39.1%; CMT = 0-52.2%) but good to very good specificity (MLD = 82.1-95.2%; CMT = 68.1-100%), depending on the cut-point used. Sensitivity improved slightly if diagnosis was interpreted at the cow level (MLD = 25.6-56.4%; CMT = 0-72.2%), though specificity generally declined (MLD = 61.8-100%; CMT = 25.0-100%) depending on the cut-point used. For LL samples, when interpreted at the quarter level, both tests had variable sensitivity (MLD = 46.6-84.8%; CMT = 9.6-72.7%) and variable specificity (MLD = 59.2-79.8%; CMT = 52.5-97.3%), depending on the cut-point used. Test sensitivity improved if interpreted at the cow level (MLD = 59.6-86.4%; CMT = 19.1-86.4%), though specificity declined (MLD = 32.4-56.8%; CMT = 14.3-92.3%). Producers considering adopting either test for LL or EL screening programs will need to carefully consider the goals and priorities of the program (e.g., whether to prioritize test sensitivity or specificity) when deciding on the level of interpretation (quarter or cow) and when selecting the optimal cut-point for interpreting test results. Additional validation studies and large randomized field studies will be needed to evaluate the effect of adopting either test in selective dry cow therapy or fresh cow screening programs on udder health, antibiotic use, and economics. The Authors. Published by the Federation of Animal Science Societies and Elsevier Inc. on behalf of the American Dairy Science Association®. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/3.0/).

  7. Characterization of fast neutron spectrum in the TRIGA for hardness testing of electronic components

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Nelson, George W.

    1986-07-01

    Argonne National Laboratory-West, operated by the University of Chicago, is located near Idaho Falls, ID, on the Idaho National Engineering Laboratory Site. ANL-West performs work in support of the Liquid Metal Fast Breeder Reactor Program (LMFBR) sponsored by the United States Department of Energy. The NRAD reactor is located at the Argonne Site within the Hot Fuel Examination Facility/North, a large hot cell facility where both non-destructive and destructive examinations are performed on highly irradiated reactor fuels and materials in support of the LMFBR program. The NRAD facility utilizes a 250-kW TRIGA reactor and is completely dedicated to neutron radiographymore » and the development of radiography techniques. Criticality was first achieved at the NRAD reactor in October of 1977. Since that time, a number of modifications have been implemented to improve operational efficiency and radiography production. This paper describes the modifications and changes that significantly improved operational efficiency and reliability of the reactor and the essential auxiliary reactor systems. (author)« less

  8. Success for All®. What Works Clearinghouse Intervention Report. Updated

    ERIC Educational Resources Information Center

    What Works Clearinghouse, 2017

    2017-01-01

    "Success for All" ("SFA"®) is a whole-school reform model (that is, a model that integrates curriculum, school culture, family, and community supports) for students in prekindergarten through grade 8. "SFA"® includes a literacy program, quarterly assessments of student learning, a social-emotional development program,…

  9. Middle School Advisement.

    ERIC Educational Resources Information Center

    Ball, Tricia

    Designed for those teaching an advisement program to middle school students, this book provides a year-long program with suggestions for many activities geared to middle school students. The text is divided into the traditional four-quarter school year but can be adapted to any school year configuration. The activities are designed so that the…

  10. 75 FR 18889 - Notice of Quarterly Report (October 1, 2009-December 31, 2009)

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-13

    ... 17,583,512 Control, Monitoring and Evaluation. Pending subsequent reports**..... 1,368,813 * Program... irrigation. Number of beneficial biological control agents developed for use by program farmers or other.... Percent of contracted road works disbursed-- rural roads. Signed contracts for feasibility and/or design...

  11. 76 FR 17870 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-October Through December 2010

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-31

    ... Registry (NOPR) Sites. Addendum XIII: Medicare-approved Ventricular Assist Device (Destination Therapy... Therapy) Facilities (October Through December 2010) On October 1, 2003, we issued our decision memorandum on ventricular assist devices (VADs) for the clinical indication of destination therapy. We...

  12. 78 FR 45441 - Sugar Program; Feedstock Flexibility Program for Bioenergy Producers

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-29

    ... sugarcane processors may borrow from CCC, pledging their sugar production as collateral for any such loan... sugar for bioenergy production under FFP as a proactive means for CCC to avoid forfeitures. FFP is... production. In addition, CCC will make quarterly announcements of revised estimates of such quantity. CCC's...

  13. Exploring the Potential of In-Service Training through Distance Education.

    ERIC Educational Resources Information Center

    Kelsey, Timothy W.; Mincemoyer, Claudia C.

    2001-01-01

    Survey responses from 228 Pennsylvania extension staff revealed time- or travel-related reasons inhibited inservice participation. They preferred regional locations over any other, though they were receptive to having some inservice programs delivered using distance education technologies. A pilot test of quarterly satellite inservice programs was…

  14. Dispositional Factors Affecting Motivation during Learning in Adult Basic and Secondary Education Programs

    ERIC Educational Resources Information Center

    Mellard, Daryl F.; Krieshok, Thomas; Fall, Emily; Woods, Kari

    2013-01-01

    Research indicates that about a quarter of adult students separate from formal adult basic and secondary education (ABE/ASE) programs before completing one educational level. This retrospective study explores individual dispositional factors that affect motivation during learning, particularly students' goals, goal-directed thinking and action…

  15. Financial Management: Education's Student Loan Program Controls over Lenders Need Improvement. Report to the Secretary of Education.

    ERIC Educational Resources Information Center

    General Accounting Office, Washington, DC.

    This report presents the results of a U.S. General Accounting Office (GAO) review of lender and Department of Education controls over the accuracy of lender-submitted quarterly billings under the Federal Family Education Loan Program, also known as the guaranteed student loan program. It reports that both lenders and the Department of Education…

  16. A Summative Evaluation of a Middle School Summer Math Program

    ERIC Educational Resources Information Center

    Nelson, Brian W.

    2014-01-01

    By some estimates, students lose an average of 2.6 months of learning during summer break, roughly one quarter of the time spent in school. To combat this problem, the school under study implemented a summer math program that was thematically linked to the Boston Red Sox baseball team. Hundreds of students have participated in the program, but the…

  17. Academic Year Abroad, 1994/95. The Most Complete Guide to Planning Academic Year Study Abroad.

    ERIC Educational Resources Information Center

    Steen, Sara J., Ed.

    This book describes over 2,100 academic programs (at least one academic quarter in length) sponsored by accredited U.S. postsecondary institutions or developed for U.S. students by foreign universities and other organizations. Entries are based on a 1993 survey. While most programs listed are available to undergraduates, many programs are also…

  18. KEEP Reading Research and Instruction: Results of the 1973-74 Program. Technical Report No. 26.

    ERIC Educational Resources Information Center

    Au, Kathryn H.; Speidel, Gisela E.

    This report summarizes research related to the use of a conventional basal reading program with students in the Kamehameha Early Education Program (KEEP). Results of instruction were measured by the number of objectives gained each quarter, the total number of objectives gained, the number of lessons taken for each objective, and scores on the…

  19. USAF Hearing Conservation Program, DOEHRS-HC Data Repository Annual Report: CY15

    DTIC Science & Technology

    2017-05-31

    AFRL-SA-WP-SR-2017-0014 USAF Hearing Conservation Program, DOEHRS-HC Data Repository Annual Report: CY15 Daniel A. Williams...Conservation Program, DOEHRS-HC Data Repository Annual Report: CY15 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR...Health Readiness System-Hearing Conservation Data Repository (DOEHRS-HC DR). Major command- and installation-level reports are available quarterly

  20. EPA Recovery Mapper

    EPA Pesticide Factsheets

    The EPA Recovery Mapper is an Internet interactive mapping application that allows users to discover information about every American Recovery and Reinvestment Act (ARRA) award that EPA has funded for six programs. By integrating data reported by the recipients of Recovery Act funding and data created by EPA, this application delivers a level of transparency and public accessibility to users interested in EPA's use of Recovery Act monies. The application is relatively easy to use and builds on the same mapping model as Google, Bing, MapQuest and other commonly used mapping interfaces. EPA Recovery Mapper tracks each award made by each program and gives basic Quick Facts information for each award including award name, location, award date, dollar amounts and more. Data Summaries for each EPA program or for each state are provided displaying dollars for Total Awarded, Total Received (Paid), and Total Jobs This Quarter by Recovery for the latest quarter of data released by Recovery.gov. The data are reported to the government and EPA four times a year by the award recipients. The latest quarterly report will always be displayed in the EPA Recovery Mapper. In addition, the application provides many details about each award. Users will learn more about how to access and interpret these data later in this document. Data shown in the EPA Recovery Mapper are derived from information reported back to FederalReporting.gov from the recipients of Recovery Act funding. EPA

  1. Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Smith, Cyrus M; Nanstad, Randy K; Clayton, Dwight A

    2012-09-01

    The Department of Energy s (DOE) Light Water Reactor Sustainability (LWRS) Program is a five year effort which works to develop the fundamental scientific basis to understand, predict, and measure changes in materials and systems, structure, and components as they age in environments associated with continued long-term operations of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging Non-Destructive Evaluation (NDE) methods which support these objectives. DOE funded Research and Development (R&D) on emerging NDE techniques to support commercial nuclear reactor sustainability is expected to begin nextmore » year. This summer, the MAaD Pathway invited subject matter experts to participate in a series of workshops which developed the basis for the research plan of these DOE R&D NDE activities. This document presents the results of one of these workshops which are the DOE LWRS NDE R&D Roadmap for Reactor Pressure Vessels (RPV). These workshops made a substantial effort to coordinate the DOE NDE R&D with that already underway or planned by the Electric Power Research Institute (EPRI) and the Nuclear Regulatory Commission (NRC) through their representation at these workshops.« less

  2. Nuclear Thermal Propulsion: A Joint NASA/DOE/DOD Workshop

    NASA Technical Reports Server (NTRS)

    Clark, John S. (Editor)

    1991-01-01

    Papers presented at the joint NASA/DOE/DOD workshop on nuclear thermal propulsion are compiled. The following subject areas are covered: nuclear thermal propulsion programs; Rover/NERVA and NERVA systems; Low Pressure Nuclear Thermal Rocket (LPNTR); particle bed reactor nuclear rocket; hybrid propulsion systems; wire core reactor; pellet bed reactor; foil reactor; Droplet Core Nuclear Rocket (DCNR); open cycle gas core nuclear rockets; vapor core propulsion reactors; nuclear light bulb; Nuclear rocket using Indigenous Martian Fuel (NIMF); mission analysis; propulsion and reactor technology; development plans; and safety issues.

  3. Aging management program of the reactor building concrete at Point Lepreau Generating Station

    NASA Astrophysics Data System (ADS)

    Aldea, C.-M.; Shenton, B.; Demerchant, M. M.; Gendron, T.

    2011-04-01

    In order for New Brunswick Power Nuclear (NBPN) to control the risks of degradation of the concrete reactor building at the Point Lepreau Generating Station (PLGS) the development of an aging management plan (AMP) was initiated. The intention of this plan was to determine the requirements for specific structural components of concrete of the reactor building that require regular inspection and maintenance to ensure the safe and reliable operation of the plant. The document is currently in draft form and presents an integrated methodology for the application of an AMP for the concrete of the reactor building. The current AMP addresses the reactor building structure and various components, such as joint sealant and liners that are integral to the structure. It does not include internal components housed within the structure. This paper provides background information regarding the document developed and the strategy developed to manage potential degradation of the concrete of the reactor building, as well as specific programs and preventive and corrective maintenance activities initiated.

  4. Development of New Transportation/Storage Cask System for Use by DOE Russian Research Reactor Fuel Return Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Michael Tyacke; Frantisek Svitak; Jiri Rychecky

    2010-04-01

    The United States, the Russian Federation, and the International Atomic Energy Agency (IAEA) have been working together on a program called the Russian Research Reactor Fuel Return (RRRFR) Program. The purpose of this program is to return Soviet or Russian supplied high-enriched uranium (HEU) fuel currently stored at Russian-designed research reactors throughout the world to Russia. To accommodate transport of the HEU spent nuclear fuel (SNF), a new large-capacity transport/storage cask system was specially designed for handling and operations under the unique conditions for these research reactor facilities. This new cask system is named the ŠKODA VPVR/M cask. The design,more » licensing, testing, and delivery of this new cask system are the results of a significant international cooperative effort by several countries and involved numerous private and governmental organizations. This paper contains the following sections: (1) Introduction/Background; (2) VPVR/M Cask Description; (3) Ancillary Equipment, (4) Cask Licensing; (5) Cask Demonstration and Operations; (6) IAEA Procurement, Quality Assurance Inspections, Fabrication, and Delivery; and, (7) Summary and Conclusions.« less

  5. Development of a New Transportation/Storage Cask System for Use by the DOE Russian Research Reactor Fuel Return Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Michael J. Tyacke; Frantisek Svitak; Jiri Rychecky

    2007-10-01

    The United States, the Russian Federation, and the International Atomic Energy Agency (IAEA) have been working together on a program called the Russian Research Reactor Fuel Return (RRRFR) Program. The purpose of this program is to return Soviet or Russian-supplied high-enriched uranium (HEU) fuel, currently stored at Russian-designed research reactors throughout the world, to Russia. To accommodate transport of the HEU spent nuclear fuel (SNF), a new large-capacity transport/storage cask system was specially designed for handling and operations under the unique conditions at these research reactor facilities. This new cask system is named the ŠKODA VPVR/M cask. The design, licensing,more » testing, and delivery of this new cask system result from a significant international cooperative effort by several countries and involved numerous private and governmental organizations. This paper contains the following sections: 1) Introduction; 2) VPVR/M Cask Description; 3) Ancillary Equipment, 4) Cask Licensing; 5) Cask Demonstration and Operations; 6) IAEA Procurement, Quality Assurance Inspections, Fabrication, and Delivery; and, 7) Conclusions.« less

  6. Reliability Analysis of RSG-GAS Primary Cooling System to Support Aging Management Program

    NASA Astrophysics Data System (ADS)

    Deswandri; Subekti, M.; Sunaryo, Geni Rina

    2018-02-01

    Multipurpose Research Reactor G.A. Siwabessy (RSG-GAS) which has been operating since 1987 is one of the main facilities on supporting research, development and application of nuclear energy programs in BATAN. Until now, the RSG-GAS research reactor has been successfully operated safely and securely. However, because it has been operating for nearly 30 years, the structures, systems and components (SSCs) from the reactor would have started experiencing an aging phase. The process of aging certainly causes a decrease in reliability and safe performances of the reactor, therefore the aging management program is needed to resolve the issues. One of the programs in the aging management is to evaluate the safety and reliability of the system and also screening the critical components to be managed.One method that can be used for such purposes is the Fault Tree Analysis (FTA). In this papers FTA method is used to screening the critical components in the RSG-GAS Primary Cooling System. The evaluation results showed that the primary isolation valves are the basic events which are dominant against the system failure.

  7. Improved Nuclear Reactor and Shield Mass Model for Space Applications

    NASA Technical Reports Server (NTRS)

    Robb, Kevin

    2004-01-01

    New technologies are being developed to explore the distant reaches of the solar system. Beyond Mars, solar energy is inadequate to power advanced scientific instruments. One technology that can meet the energy requirements is the space nuclear reactor. The nuclear reactor is used as a heat source for which a heat-to-electricity conversion system is needed. Examples of such conversion systems are the Brayton, Rankine, and Stirling cycles. Since launch cost is proportional to the amount of mass to lift, mass is always a concern in designing spacecraft. Estimations of system masses are an important part in determining the feasibility of a design. I worked under Michael Barrett in the Thermal Energy Conversion Branch of the Power & Electric Propulsion Division. An in-house Closed Cycle Engine Program (CCEP) is used for the design and performance analysis of closed-Brayton-cycle energy conversion systems for space applications. This program also calculates the system mass including the heat source. CCEP uses the subroutine RSMASS, which has been updated to RSMASS-D, to estimate the mass of the reactor. RSMASS was developed in 1986 at Sandia National Laboratories to quickly estimate the mass of multi-megawatt nuclear reactors for space applications. In response to an emphasis for lower power reactors, RSMASS-D was developed in 1997 and is based off of the SP-100 liquid metal cooled reactor. The subroutine calculates the mass of reactor components such as the safety systems, instrumentation and control, radiation shield, structure, reflector, and core. The major improvements in RSMASS-D are that it uses higher fidelity calculations, is easier to use, and automatically optimizes the systems mass. RSMASS-D is accurate within 15% of actual data while RSMASS is only accurate within 50%. My goal this summer was to learn FORTRAN 77 programming language and update the CCEP program with the RSMASS-D model.

  8. Comparison of Analysis Results Between 2D/1D Synthesis and RAPTOR-M3G in the Korea Standard Nuclear Plant (KSNP)

    NASA Astrophysics Data System (ADS)

    Joung Lim, Mi; Maeng, Young Jae; Fero, Arnold H.; Anderson, Stanwood L.

    2016-02-01

    The 2D/1D synthesis methodology has been used to calculate the fast neutron (E > 1.0 MeV) exposure to the beltline region of the reactor pressure vessel. This method uses the DORT 3.1 discrete ordinates code and the BUGLE-96 cross-section library based on ENDF/B-VI. RAPTOR-M3G (RApid Parallel Transport Of Radiation-Multiple 3D Geometries) which performs full 3D calculations was developed and is based on domain decomposition algorithms, where the spatial and angular domains are allocated and processed on multi-processor computer architecture. As compared to traditional single-processor applications, this approach reduces the computational load as well as the memory requirement per processor. Both methods are applied to surveillance test results for the Korea Standard Nuclear Plant (KSNP)-OPR (Optimized Power Reactor) 1000 MW. The objective of this paper is to compare the results of the KSNP surveillance program between 2D/1D synthesis and RAPTOR-M3G. Each operating KSNP has a reactor vessel surveillance program consisting of six surveillance capsules located between the core and the reactor vessel in the downcomer region near the reactor vessel wall. In addition to the In-Vessel surveillance program, an Ex-Vessel Neutron Dosimetry (EVND) program has been implemented. In order to estimate surveillance test results, cycle-specific forward transport calculations were performed by 2D/1D synthesis and by RAPTOR-M3G. The ratio between measured and calculated (M/C) reaction rates will be discussed. The current plan is to install an EVND system in all of the Korea PWRs including the new reactor type, APR (Advanced Power Reactor) 1400 MW. This work will play an important role in establishing a KSNP-specific database of surveillance test results and will employ RAPTOR-M3G for surveillance dosimetry location as well as positions in the KSNP reactor vessel.

  9. FALCON reactor-pumped laser description and program overview

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    None

    1989-12-01

    The FALCON (Fission Activated Laser CONcept) reactor-pumped laser program at Sandia National Laboratories is examining the feasibility of high-power systems pumped directly by the energy from a nuclear reactor. In this concept we use the highly energetic fission fragments from neutron induced fission to excite a large volume laser medium. This technology has the potential to scale to extremely large optical power outputs in a primarily self-powered device. A laser system of this type could also be relatively compact and capable of long run times without refueling.

  10. A complete dosimetry experimental program in support to the core characterization and to the power calibration of the CABRI reactor. A complete dosimetry experimental program in support of the core characterization and of the power calibration of the CABRI reactor

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rodiac, F.; Hudelot, JP.; Lecerf, J.

    CABRI is an experimental pulse reactor operated by CEA at the Cadarache research center. Since 1978 the experimental programs have aimed at studying the fuel behavior under Reactivity Initiated Accident (RIA) conditions. Since 2003, it has been refurbished in order to be able to provide RIA and LOCA (Loss Of Coolant Accident) experiments in prototypical PWR conditions (155 bar, 300 deg. C). This project is part of a broader scope including an overall facility refurbishment and a safety review. The global modification is conducted by the CEA project team. It is funded by IRSN, which is conducting the CIP experimentalmore » program, in the framework of the OECD/NEA project CIP. It is financed in the framework of an international collaboration. During the reactor restart, commissioning tests are realized for all equipment, systems and circuits of the reactor. In particular neutronics and power commissioning tests will be performed respectively in 2015 and 2016. This paper focuses on the design of a complete and original dosimetry program that was built in support to the CABRI core characterization and to the power calibration. Each one of the above experimental goals will be fully described, as well as the target uncertainties and the forecasted experimental techniques and data treatment. (authors)« less

  11. The Structure and Dynamics of the Solar Corona and Inner Heliosphere

    NASA Technical Reports Server (NTRS)

    Mikic, Zoran; Grebowsky, J. (Technical Monitor)

    2001-01-01

    This report covers technical progress during the third quarter of the second year of NASA Sun-Earth Connections Theory Program (SECTP) contract 'The Structure and Dynamics of the Solar Corona and Inner Heliosphere,' NAS5-99188, between NASA and Science Applications International Corporation, and covers the period February 16, 2001 to May 15, 2001. Under this contract SAIC and the University of California, Irvine (UCI) have conducted research into theoretical modeling of active regions, the solar corona, and the inner heliosphere, using the MHD model.In this report we summarize the accomplishments made by our group during the first seven quarters of our Sun-Earth Connection Theory Program contract. The descriptions are intended to illustrate our principal results. A full account can be found in the referenced publications.

  12. A Special Topic From Nuclear Reactor Dynamics for the Undergraduate Physics Curriculum

    ERIC Educational Resources Information Center

    Sevenich, R. A.

    1977-01-01

    Presents an intuitive derivation of the point reactor equations followed by formulation of equations for inverse and direct kinetics which are readily programmed on a digital computer. Suggests several computer simulations involving the effect of control rod motion on reactor power. (MLH)

  13. Status of the US RERTR Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Travelli, A.

    1995-02-01

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. The major events, findings, and activities of 1994 are reviewed after a brief summary of the results which the RERTR Program had achieved by the end of 1993 in collaboration with its many international partners. The RERTR Program has moved aggressively to support President Clinton`s nonproliferation policy and his goal {open_quotes}to minimize the use of highly-enriched uranium in civil nuclear programs{close_quotes}. An Environmental Assessment which addresses the urgent-relief acceptance of 409 spent fuel elements was completed, and the first shipment of spent fuel elements is scheduledmore » for this month. An Environmental Impact Statement addressing the acceptance of spent research reactor fuel containing enriched uranium of U.S. origin is scheduled for completion by the end of June 1995. The U.S. administration has decided to resume development of high-density LEU research reactor fuels. DOE funding and guidance are expected to begin soon. A preliminary plan for the resumption of fuel development has been prepared and is ready for implementation. The scope and main technical activities of a plan to develop and demonstrate within the next five years the technical means needed to convert Russian-supplied research reactors to LEU fuels was agreed upon by the RERTR Program and four Russian institutes lead by RDIPE. Both Secretary O`Leary and Minister Michailov have expressed strong support for this initiative. Joint studies have made significant progress, especially in assessing the technical and economic feasibility of using reduced enrichment fuels in the SAFARI-I reactor in South Africa and in the Advanced Neutron Source reactor under design at ORNL. Significant progress was achieved on several aspects of producing {sup 99}Mo from fission targets utilizing LEU instead of HEU to the achievement of the common goal.« less

  14. Nuclear Energy Enabling Technologies (NEET) Reactor Materials: News for the Reactor Materials Crosscut, May 2016

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Maloy, Stuart Andrew

    In this newsletter for Nuclear Energy Enabling Technologies (NEET) Reactor Materials, pages 1-3 cover highlights from the DOE-NE (Nuclear Energy) programs, pages 4-6 cover determining the stress-strain response of ion-irradiated metallic materials via spherical nanoindentation, and pages 7-8 cover theoretical approaches to understanding long-term materials behavior in light water reactors.

  15. Association between Traditional Nursing Home Quality Measures and Two Sources of Nursing Home Complaints

    PubMed Central

    Troyer, Jennifer L; Sause, Wendy

    2013-01-01

    Objective To test for an association between traditional nursing home quality measures and two sources of resident- and caregiver-derived nursing home complaints. Data Sources Nursing home complaints to the North Carolina Long-Term Care Ombudsman Program and state certification agency from October 2002 through September 2006 were matched with Online Survey Certification and Reporting data and Minimum Data Set Quality Indicators (MDS-QIs). Study Design We examine the association between the number of complaints filed against a facility and measures of inspection violations, staffing levels, and MDS-QIs. Data Extraction One observation per facility per quarter is constructed by matching quarterly data on complaints to OSCAR data from the same or most recent prior quarter and to MDS-QIs from the same quarter. One observation per inspection is obtained by matching OSCAR data to complaint totals from both the same and the immediate prior quarter. Principal Findings There is little relationship between MDS-QIs and complaints. Ombudsman complaints and inspection violations are generally unrelated, but there is a positive relationship between state certification agency complaints and inspection violations. Conclusions Ombudsman and state certification agency complaint data are resident- and caregiver-derived quality measures that are distinctive from and complement traditional quality measures. PMID:23216541

  16. Lawrence Livermore National Laboratory Safeguards and Security quarterly progress report to the US Department of Energy: Quarter ending December 31, 1993

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Davis, G.; Mansur, D.L.; Ruhter, W.D.

    1994-01-01

    The Lawrence Livermore National Laboratory (LLNL) carries out safeguards and security activities for the Department of Energy (DOE), Office of Safeguards and Security (OSS), as well as other organizations, both within and outside the DOE. This document summarizes the activities conducted for the OSS during the first quarter of fiscal year 1994 (October through December, 1993). The nature and scope of the activities carried out for OSS at LLNL require a broad base of technical expertise. To assure projects are staffed and executed effectively, projects are conducted by the organization at LLNL best able to supply the needed technical expertise.more » These projects are developed and managed by senior program managers. Institutional oversight and coordination is provided through the LLNL Deputy Director`s office. At present, the Laboratory is supporting OSS in five areas: (1) Safeguards Technology, (2) Safeguards and Decision Support, (3) Computer Security, (4) DOE Automated Physical Security, and (5) DOE Automated Visitor Access Control System. This report describes the activities in each of these five areas. The information provided includes an introduction which briefly describes the activity, summary of major accomplishments, task descriptions with quarterly progress, summaries of milestones and deliverables and publications published this quarter.« less

  17. Lawrence Livermore National Laboratory safeguards and security quarterly progress report to the U.S. Department of Energy. Quarter ending December 31, 1996

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Davis, G.; Mansur, D.L.; Ruhter, W.D.

    The Lawrence Livermore National Laboratory (LLNL) carries out safeguards and security activities for the Department of Energy (DOE), Office of Safeguards and Security (OSS), as well as other organizations, both within and outside the DOE. This document summarizes the activities conducted for the OSS during the First Quarter of Fiscal Year 1997 (October through December, 1996). The nature and scope of the activities carried out for OSS at LLNL require a broad base of technical expertise. To assure projects are staffed and executed effectively, projects are conducted by the organization at LLNL best able to supply the needed technical expertise.more » These projects are developed and managed by senior program managers. Institutional oversight and coordination is provided through the LLNL Deputy Director`s office. At present, the Laboratory is supporting OSS in four areas: (1) safeguards technology; (2) safeguards and material accountability; (3) computer security--distributed systems; and (4) physical and personnel security support. The remainder of this report describes the activities in each of these four areas. The information provided includes an introduction which briefly describes the activity, summary of major accomplishments, task descriptions with quarterly progress, summaries of milestones and deliverables and publications published this quarter.« less

  18. RECOMMENDATIONS FOR UO3 PLANT BIOASSAY

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Carbaugh, Eugene H.

    2010-07-12

    Alternative urine bioassay programs are described for application with decontamination and decommissioning activities at the Hanford UO3 Plant. The alternatives are based on quarterly or monthly urine bioassay for recycled uranium, assuming multiple acute inhalation intakes of recycled uranium occurring over a year. The inhalations are assumed to be 5µm AMAD particles of 80% absorption type F and 20% absorption type M. Screening levels, expressed as daily uranium mass excretion rates in urine, and the actions associated with these levels are provided for both quarterly and monthly sampling frequencies.

  19. Next Generation Transport Phenomenology Model

    NASA Technical Reports Server (NTRS)

    Strickland, Douglas J.; Knight, Harold; Evans, J. Scott

    2004-01-01

    This report describes the progress made in Quarter 3 of Contract Year 3 on the development of Aeronomy Phenomenology Modeling Tool (APMT), an open-source, component-based, client-server architecture for distributed modeling, analysis, and simulation activities focused on electron and photon transport for general atmospheres. In the past quarter, column emission rate computations were implemented in Java, preexisting Fortran programs for computing synthetic spectra were embedded into APMT through Java wrappers, and work began on a web-based user interface for setting input parameters and running the photoelectron and auroral electron transport models.

  20. 77 FR 55877 - Initial Test Program of Condensate and Feedwater Systems for Light-Water Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-11

    ...-492- 3668; email: [email protected] . NRC's Agencywide Documents Access and Management System... Systems for Light-Water Reactors AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance... Systems for Boiling Water Reactor Power Plants.'' This regulatory guide is being revised to: (1) Expand...

  1. The Neurological Basis and Potential Modification of Emotional Intelligence through Affective/Behavioral Training

    DTIC Science & Technology

    2010-10-01

    facial trustworthiness; facial displays of anger) presented subliminally . Furthermore, the responsiveness of these regions to subliminal stimulation ...develop, or program the computerized stimulation paradigms for use during functional neuroimaging (i.e., MJT; BMAT; EFAT). These paradigms will be...programming began on the computerized functional MRI stimulation paradigms using e-prime software. • Quarter #2: Programming of all computerized functional

  2. Structuring a risk-based bioassay program for uranium usage in university laboratories

    NASA Astrophysics Data System (ADS)

    Dawson, Johnne Talia

    Bioassay programs are integral in a radiation safety program. They are used as a method of determining whether individuals working with radioactive material have been exposed and have received a resulting dose. For radionuclides that are not found in nature, determining an exposure is straightforward. However, for a naturally occurring radionuclide like uranium, it is not as straightforward to determine whether a dose is the result of an occupational exposure. The purpose of this project is to address this issue within the University of Nevada, Las Vegas's (UNLV) bioassay program. This project consisted of two components that studied the effectiveness of a bioassay program in determining the dose for an acute inhalation of uranium. The first component of the plan addresses the creation of excretion curves, utilizing MATLAB that would allow UNLV to be able to determine at what time an inhalation dose can be attributed to. The excretion curves were based on the ICRP 30 lung model, as well as the Annual Limit Intake (ALI) values located in the Nuclear Regulatory Commission's 10CFR20 which is based on ICRP 30 (International Commission on Radiological Protection). The excretion curves would allow UNLV to be able to conduct in-house investigations of inhalation doses without solely depending on outside investigations and sources. The second component of the project focused on the creation of a risk based bioassay program to be utilized by UNLV that would take into account bioassay frequency that depended on the individual. Determining the risk based bioassay program required the use of baseline variance in order to minimize the investigation of false positives among those individuals who undergo bioassays for uranium work. The proposed program was compared against an evaluation limit of 10 mrem per quarter, an investigational limit of 125 mrem per quarter, and the federal/state requirement of 1.25 rem per quarter. It was determined that a bioassay program whose bioassay frequency varies per person, depending on the chemical class of material being worked with, in conjunction with continuous air monitoring can sufficiently meet ALARA standards.

  3. Resource Use and Medicare Costs During Lay Navigation for Geriatric Patients With Cancer.

    PubMed

    Rocque, Gabrielle B; Pisu, Maria; Jackson, Bradford E; Kvale, Elizabeth A; Demark-Wahnefried, Wendy; Martin, Michelle Y; Meneses, Karen; Li, Yufeng; Taylor, Richard A; Acemgil, Aras; Williams, Courtney P; Lisovicz, Nedra; Fouad, Mona; Kenzik, Kelly M; Partridge, Edward E

    2017-06-01

    Lay navigators in the Patient Care Connect Program support patients with cancer from diagnosis through survivorship to end of life. They empower patients to engage in their health care and navigate them through the increasingly complex health care system. Navigation programs can improve access to care, enhance coordination of care, and overcome barriers to timely, high-quality health care. However, few data exist regarding the financial implications of implementing a lay navigation program. To examine the influence of lay navigation on health care spending and resource use among geriatric patients with cancer within The University of Alabama at Birmingham Health System Cancer Community Network. This observational study from January 1, 2012, through December 31, 2015, used propensity score-matched regression analysis to compare quarterly changes in the mean total Medicare costs and resource use between navigated patients and nonnavigated, matched comparison patients. The setting was The University of Alabama at Birmingham Health System Cancer Community Network, which includes 2 academic and 10 community cancer centers across Alabama, Georgia, Florida, Mississippi, and Tennessee. Participants were Medicare beneficiaries with cancer who received care at participating institutions from 2012 through 2015. The primary exposure was contact with a patient navigator. Navigated patients were matched to nonnavigated patients on age, race, sex, cancer acuity (high vs low), comorbidity score, and preenrollment characteristics (costs, emergency department visits, hospitalizations, intensive care unit admissions, and chemotherapy in the preenrollment quarter). Total costs to Medicare, components of cost, and resource use (emergency department visits, hospitalizations, and intensive care unit admissions). In total, 12 428 patients (mean (SD) age at cancer diagnosis, 75 (7) years; 52.0% female) were propensity score matched, including 6214 patients in the navigated group and 6214 patients in the matched nonnavigated comparison group. Compared with the matched comparison group, the mean total costs declined by $781.29 more per quarter per navigated patient (β = -781.29, SE = 45.77, P < .001), for an estimated $19 million decline per year across the network. Inpatient and outpatient costs had the largest between-group quarterly declines, at $294 and $275, respectively, per patient. Emergency department visits, hospitalizations, and intensive care unit admissions decreased by 6.0%, 7.9%, and 10.6%, respectively, per quarter in navigated patients compared with matched comparison patients (P < .001). Costs to Medicare and health care use from 2012 through 2015 declined significantly for navigated patients compared with matched comparison patients. Lay navigation programs should be expanded as health systems transition to value-based health care.

  4. Status of JUPITER Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Inoue, T.; Shirakata, K.; Kinjo, K.

    To obtain the data necessary for evaluating the nuclear design method of a large-scale fast breeder reactor, criticality tests with a large- scale homogeneous reactor were conducted as part of a joint research program by Japan and the U.S. Analyses of the tests are underway in both countries. The purpose of this paper is to describe the status of this project.

  5. 76 FR 2346 - Quarterly Update to Annual Listing of Foreign Government Subsidies on Articles of Cheese Subject...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-13

    ... DUTY Gross \\1\\ Subsidy Net \\2\\ Subsidy Country Program(s) ($/lb) ($/lb) 27 European Union Member States \\3\\........ European Union Restitution... $0.00 $0.00 Payments Canada Export Assistance on......... 0... states of the European Union are: Austria, Belgium, Bulgaria, Cyprus, Czech Republic, Denmark, Estonia...

  6. 12 CFR Appendix A to Subpart B of... - Risk-Based Capital Stress Test

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Loan Number Ending Scheduled Balance Group Pre/Post Act Property State Product Type Origination Date... program assets post-1996 Act Swap balances; (iii) Farmer Mac I program assets pre-1996 Act; (iv) Farmer... stress test applies quarterly updates of the weighted average guarantee rates for post-1996 Farmer Mac I...

  7. 12 CFR Appendix A to Subpart B of... - Risk-Based Capital Stress Test

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Loan Number Ending Scheduled Balance Group Pre/Post Act Property State Product Type Origination Date... program assets post-1996 Act Swap balances; (iii) Farmer Mac I program assets pre-1996 Act; (iv) Farmer... stress test applies quarterly updates of the weighted average guarantee rates for post-1996 Farmer Mac I...

  8. 75 FR 14905 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-October Through December 2009

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-26

    ... stent facilities. Included in this notice is a list of the American College of Cardiology's National... 21244-1850, or you can call (410) 786-6962. Questions concerning Medicare-approved carotid stent... 20 of the CFR. Addendum VIII includes listings of Medicare-approved carotid stent facilities. All...

  9. 75 FR 58789 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-April Through June 2010

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-24

    ...- approved carotid stent facilities. Included in this notice is a list of the American College of Cardiology... 21244-1850, or you can call (410) 786-6962. Questions concerning Medicare-approved carotid stent... listings of Medicare-approved carotid stent facilities. All facilities listed meet CMS standards for...

  10. 75 FR 79173 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-July Through September 2010

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-17

    ... collections of information in CMS regulations and a list of Medicare- approved carotid stent facilities.... Questions concerning Medicare-approved carotid stent facilities in Addendum VIII may be addressed to Sarah J... 20 of the CFR. Addendum VIII includes listings of Medicare-approved carotid stent facilities. All...

  11. 40 CFR 86.1920 - What in-use testing information must I report to EPA?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... (CONTINUED) AIR PROGRAMS (CONTINUED) CONTROL OF EMISSIONS FROM NEW AND IN-USE HIGHWAY VEHICLES AND ENGINES Manufacturer-Run In-Use Testing Program for Heavy-Duty Diesel Engines § 86.1920 What in-use testing information... engine for which testing was completed during the calendar quarter. Alternatively, you may separately...

  12. 40 CFR 86.1920 - What in-use testing information must I report to EPA?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... (CONTINUED) AIR PROGRAMS (CONTINUED) CONTROL OF EMISSIONS FROM NEW AND IN-USE HIGHWAY VEHICLES AND ENGINES (CONTINUED) Manufacturer-Run In-Use Testing Program for Heavy-Duty Diesel Engines § 86.1920 What in-use... data from each engine for which testing was completed during the calendar quarter. Alternatively, you...

  13. 40 CFR 86.1920 - What in-use testing information must I report to EPA?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... (CONTINUED) AIR PROGRAMS (CONTINUED) CONTROL OF EMISSIONS FROM NEW AND IN-USE HIGHWAY VEHICLES AND ENGINES (CONTINUED) Manufacturer-Run In-Use Testing Program for Heavy-Duty Diesel Engines § 86.1920 What in-use... data from each engine for which testing was completed during the calendar quarter. Alternatively, you...

  14. 76 FR 78675 - Notice of Regulatory Waiver Requests Granted for the Third Quarter of Calendar Year 2011

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-19

    ... county to maintain capacity to administer its CDBG program until December 31, 2011. Contact: Steve... to affected local governments in a timely manner. Contact: Steve Rhodeside, Acting Director, State... administer its CDBG program until December 31, 2011. Contact: Steve Johnson, Office of Block Grant Assistance...

  15. Measuring How Benchmark Assessments Affect Student Achievement. Issues & Answers. REL 2007-No. 039

    ERIC Educational Resources Information Center

    Henderson, Susan; Petrosino, Anthony; Guckenburg, Sarah; Hamilton, Stephen

    2007-01-01

    This report examines a Massachusetts pilot program for quarterly benchmark exams in middle-school mathematics, finding that program schools do not show greater gains in student achievement after a year. But that finding might reflect limited data rather than ineffective benchmark assessments. Benchmark assessments are used in many districts…

  16. Advancing Vocational Education Through Research and Development.

    ERIC Educational Resources Information Center

    Bureau of Occupational and Adult Education (DHEW/OE), Washington, DC. Div. of Research and Demonstration.

    This report contains information about the legislative and regulatory framework for Section 131 (a) of part C of the U.S. Commissioner of Education's Vocational Education Research Programs; the planning and its procedures leading to the determination of the program priority areas for fiscal year 1976 and the transition quarter; the processes used…

  17. Infants and Toddlers, 2001-2002.

    ERIC Educational Resources Information Center

    Kroenke, Lillian DeVault, Ed.

    2002-01-01

    This document is comprised of the 2001-2002 issues of a quarterly journal for teachers and parents of children in Montessori infant and toddler programs. The spring 2001 issue presents articles on the history of infant and toddler programs in Italy and how to fulfill infant needs in Montessori child care, and on learning activities in the kitchen…

  18. Course Outline Workshop III: Paraprofessional Training.

    ERIC Educational Resources Information Center

    Burron, Arni, Comp.; Santopietro, Kathy, Comp.

    The materials in this teaching guide represent the third quarter of a community college program designed to teach paraprofessionals how to tutor in an adult literacy program. Techniques for teaching reading and English as a second language are included. Lesson plans for five classes cover the informal reading inventory, review and practice in the…

  19. NC Families and Communities Equals Success (FACES): Six Months Later.

    ERIC Educational Resources Information Center

    Fernandez, Maria E.; Campbell, Kimm; Honess, Karen; Gallagher, Natalie Gibbs; Thurber, Lori; Smitley, Andy

    This paper reports on clinical and school outcomes after 6 months of implementing the North Carolina FACES (Families and Communities Equals Success) mental health program. Of the 210 children and youth participating in the program evaluation, 42 percent were African American, more than three quarters were male, 55 percent of families had annual…

  20. Kansas State University DOE/KEURP Site Operator User Task Force. Year 3, Fourth quarterly report, April 1--June 30, 1994

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hague, J.

    This program relates to demonstration use of electric-powered vehicles. KSU has two electric cars (conversion vehicles) from Soleq. Corp., and is purchasing 4 Chevy trucks for conversion. This document discusses the participating groups, program plan, events, vehicles and components, operations, and procurement.

  1. Space nuclear safety program

    NASA Astrophysics Data System (ADS)

    George, T. G.

    1990-02-01

    This quarterly report describes studies related to the use of Pu(238)O sub 2 in radioisotope power systems, carried out of the Office of Defense Energy Programs and Special Applications of the U.S. Department of Energy by Los Alamos National Laboratory. The studies are ongoing; the results and conclusions described may change as the work progresses.

  2. 40 CFR 86.1920 - What in-use testing information must I report to EPA?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... (CONTINUED) AIR PROGRAMS (CONTINUED) CONTROL OF EMISSIONS FROM NEW AND IN-USE HIGHWAY VEHICLES AND ENGINES (CONTINUED) Manufacturer-Run In-Use Testing Program for Heavy-Duty Diesel Engines § 86.1920 What in-use... data from each engine for which testing was completed during the calendar quarter. Alternatively, you...

  3. Development of a Diabetes Education Program for Youth With Type 2 Diabetes

    PubMed Central

    Grey, Margaret; Schreiner, Barbara; Pyle, Laura

    2009-01-01

    Purpose The purpose of this article is to present the Treatment Options for Type 2 Diabetes in Adolescents and Youth (TOD2AY) study and a description of the implementation of the standard diabetes education (SDE) program. Methods A total of 218 participants (one third of the eventual sample of 750) were initially enrolled in the study. To date, the mean age of participants was 14.3 + 2.1 years, with 63% being female. Families of study participants were largely low or middle income (more than half report family income <$35 000) and about three-quarters were minority. Results More than three-quarters (79%) of families achieved full mastery of the entire SDE program. Mastery required on average 5.5 + 1.3 sessions. In addition, 62% of the families were able to achieve mastery of the session topic in a single visit. Conclusions In summary, the TOD2AY study SDE program fills the need for effective, engaging materials for youth and their families to use in mastering essential type 2 diabetes skills and knowledge. PMID:19244566

  4. Quarterly Program Progress Report April 1, 2002-June 30, 2002

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Palafox, Neal A., MD, MPH

    2002-07-31

    DOE B188 DOE/PHRI Special Medical Care Program in the Republic of the Marshall Islands (RMI)Quarterly Program Progress Report The DOE/PHRI Special Medical Care Program continues to provide, on a year round basis, a broad spectrum of medical care to the DOE patient population. During the fourth quarter of Year 4, the following medical services were provided: (1) Annual medical examinations for the DOE patient population (see Exhibit 1 for details). (2) Medications for the DOE patient population. (3) Preventive and primary medical care to the DOE patient population in the RMI as time and resources permit. (4) Additional manpower formore » the outpatient clinics at Ebeye and Majuro Hospitals (see Exhibit 2 for details). (5) Ancillary services such as labs, radiology and pharmacy in coordination with Kwajalein Hospital, Majuro Hospital and the 177 Health Care Program (177 HCP). (6) Referrals to Ebeye Hospital, Majuro Hospital and Kwajalein Hospital as necessary. (7) Referrals to Straub Clinic and Hospital in Honolulu as necessary (for details see Exhibit 1). (8) Monitored and adjusted monthly annual examination schedules based on equipment failure at Kwajalein. In addition to the above, the program was also involved in the following activities during this quarter: (1) Organized and conducted continuing medical education (CME) talks for the program's RMI staff and other RMI healthcare workers. (2) Held meetings with RMI government officials and Local Atoll government officials. (3) Input past medical records into the Electronic Medical Record (EMR) system. (4) Made adjustments to and created more templates for the EMR system. (5) Coordinated with the Public Health Departments on Majuro and Ebeye. (6) Met with PEACESAT to discuss possible collaboration on high speed Internet access. (7) Looked for opportunities to expand the program's telehealth capabilities. (8) Participated in the DOE-RMI Meeting in Honolulu. (9) Finalized the agreement with the RMI Ministry of Health and Environment (MOHE) and Majuro Hospital to hire Dr. Marie Lanwi on a part-time basis. (10) Held a Community Advisory Group (CAG) Meeting and Community Meeting on Majuro. (11) Negotiated with Kwajalein with regards to the increase in laboratory and procedure costs and continuing Mammography services for the DOE patient population. (12) Met with DOE in Honolulu to discuss the next year's program and budget. (13) Trained new residents in the use of the electronic medical record system. (14) Conducted electronic medical record audits. (15) Participated in a training session for the appointment scheduler module by Physician Micro System, Inc. on the EMR system. (16) Worked on the Year 5 Continuation Application and Budget. (17) Finalized the Memorandum of Understanding (MOU) with 177. (18) Worked with DOE and Bechtel Nevada (BN) to reduce PHRI program costs to meet an increase in referral costs paid by Bechtel. This report details the additions and changes to the program for the April 1, 2002-June 30, 2002 period.« less

  5. International Space Station USOS Crew Quarters Development

    NASA Technical Reports Server (NTRS)

    Broyan, James Lee, Jr.; Borrego, Melissa Ann; Bahr, Juergen F.

    2008-01-01

    The International Space Station (ISS) United States Operational Segment (USOS) currently provides a Temporary Sleep Station (TeSS) as crew quarters for one crewmember in the Laboratory Module. The Russian Segment provides permanent crew quarters (Kayutas) for two crewmembers in the Service Module. The TeSS provides limited electrical, communication, and ventilation functionality. A new permanent rack sized USOS ISS Crew Quarters (CQ) is being developed. Up to four CQs can be installed into the Node 2 element to increase the ISS crewmember size to six. The new CQs will provide private crewmember space with enhanced acoustic noise mitigation, integrated radiation reduction material, controllable airflow, communication equipment, redundant electrical systems, and redundant caution and warning systems. The rack sized CQ is a system with multiple crewmember restraints, adjustable lighting, controllable ventilation, and interfaces that allow each crewmember to personalize their CQ workspace. Providing an acoustically quiet and visually isolated environment, while ensuring crewmember safety, is critical for obtaining crewmember rest and comfort to enable long term crewmember performance. The numerous human factor, engineering, and program considerations during the concept, design, and prototyping are outlined in the paper.

  6. Low cost hydrogen/novel membrane technology for hydrogen separation from synthesis gas, Phase 1. Quarterly technical progress report for the period ending March 31, 1986

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1986-12-31

    The goal of this program is to develop polymer membranes useful in the preparation of hydrogen from coal-derived synthesis gas. During this quarter the first experiment were aimed at developing high performance composite membranes for the separation of hydrogen from nitrogen and carbon monoxide. Three polymers have been selected as materials for these membranes: polyetherimide cellulose acetate and ethylcellulose. This quarter the investigators worked on polyetherimide and cellulose acetate membranes. The overall structure of these membranes is shown schematically in Figure 1. As shown, a microporous support membrane is first coated with a high flux intermediate layer then with anmore » ultrathin permselective layer and finally, if necessary, a thin protective high flux layer. 1 fig., 4 tabs.« less

  7. Development and experimental qualification of a calculation scheme for the evaluation of gamma heating in experimental reactors. Application to MARIA and Jules Horowitz (JHR) MTR Reactors

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Tarchalski, M.; Pytel, K.; Wroblewska, M.

    2015-07-01

    Precise computational determination of nuclear heating which consists predominantly of gamma heating (more than 80 %) is one of the challenges in material testing reactor exploitation. Due to sophisticated construction and conditions of experimental programs planned in JHR it became essential to use most accurate and precise gamma heating model. Before the JHR starts to operate, gamma heating evaluation methods need to be developed and qualified in other experimental reactor facilities. This is done inter alia using OSIRIS, MINERVE or EOLE research reactors in France. Furthermore, MARIA - Polish material testing reactor - has been chosen to contribute to themore » qualification of gamma heating calculation schemes/tools. This reactor has some characteristics close to those of JHR (beryllium usage, fuel element geometry). To evaluate gamma heating in JHR and MARIA reactors, both simulation tools and experimental program have been developed and performed. For gamma heating simulation, new calculation scheme and gamma heating model of MARIA have been carried out using TRIPOLI4 and APOLLO2 codes. Calculation outcome has been verified by comparison to experimental measurements in MARIA reactor. To have more precise calculation results, model of MARIA in TRIPOLI4 has been made using the whole geometry of the core. This has been done for the first time in the history of MARIA reactor and was complex due to cut cone shape of all its elements. Material composition of burnt fuel elements has been implemented from APOLLO2 calculations. An experiment for nuclear heating measurements and calculation verification has been done in September 2014. This involved neutron, photon and nuclear heating measurements at selected locations in MARIA reactor using in particular Rh SPND, Ag SPND, Ionization Chamber (all three from CEA), KAROLINA calorimeter (NCBJ) and Gamma Thermometer (CEA/SCK CEN). Measurements were done in forty points using four channels. Maximal nuclear heating evaluated from measurements is of the order of 2.5 W/g at half of the possible MARIA power - 15 MW. The approach and the detailed program for experimental verification of calculations will be presented. The following points will be discussed: - Development of a gamma heating model of MARIA reactor with TRIPOLI 4 (coupled neutron-photon mode) and APOLLO2 model taking into account the key parameters like: configuration of the core, experimental loading, control rod location, reactor power, fuel depletion); - Design of specific measurement tools for MARIA experiments including for instance a new single-cell calorimeter called KAROLINA calorimeter; - MARIA experimental program description and a preliminary analysis of results; - Comparison of calculations for JHR and MARIA cores with experimental verification analysis, calculation behavior and n-γ 'environments'. (authors)« less

  8. Intern Programs

    Science.gov Websites

    , engineering and computing. Working with Fermilab scientists or engineers, interns have an opportunity to four quarters at Fermilab, alternating periods of full-time study at their schools with full-time

  9. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cappiello, M.; Hobbins, R.; Penny, K.

    As part of the Department of Energy Advanced Fuel Cycle program, a series of fuels development irradiation tests have been performed in the Advanced Test Reactor (ATR) at the Idaho National Laboratory. These tests are providing excellent data for advanced fuels development. The program is focused on the transmutation of higher actinides which best can be accomplished in a sodium-cooled fast reactor. Because a fast test reactor is no longer available in the US, a special test vehicle is used to achieve near-prototypic fast reactor conditions (neutron spectra and temperature) for use in ATR (a water-cooled thermal reactor). As partmore » of the testing program, there were many successful tests of advanced fuels including metals and ceramics. Recently however, there have been three experimental campaigns using metal fuels that experienced failure during irradiation. At the request of the program, an independent review committee was convened to review the post-test analyses performed by the fuels development team, to assess the conclusions of the team for the cause of the failures, to assess the adequacy and completeness of the analyses, to identify issues that were missed, and to make recommendations for improvements in the design and operation of future tests. Although there is some difference of opinion, the review committee largely agreed with the conclusions of the fuel development team regarding the cause of the failures. For the most part, the analyses that support the conclusions are sufficient.« less

  10. SP-100 program developments

    NASA Technical Reports Server (NTRS)

    Schnyer, A. D.; Sholtis, J. A., Jr.; Wahlquist, E. J.; Verga, R. L.; Wiley, R. L.

    1985-01-01

    An update is provided on the status of the Sp-100 Space Reactor Power Program. The historical background that led to the program is reviewed and the overall program objectives and development approach are discussed. The results of the mission studies identify applications for which space nuclear power is desirable and even essential. Results of a series of technology feasibility experiments are expected to significantly improve the earlier technology data base for engineering development. The conclusion is reached that a nuclear reactor space power system can be developed by the early 1990s to meet emerging mission performance requirements.

  11. Quality Assurance Program Plan for SFR Metallic Fuel Data Qualification

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Benoit, Timothy; Hlotke, John Daniel; Yacout, Abdellatif

    2017-07-05

    This document contains an evaluation of the applicability of the current Quality Assurance Standards from the American Society of Mechanical Engineers Standard NQA-1 (NQA-1) criteria and identifies and describes the quality assurance process(es) by which attributes of historical, analytical, and other data associated with sodium-cooled fast reactor [SFR] metallic fuel and/or related reactor fuel designs and constituency will be evaluated. This process is being instituted to facilitate validation of data to the extent that such data may be used to support future licensing efforts associated with advanced reactor designs. The initial data to be evaluated under this program were generatedmore » during the US Integral Fast Reactor program between 1984-1994, where the data includes, but is not limited to, research and development data and associated documents, test plans and associated protocols, operations and test data, technical reports, and information associated with past United States Nuclear Regulatory Commission reviews of SFR designs.« less

  12. Atmospheric Radiation Measurement program climate research facility operations quarterly report April 1 - June 30, 2007.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sisterson, D. L.

    2007-07-26

    Individual raw data streams from instrumentation at the Atmospheric Radiation Measurement (ARM) Program Climate Research Facility (ACRF) fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near real time. Raw and processed data are then sent daily to the ACRF Archive, where they are made available to users. For each instrument, we calculate the ratio of the actual number of data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual data stream, site, and monthmore » for the current year and (2) site and fiscal year (FY) dating back to 1998. The U.S. Department of Energy requires national user facilities to report time-based operating data. The requirements concern the actual hours of operation (ACTUAL); the estimated maximum operation or uptime goal (OPSMAX), which accounts for planned downtime; and the VARIANCE [1 - (ACTUAL/OPSMAX)], which accounts for unplanned downtime. The OPSMAX time for the third quarter of FY 2007 for the Southern Great Plains (SGP) site is 2,074.8 hours (0.95 x 2,184 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1,965.6 hours (0.90 x 2,184), and that for the Tropical Western Pacific (TWP) locale is 1,856.4 hours (0.85 x 2,184). The OPSMAX time for the ARM Mobile Facility (AMF) is 2,074.8 hours (0.95 x 2,184). The differences in OPSMAX performance reflect the complexity of local logistics and the frequency of extreme weather events. It is impractical to measure OPSMAX for each instrument or data stream. Data availability reported here refers to the average of the individual, continuous data streams that have been received by the Archive. Data not at the Archive are caused by downtime (scheduled or unplanned) of the individual instruments. Therefore, data availability is directly related to individual instrument uptime. Thus, the average percent of data in the Archive represents the average percent of the time (24 hours per day, 91 days for this quarter) the instruments were operating this quarter. Table 1 shows the accumulated maximum operation time (planned uptime), the actual hours of operation, and the variance (unplanned downtime) for the period April 1 through June 30, 2007, for the fixed sites only. The AMF has been deployed to Germany and is operational this quarter. The third quarter comprises a total of 2,184 hours. Although the average exceeded our goal this quarter, there were cash flow issues resulting from Continuing Resolution early in the period that did not allow for timely instrument repairs that kept our statistics lower than past quarters at all sites. The low NSA numbers resulted from missing MFRSR data this spring that appears to be recoverable but not available at the Archive at the time of this report.« less

  13. RDT quarterly : vol. 3, no. 3.

    DOT National Transportation Integrated Search

    2000-01-01

    The Missouri Transportation Bulletin is published by the Technology Transfer Assistance Program of the Missouri Department of Transportation, Jefferson City, Missouri. The opinions, findings or recommendations expressed in thisBulletin are not necess...

  14. RDT quarterly : vol. 3, no. 2.

    DOT National Transportation Integrated Search

    1999-01-01

    The Missouri Transportation Bulletin is published by the Technology Transfer Assistance Program of the Missouri Department of Transportation, : Jefferson City, Missouri. The opinions, findings or recommendations expressed in thisBulletin are not nece...

  15. Hydrogen Energy: A bibliography with abstracts

    NASA Technical Reports Server (NTRS)

    1976-01-01

    Bibliographic series cites documents relating to use of hydrogen as energy carrier. In addition to cumulative volume, annual supplement is available for 1974, and quarterly update program serves 1975 and current calendar year.

  16. Interim MELCOR Simulation of the Fukushima Daiichi Unit 2 Accident Reactor Core Isolation Cooling Operation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Ross, Kyle W.; Gauntt, Randall O.; Cardoni, Jeffrey N.

    2013-11-01

    Data, a brief description of key boundary conditions, and results of Sandia National Laboratories’ ongoing MELCOR analysis of the Fukushima Unit 2 accident are given for the reactor core isolation cooling (RCIC) system. Important assumptions and related boundary conditions in the current analysis additional to or different than what was assumed/imposed in the work of SAND2012-6173 are identified. This work is for the U.S. Department of Energy’s Nuclear Energy University Programs fiscal year 2014 Reactor Safety Technologies Research and Development Program RC-7: RCIC Performance under Severe Accident Conditions.

  17. Safe Affordable Fission Engine-(SAFE-) 100a Heat Exchanger Thermal and Structural Analysis

    NASA Technical Reports Server (NTRS)

    Steeve, B. E.

    2005-01-01

    A potential fission power system for in-space missions is a heat pipe-cooled reactor coupled to a Brayton cycle. In this system, a heat exchanger (HX) transfers the heat of the reactor core to the Brayton gas. The Safe Affordable Fission Engine- (SAFE-) 100a is a test program designed to thermally and hydraulically simulate a 95 Btu/s prototypic heat pipe-cooled reactor using electrical resistance heaters on the ground. This Technical Memorandum documents the thermal and structural assessment of the HX used in the SAFE-100a program.

  18. Highly Selective Nuclide Removal from the R-Reactor Disassembly Basin at the SRS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pickett, J. B.; Austin, W. E.; Dukes, H. H.

    This paper describes the results of a deployment of highly selective ion-exchange resin technologies for the in-situ removal of Cs-137 and Sr-90 from the Savannah River Site (SRS) R-Reactor Disassembly Basin. The deployment was supported by the DOE Office of Science and Technology's (OST, EM-50) National Engineering Technology Laboratory (NETL), as a part of an Accelerated Site Technology Deployment (ASTD) project. The Facilities Decontamination and Decommissioning (FDD) Program at the SRS conducted this deployment as a part of an overall program to deactivate three of the site's five reactor disassembly basins.

  19. Highly Selective Nuclide Removal from the R-Reactor Disassembly Basin at SRS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pickett, J.B.

    This paper describes the results of a deployment of highly selective ion-exchange resin technologies for the in-situ removal of Cs-137 and Sr-90 from the Savannah River Site (SRS) R-Reactor Disassembly Basin. The deployment was supported by the DOE Office of Science and Technology's (OST, EM-50) National Engineering Technology Laboratory (NETL), as a part of an Accelerated Site Technology Deployment (ASTD) project. The Facilities Decontamination and Decommissioning (FDD) Program at the SRS conducted this deployment as a part of an overall program to deactivate three of the site's five reactor disassembly basins

  20. Status and progress of the RERTR program in the year 2002.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Travelli, A.; Technology Development

    2003-01-01

    Following the cancellation of the 2001 International RERTR Meeting, which had been planned to occur in Bali, Indonesia, this paper describes the progress achieved by the Reduced Enrichment for Research and Test Reactors (RERTR) Program in collaboration with its many international partners during the years 2001 and 2002, and discusses the main activities planned for the year 2003. The past two years have been characterized by very important achievements of the RERTR program, but these technical achievements have been overshadowed by the terrible events of September 11, 2001. Those events have caused the U.S. Government to reevaluate the importance andmore » urgency of the RERTR program goals. A recommendation made at the highest levels of the government calls for an immediate acceleration of the program activities, with the goal of converting all the world's research reactors to low-enriched fuel at the earliest possible time, and including both Soviet-designed and United States-designed research reactors.« less

  1. Flow Induced Vibration Program at Argonne National Laboratory

    NASA Astrophysics Data System (ADS)

    1984-01-01

    The Argonne National Laboratory's Flow Induced Vibration Program, currently residing in the Laboratory's Components Technology Division is discussed. Throughout its existence, the overall objective of the program was to develop and apply new and/or improved methods of analysis and testing for the design evaluation of nuclear reactor plant components and heat exchange equipment from the standpoint of flow induced vibration. Historically, the majority of the program activities were funded by the US Atomic Energy Commission, the Energy Research and Development Administration, and the Department of Energy. Current DOE funding is from the Breeder Mechanical Component Development Division, Office of Breeder Technology Projects; Energy Conversion and Utilization Technology Program, Office of Energy Systems Research; and Division of Engineering, Mathematical and Geosciences, office of Basic Energy Sciences. Testing of Clinch River Breeder Reactor upper plenum components was funded by the Clinch River Breeder Reactor Plant Project Office. Work was also performed under contract with Foster Wheeler, General Electric, Duke Power Company, US Nuclear Regulatory Commission, and Westinghouse.

  2. Atmospheric Radiation Measurement program climate research facility operations quarterly report October 1 - December 31, 2008.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sisterson, D. L.

    2009-01-15

    Individual raw data streams from instrumentation at the Atmospheric Radiation Measurement (ARM) Program Climate Research Facility (ACRF) fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near real-time. Raw and processed data are then sent daily to the ACRF Archive, where they are made available to users. For each instrument, they calculate the ratio of the actual number of data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual data stream, site, and month formore » the current year and (2) site and fiscal year (FY) dating back to 1998. The US Department of Energy (DOE) requires national user facilities to report time-based operating data. The requirements concern the actual hours of operation (ACTUAL); the estimated maximum operation or uptime goal (OPSMAX), which accounts for planned downtime; and the VARIANCE [1-(ACTUAL/OPSMAX)], which accounts for unplanned downtime. The OPSMAX time for the first quarter of FY 2009 for the Southern Great Plains (SGP) site is 2,097.60 hours (0.95 x 2,208 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1,987.20 hours (0.90 x 2,208), and for the Tropical Western Pacific (TWP) locale is 1,876.80 hours (0.85 x 2,208). The OPSMAX time for the ARM Mobile Facility (AMF) is not reported this quarter because the data have not yet been released from China to the DMF for processing. The differences in OPSMAX performance reflect the complexity of local logistics and the frequency of extreme weather events. It is impractical to measure OPSMAX for each instrument or data stream. Data availability reported here refers to the average of the individual, continuous data streams that have been received by the Archive. Data not at the Archive are caused by downtime (scheduled or unplanned) of the individual instruments. Therefore, data availability is directly related to individual instrument uptime. Thus, the average percentage of data in the Archive represents the average percentage of the time (24 hours per day, 92 days for this quarter) the instruments were operating this quarter. Table 1 shows the accumulated maximum operation time (planned uptime), actual hours of operation, and variance (unplanned downtime) for the period October 1-December 31, 2008, for the fixed sites. The AMF has been deployed to China, but the data have not yet been released. The first quarter comprises a total of 2,208 hours. The average exceeded their goal this quarter.« less

  3. Atmospheric Radiation Measurement program climate research facility operations quarterly report January 1 - March 31, 2009.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sisterson, D. L.

    2009-04-23

    Individual raw data streams from instrumentation at the Atmospheric Radiation Measurement (ARM) Program Climate Research Facility (ACRF) fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near real-time. Raw and processed data are then sent daily to the ACRF Archive, where they are made available to users. For each instrument, we calculate the ratio of the actual number of data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual data stream, site, and month formore » the current year and (2) site and fiscal year (FY) dating back to 1998. The U.S. Department of Energy (DOE) requires national user facilities to report time-based operating data. The requirements concern the actual hours of operation (ACTUAL); the estimated maximum operation or uptime goal (OPSMAX), which accounts for planned downtime; and the VARIANCE [1 - (ACTUAL/OPSMAX)], which accounts for unplanned downtime. The OPSMAX time for the second quarter of FY 2009 for the Southern Great Plains (SGP) site is 2,052.00 hours (0.95 x 2,160 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1,944.00 hours (0.90 x 2,160), and for the Tropical Western Pacific (TWP) locale is 1,836.00 hours (0.85 x 2,160). The OPSMAX time for the ARM Mobile Facility (AMF) is not reported this quarter because not all of the metadata have been acquired that are used to generate this metric. The differences in OPSMAX performance reflect the complexity of local logistics and the frequency of extreme weather events. It is impractical to measure OPSMAX for each instrument or data stream. Data availability reported here refers to the average of the individual, continuous data streams that have been received by the Archive. Data not at the Archive are caused by downtime (scheduled or unplanned) of the individual instruments. Therefore, data availability is directly related to individual instrument uptime. Thus, the average percentage of data in the Archive represents the average percentage of the time (24 hours per day, 90 days for this quarter) the instruments were operating this quarter. Summary. Table 1 shows the accumulated maximum operation time (planned uptime), actual hours of operation, and variance (unplanned downtime) for the period January 1 - March 31, 2009, for the fixed sites. The AMF has completed its mission in China but not all of the data can be released to the public at the time of this report. The second quarter comprises a total of 2,160 hours. The average exceeded our goal this quarter.« less

  4. On use of ZPR research reactors and associated instrumentation and measurement methods for reactor physics studies

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Chauvin, J.P.; Blaise, P.; Lyoussi, A.

    2015-07-01

    The French atomic and alternative energies -CEA- is strongly involved in research and development programs concerning the use of nuclear energy as a clean and reliable source of energy and consequently is working on the present and future generation of reactors on various topics such as ageing plant management, optimization of the plutonium stockpile, waste management and innovative systems exploration. Core physics studies are an essential part of this comprehensive R and D effort. In particular, the Zero Power Reactor (ZPR) of CEA: EOLE, MINERVE and MASURCA play an important role in the validation of neutron (as well photon) physicsmore » calculation tools (codes and nuclear data). The experimental programs defined in the CEA's ZPR facilities aim at improving the calculation routes by reducing the uncertainties of the experimental databases. They also provide accurate data on innovative systems in terms of new materials (moderating and decoupling materials) and new concepts (ADS, ABWR, new MTR (e.g. JHR), GENIV) involving new fuels, absorbers and coolant materials. Conducting such interesting experimental R and D programs is based on determining and measuring main parameters of phenomena of interest to qualify calculation tools and nuclear data 'libraries'. Determining these parameters relies on the use of numerous and different experimental techniques using specific and appropriate instrumentation and detection tools. Main ZPR experimental programs at CEA, their objectives and challenges will be presented and discussed. Future development and perspectives regarding ZPR reactors and associated programs will be also presented. (authors)« less

  5. 10 CFR 72.218 - Termination of licenses.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General License for Storage of Spent Fuel at Power Reactor Sites § 72.218 Termination of licenses. (a) The notification regarding the program for the management of spent fuel at the reactor required by § 50.54(bb) of...

  6. 10 CFR 72.218 - Termination of licenses.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General License for Storage of Spent Fuel at Power Reactor Sites § 72.218 Termination of licenses. (a) The notification regarding the program for the management of spent fuel at the reactor required by § 50.54(bb) of...

  7. Early Program Development

    NASA Image and Video Library

    1963-01-01

    This artist's concept from 1963 shows a proposed NERVA (Nuclear Engine for Rocket Vehicle Application) incorporating the NRX-A1, the first NERVA-type cold flow reactor. The NERVA engine, based on Kiwi nuclear reactor technology, was intended to power a RIFT (Reactor-In-Flight-Test) nuclear stage, for which Marshall Space Flight Center had development responsibility.

  8. Zirconium Hydride Space Power Reactor design.

    NASA Technical Reports Server (NTRS)

    Asquith, J. G.; Mason, D. G.; Stamp, S.

    1972-01-01

    The Zirconium Hydride Space Power Reactor being designed and fabricated at Atomics International is intended for a wide range of potential applications. Throughout the program a series of reactor designs have been evaluated to establish the unique requirements imposed by coupling with various power conversion systems and for specific applications. Current design and development emphasis is upon a 100 kilowatt thermal reactor for application in a 5 kwe thermoelectric space power generating system, which is scheduled to be fabricated and ground tested in the mid 70s. The reactor design considerations reviewed in this paper will be discussed in the context of this 100 kwt reactor and a 300 kwt reactor previously designed for larger power demand applications.

  9. FY16 Status Report for the Uranium-Molybdenum Fuel Concept

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bennett, Wendy D.; Doherty, Ann L.; Henager, Charles H.

    2016-09-22

    The Fuel Cycle Research and Development program of the Office of Nuclear Energy has implemented a program to develop a Uranium-Molybdenum metal fuel for light water reactors. Uranium-Molybdenum fuel has the potential to provide superior performance based on its thermo-physical properties. With sufficient development, it may be able to provide the Light Water Reactor industry with a melt-resistant, accident-tolerant fuel with improved safety response. The Pacific Northwest National Laboratory has been tasked with extrusion development and performing ex-reactor corrosion testing to characterize the performance of Uranium-Molybdenum fuel in both these areas. This report documents the results of the fiscal yearmore » 2016 effort to develop the Uranium-Molybdenum metal fuel concept for light water reactors.« less

  10. Administrative and Technical Support for the U.S. Army Medical Research and Development Command Joint Working Group on Medical Chemical Defense

    DTIC Science & Technology

    1989-08-01

    microproces;qor databaAing systems for monitoring project and contract reports and program technology trans. fers, coordinating and providing administratIvo ...The JWGD 3 annual planning process generally included: - Program review by the JWGD’ membership at quarterly meetings, which consisted of the review...Office developed the program planning and budget documents associated with the planning process outlined above. Program project databases and

  11. Evaluation of Nuclear Facility Decommissioning Projects program: a reference research reactor. Project summary report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Baumann, B.L.; Miller, R.L.

    1983-10-01

    This document presents, in summary form, generic conceptual information relevant to the decommissioning of a reference research reactor (RRR). All of the data presented were extracted from NUREG/CR-1756 and arranged in a form that will provide a basis for future comparison studies for the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program.

  12. Surfactant studies for bench-scale operation

    NASA Technical Reports Server (NTRS)

    Hickey, Gregory S.; Sharma, Pramod K.

    1993-01-01

    A phase 2 study has been initiated to investigate surfactant-assisted coal liquefaction, with the objective of quantifying the enhancement in liquid yields and product quality. This report covers the second quarter of work. The major accomplishments were: completion of coal liquefaction autoclave reactor runs with Illinois number 6 coal at processing temperatures of 300, 325, and 350 C, and pressures of 1800 psig; analysis of the filter cake and the filtrate obtained from the treated slurry in each run; and correlation of the coal conversions and the liquid yield quality to the surfactant concentration. An increase in coal conversions and upgrading of the liquid product quality due to surfactant addition was observed for all runs.

  13. Programs That Make An Impact

    DOT National Transportation Integrated Search

    1996-06-17

    The Quarterly Census of Employment and Wages (QCEW) data for June 2006 was used to derive industry employment information for the impact analyses. Only non-farm, nongovernmental business establishments, with accurate location information, was used in...

  14. PQRS Mess.

    PubMed

    Sorrel, Amy Lynn

    2016-03-01

    One-quarter of physicians who participate in the Physician Quality Reporting System and the value modifier program risked payment cuts stemming from difficulties the Centers for Medicare & Medicaid Services had with collecting and analyzing 2014 quality data.

  15. 34 CFR 1100.30 - Where may the fellowship project be conducted?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... INSTITUTE FOR LITERACY NATIONAL INSTITUTE FOR LITERACY: LITERACY LEADER FELLOWSHIP PROGRAM What Conditions... is required to attend quarterly meetings at the National Institute for Literacy in Washington, D.C...

  16. 75 FR 55356 - Proposed Collection, Comment Request

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-10

    ... implementation process will begin with a pre-test beginning in the first quarter of 2011 to assess cell phone... burden, conducts a pre-clearance consultation program to provide the general public and Federal agencies...

  17. 75 FR 55612 - Proposed Collection, Comment Request

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-13

    ... implementation process will begin with a pre-test beginning in the first quarter of 2011 to assess cell phone... burden, conducts a pre-clearance consultation program to provide the general public and Federal agencies...

  18. Status of Wrought FeCrAl-UO 2 Capsules Irradiated in the Advanced Test Reactor

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Field, Kevin G.; Harp, J.; Core, G.

    2017-07-01

    Candidate cladding materials for accident tolerant fuel applications require extensive testing and validation prior to commercial deployment within the nuclear power industry. One class of cladding materials, FeCrAl alloys, is currently undergoing such effort. Within these activities is a series of irradiation programs within the Advanced Test Reactor. These programs are developed to aid in commercial maturation and understand the fundamental mechanisms controlling the cladding performance during normal operation of a typical light water reactor. Three different irradiation programs are on-going; one designed as a simple proof-of-principle concept, the other to evaluate the susceptibility of FeCrAl to fuel-cladding chemical interaction,more » and the last to fully simulate the conditions of a pressurized water reactor experimentally. To date, nondestructive post-irradiation examination has been completed on the rodlet deemed FCA-L3 from the simple proof-of-concept irradiation program. Initial results show possible breach of the rodlet under irradiation but further studies are needed to conclusively determine whether breach has occurred and the underlying reasons for such a possible failure. Further work includes characterizing additional rodlets following irradiation.« less

  19. Silicon materials task of the low cost solar array project. Phase 3: Effect of impurities and processing on silicon solar cells

    NASA Technical Reports Server (NTRS)

    Hopkins, R. H.; Davis, J. R.; Blais, P. D.; Rohatgi, A.; Campbell, R. B.; Rai-Choudhury, P.; Mollenkopf, H. C.; Mccormick, J. R.

    1979-01-01

    The 13th quarterly report of a study entitled an Investigation of the Effects of Impurities and Processing on Silicon Solar Cells is given. The objective of the program is to define the effects of impurities, various thermochemical processes and any impurity-process interactions on the performance of terrestrial silicon solar cells. The Phase 3 program effort falls in five areas: (1) cell processing studies; (2) completion of the data base and impurity-performance modeling for n-base cells; (3) extension of p-base studies to include contaminants likely to be introduced during silicon production, refining or crystal growth; (4) anisotropy effects; and (5) a preliminary study of the permanence of impurity effects in silicon solar cells. The quarterly activities for this report focus on tasks (1), (3) and (4).

  20. United States Air Force Statistical Digest, Fiscal Year 1960. Fifteenth Edition

    DTIC Science & Technology

    1960-09-30

    USAF CIVILIAN EMPLOYEES IN SALARIED AND WAGE BOARD GROUPS EMPLOYED UNDER MILITARY , ASSISTANCE PROGRAM (MAP), AT END OF QUARTER - FY � (Previous year...provide summary data on all aspects of the Mlli_ 165 tary Assistance program administered by the Air Force. The data were compiled from progress reports...Military Assistance . MAP AIRCRAFT - Aircraft in foreign countries provided by the USAF under Military Assistance Program . AIRCRAFT ATTRITION - Aircraft

  1. Simplifying ART cohort monitoring: can pharmacy stocks provide accurate estimates of patients retained on antiretroviral therapy in Malawi?

    PubMed

    Tweya, Hannock; Feldacker, Caryl; Ben-Smith, Anne; Harries, Anthony D; Komatsu, Ryuichi; Jahn, Andreas; Phiri, Sam; Tassie, Jean-Michel

    2012-07-20

    Routine monitoring of patients on antiretroviral therapy (ART) is crucial for measuring program success and accurate drug forecasting. However, compiling data from patient registers to measure retention in ART is labour-intensive. To address this challenge, we conducted a pilot study in Malawi to assess whether patient ART retention could be determined using pharmacy records as compared to estimates of retention based on standardized paper- or electronic based cohort reports. Twelve ART facilities were included in the study: six used paper-based registers and six used electronic data systems. One ART facility implemented an electronic data system in quarter three and was included as a paper-based system facility in quarter two only. Routine patient retention cohort reports, paper or electronic, were collected from facilities for both quarter two [April-June] and quarter three [July-September], 2010. Pharmacy stock data were also collected from the 12 ART facilities over the same period. Numbers of ART continuation bottles recorded on pharmacy stock cards at the beginning and end of each quarter were documented. These pharmacy data were used to calculate the total bottles dispensed to patients in each quarter with intent to estimate the number of patients retained on ART. Information for time required to determine ART retention was gathered through interviews with clinicians tasked with compiling the data. Among ART clinics with paper-based systems, three of six facilities in quarter two and four of five facilities in quarter three had similar numbers of patients retained on ART comparing cohort reports to pharmacy stock records. In ART clinics with electronic systems, five of six facilities in quarter two and five of seven facilities in quarter three had similar numbers of patients retained on ART when comparing retention numbers from electronically generated cohort reports to pharmacy stock records. Among paper-based facilities, an average of 13 4 hours was needed to calculate patient retention for cohort reporting using patient registers as compared to 2.25 hours using pharmacy stock cards. The numbers of patients retained on ART as estimated using pharmacy stock records were largely similar to estimates based on either paper registers or electronic data system. Furthermore, less time and staff effort was needed to estimate ART patient retention using pharmacy stock records versus paper-based registers. Reinforcing ARV stock management may improve the precision of estimates.

  2. International academic program in technologies of light-water nuclear reactors. Phases of development and implementation

    NASA Astrophysics Data System (ADS)

    Geraskin, N. I.; Glebov, V. B.

    2017-01-01

    The results of implementation of European educational projects CORONA and CORONA II dedicated to preserving and further developing nuclear knowledge and competencies in the area of technologies of light-water nuclear reactors are analyzed. Present article addresses issues of design and implementation of the program for specialized training in the branch of technologies of light-water nuclear reactors. The systematic approach has been used to construct the program for students of nuclear specialties, which corresponding to IAEA standards and commonly accepted nuclear principles recognized in the European Union. Possibilities of further development of the international cooperation between countries and educational institutions are analyzed. Special attention is paid to e-learning/distance training, nuclear knowledge preservation and interaction with European Nuclear Education Network.

  3. INL Experimental Program Roadmap for Thermal Hydraulic Code Validation

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Glenn McCreery; Hugh McIlroy

    2007-09-01

    Advanced computer modeling and simulation tools and protocols will be heavily relied on for a wide variety of system studies, engineering design activities, and other aspects of the Next Generation Nuclear Power (NGNP) Very High Temperature Reactor (VHTR), the DOE Global Nuclear Energy Partnership (GNEP), and light-water reactors. The goal is for all modeling and simulation tools to be demonstrated accurate and reliable through a formal Verification and Validation (V&V) process, especially where such tools are to be used to establish safety margins and support regulatory compliance, or to design a system in a manner that reduces the role ofmore » expensive mockups and prototypes. Recent literature identifies specific experimental principles that must be followed in order to insure that experimental data meet the standards required for a “benchmark” database. Even for well conducted experiments, missing experimental details, such as geometrical definition, data reduction procedures, and manufacturing tolerances have led to poor Benchmark calculations. The INL has a long and deep history of research in thermal hydraulics, especially in the 1960s through 1980s when many programs such as LOFT and Semiscle were devoted to light-water reactor safety research, the EBRII fast reactor was in operation, and a strong geothermal energy program was established. The past can serve as a partial guide for reinvigorating thermal hydraulic research at the laboratory. However, new research programs need to fully incorporate modern experimental methods such as measurement techniques using the latest instrumentation, computerized data reduction, and scaling methodology. The path forward for establishing experimental research for code model validation will require benchmark experiments conducted in suitable facilities located at the INL. This document describes thermal hydraulic facility requirements and candidate buildings and presents examples of suitable validation experiments related to VHTRs, sodium-cooled fast reactors, and light-water reactors. These experiments range from relatively low-cost benchtop experiments for investigating individual phenomena to large electrically-heated integral facilities for investigating reactor accidents and transients.« less

  4. Simulation Activity for Initiating Thinking about Year Around School Plans.

    ERIC Educational Resources Information Center

    Sagness, Richard L.

    This document presents a three-step model for providing teachers with basic information on year-round or extended school plans. As a first step, descriptions of basic plans are given. The four used in this paper are Staggered Quarter for All, Full 48-week School Year for All, Voluntary Summer Program, and A Summer Program for Professional…

  5. Linking Geography to Reading and English Language Learners' Achievement in US Elementary and Middle School Classrooms

    ERIC Educational Resources Information Center

    Hinde, Elizabeth R.; Osborn Popp, Sharon E.; Jimenez-Silva, Margarita; Dorn, Ronald I.

    2011-01-01

    The "GeoLiteracy for English language learners" (ELLs) program is a curriculum that enhances reading and writing skills while teaching geography content for US students in kindergarten through eighth grades. The program includes 85 lesson plans that address all US national geography standards, a quarter of which address environmental…

  6. A Survey of Rorschach Teaching in APA-Approved Clinical Graduate Programs

    ERIC Educational Resources Information Center

    Del Gaudio, Andrew C.; Ritzler, Barry A.

    1976-01-01

    This survey of APA-approved doctoral programs in clinical psychology provides a status assessment of the Rorschach technique. Eighty-one percent emphasized the technique; a quarter offered the course for a full year; respondents with more experience rated the technique higher; and its was rated highly as a clinical tool and teaching aid, but low…

  7. Educational Technology Program. Quarterly Technical Summary, 1 March - 31 May 1972.

    ERIC Educational Resources Information Center

    Frick, Frederick C.

    The results of the field trials of the Lincoln Training System (LTS-3) program are summarized in this report. The LTS-3 system was designed to teach basic electronics to Air Force personnel at Kessler Air Force Base, Mississippi. The results indicated that the instructional delays due to system failure were minimal, and those failures were…

  8. NASA Sun-Earth Connections Theory Program: The Structure and Dynamics of the Solar Corona and Inner Heliosphere

    NASA Technical Reports Server (NTRS)

    Mikic, Zoran; Grebowsky, Joseph (Technical Monitor)

    2001-01-01

    This report covers technical progress during the first quarter of the second year of NASA Sun-Earth Connections Theory Program (SECTP). SAIC and the University of California, Irvine (UCI) have conducted research into theoretical modeling of active regions, the solar corona, and the inner heliosphere, using the MHD model.

  9. Leading Contributors to the Research Consortium's Annual Program, 1992-2011: High-Visibility Institutions, Researchers, and Topics

    ERIC Educational Resources Information Center

    Cardinal, Bradley J.; Lee, Hyo

    2013-01-01

    Between 1992-2011, peer-reviewed research on the Research Consortium's annual program has been published in abstract form in the "Research Quarterly for Exercise and Sport". On the basis of frequency, high-visibility institutions, researchers, and sub-disciplinary categories were identified. Data were extracted from each abstract (N =…

  10. 78 FR 17995 - Agency Information Collection Activity Under OMB Review

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-03-25

    ... collections: 49 U.S.C. Section 5337--State of Good Repair Program 49 U.S.C. Section 5339--Bus and Bus... on a quarterly basis. The information submitted ensures FTA's compliance with applicable federal laws. Title: 49 U.S.C. Section 5339--Bus and Bus Facilities Program. Abstract: 49 U.S.C. 5339--Bus and Bus...

  11. Adult Continuing Education and Human Resource Development: Present Competitors, Potential Partners

    ERIC Educational Resources Information Center

    Smith, Douglas H.

    2006-01-01

    Adult Continuing Education (ACE) and Human Resource Development (HRD) have grown tremendously in the last quarter century. ACE experienced tremendous growth in the 60s and 70s, with over 17 million attending colleges and universities, and local school and community adult education programs by the end of the 1970s. More ACE programs were started…

  12. Government Information Quarterly. Volume 7, no. 2: National Aeronautics and Space Administration Scientific and Technical Information Programs. Special issue

    NASA Technical Reports Server (NTRS)

    Hernon, Peter (Editor); Mcclure, Charles R. (Editor); Pinelli, Thomas E. (Editor)

    1990-01-01

    NASA scientific and technical information (STI) programs are discussed. Topics include management of information in a research and development agency, the new space and Earth science information systems at NASA's archive, scientific and technical information management, and technology transfer of NASA aerospace technology to other industries.

  13. Returning HEU Fuel from the Czech Republic to Russia

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Michael Tyacke; Dr. Igor Bolshinsky

    In December 1999, representatives from the United States, Russian Federation, and International Atomic Energy Agency began working on a program to return Russian supplied, highly enriched, uranium fuel stored at foreign research reactors to Russia. Now, under the Global Threat Reduction Initiative’s Russian Research Reactor Fuel Return Program, this effort has repatriated over 800 kg of highly enriched uranium to Russia from over 10 countries. In May 2004, the “Agreement Between the Government of the United States of America and the Government of the Russian Federation Concerning Cooperation for the Transfer of Russian Produced Research Reactor Nuclear Fuel to themore » Russian Federation” was signed. This agreement provides legal authority for the Russian Research Reactor Fuel Return Program and establishes parameters whereby eligible countries may return highly enriched uranium spent and fresh fuel assemblies and other fissile materials to Russia. On December 8, 2007, one of the largest shipments of highly enriched uranium spent nuclear fuel was successfully made from a Russian-designed nuclear research reactor in the Czech Republic to the Russian Federation. This accomplishment is the culmination of years of planning, negotiations, and hard work. The United States, Russian Federation, and the International Atomic Energy Agency have been working together. In February 2003, Russian Research Reactor Fuel Return Program representatives met with the Nuclear Research Institute in Rež, Czech Republic, and discussed the return of their highly enriched uranium spent nuclear fuel to the Russian Federation for reprocessing. Nearly 5 years later, the shipment was made. This article discusses the planning, preparations, coordination, and cooperation required to make this important international shipment.« less

  14. Status and progress of the RERTR program in the year 2003.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Travelli, A.; Nuclear Engineering Division

    2003-01-01

    One of the most important events affecting the RERTR program during the past year was the decision by the U.S. Department of Energy to request the U.S. Congress to significantly increase RERTR program funding. This decision was prompted, at least in part, by the terrible events of September 11, 2001, and by a high-level U.S./Russian Joint Expert Group recommendation to immediately accelerate RERTR program activities in both countries, with the goal of converting all the world's research reactors to low-enriched fuel at the earliest possible time, and including both Soviet-designed and United States-designed research reactors. The U.S. Congress is expectedmore » to approve this request very soon, and the RERTR program has prepared itself well for the intense activities that the 'Accelerated RERTR Program' will require. Promising results have been obtained in the development of a fabrication process for monolithic LEU U-Mo fuel. Most existing and future research reactors could be converted to LEU with this fuel, which has a uranium density between 15.4 and 16.4 g/cm{sup 3} and yielded promising irradiation results in 2002. The most promising method hinges on producing the monolithic meat by cold-rolling a thin ingot produced by casting. The aluminum clad and the meat are bonded by friction stir welding and the cladding surface is finished by a light cold roll. This method can be applied to the production of miniplates and appears to be extendable to the production of full-size plates, possibly with intermediate anneals. Other methods planned for investigation include high temperature bonding and hot isostatic pressing. The progress achieved within the Russian RERTR program, both for the traditional tube-type elements and for the new 'universal' LEU U-Mo pin-type elements, promises to enable soon the conversion of many Russian-designed research and test reactors. Irradiation testing of both fuel types with LEU U-Mo dispersion fuels has begun. Detailed studies are in progress to define the feasibility of converting each Russian-designed research and test reactor to either fuel type. The plan for the Accelerated RERTR Program is structured to achieve LEU conversion of all HEU research reactors supplied by the United States and Russia during the next nine years. This effort will address, in addition to the fuel development and qualification, the analyses and performance/economic/safety evaluations needed to implement the conversions. In combination with this over-arching goal, the RERTR program plans to achieve at the earliest possible date qualification of LEU U-Mo dispersion fuels with uranium densities of 6 g/cm{sup 3} and 7 g/cm{sup 3}. Reactors currently using or planning to use LEU silicide fuel will rely on this fuel after termination of the FRRSNFA program, because it is acceptable to COGEMA for reprocessing. Qualification of LEU U-Mo dispersion fuels has suffered some unavoidable delays but, to accelerate it as much as possible, the RERTR program, the French CEA, and the Australian ANSTO have agreed to jointly pursue a two-element qualification test of LEU U-Mo dispersion fuel with uranium density of 7.0 g/cm{sup 3} to be performed in the Osiris reactor during 2004. The RERTR program also intends to eliminate all obstacles to the utilization of LEU in targets for isotope production, so that this important function can be performed without the need for weapons-grade materials. All of us, working together as we have for many years, can ensure that all these goals will be achieved. By promoting the efficiency and safety of research reactors while eliminating the traffic in weapons-grade uranium, we can prevent the possibility that some of this material might fall in the wrong hands. Few causes can be more deserving of our joint efforts.« less

  15. Exploratory development of a glass ceramic automobile thermal reactor. [anti-pollution devices

    NASA Technical Reports Server (NTRS)

    Gould, R. E.; Petticrew, R. W.

    1973-01-01

    This report summarizes the design, fabrication and test results obtained for glass-ceramic (CER-VIT) automotive thermal reactors. Several reactor designs were evaluated using both engine-dynamometer and vehicle road tests. A maximum reactor life of about 330 hours was achieved in engine-dynamometer tests with peak gas temperatures of about 1065 C (1950 F). Reactor failures were mechanically induced. No evidence of chemical degradation was observed. It was concluded that to be useful for longer times, the CER-VIT parts would require a mounting system that was an improvement over those tested in this program. A reactor employing such a system was designed and fabricated.

  16. Delivering digital health and well-being at scale: lessons learned during the implementation of the dallas program in the United Kingdom.

    PubMed

    Devlin, Alison M; McGee-Lennon, Marilyn; O'Donnell, Catherine A; Bouamrane, Matt-Mouley; Agbakoba, Ruth; O'Connor, Siobhan; Grieve, Eleanor; Finch, Tracy; Wyke, Sally; Watson, Nicholas; Browne, Susan; Mair, Frances S

    2016-01-01

    To identify implementation lessons from the United Kingdom Delivering Assisted Living Lifestyles at Scale (dallas) program-a large-scale, national technology program that aims to deliver a broad range of digital services and products to the public to promote health and well-being. Prospective, longitudinal qualitative research study investigating implementation processes. Qualitative data collected includes semi-structured e-Health Implementation Toolkit-led interviews at baseline/mid-point (n = 38), quarterly evaluation, quarterly technical and barrier and solutions reports, observational logs, quarterly evaluation alignment interviews with project leads, observational data collected during meetings, and ethnographic data from dallas events (n > 200 distinct pieces of qualitative data). Data analysis was guided by Normalization Process Theory, a sociological theory that aids conceptualization of implementation issues in complex healthcare settings. Five key challenges were identified: 1) The challenge of establishing and maintaining large heterogeneous, multi-agency partnerships to deliver new models of healthcare; 2) The need for resilience in the face of barriers and set-backs including the backdrop of continually changing external environments; 3) The inherent tension between embracing innovative co-design and achieving delivery at pace and at scale; 4) The effects of branding and marketing issues in consumer healthcare settings; and 5) The challenge of interoperability and information governance, when commercial proprietary models are dominant. The magnitude and ambition of the dallas program provides a unique opportunity to investigate the macro level implementation challenges faced when designing and delivering digital health and wellness services at scale. Flexibility, adaptability, and resilience are key implementation facilitators when shifting to new digitally enabled models of care. © The Author 2015. Published by Oxford University Press on behalf of the American Medical Informatics Association.

  17. Seven Q-Tracks monitors of laboratory quality drive general performance improvement: experience from the College of American Pathologists Q-Tracks program 1999-2011.

    PubMed

    Meier, Frederick A; Souers, Rhona J; Howanitz, Peter J; Tworek, Joseph A; Perrotta, Peter L; Nakhleh, Raouf E; Karcher, Donald S; Bashleben, Christine; Darcy, Teresa P; Schifman, Ron B; Jones, Bruce A

    2015-06-01

    Many production systems employ standardized statistical monitors that measure defect rates and cycle times, as indices of performance quality. Clinical laboratory testing, a system that produces test results, is amenable to such monitoring. To demonstrate patterns in clinical laboratory testing defect rates and cycle time using 7 College of American Pathologists Q-Tracks program monitors. Subscribers measured monthly rates of outpatient order-entry errors, identification band defects, and specimen rejections; median troponin order-to-report cycle times and rates of STAT test receipt-to-report turnaround time outliers; and critical values reporting event defects, and corrected reports. From these submissions Q-Tracks program staff produced quarterly and annual reports. These charted each subscriber's performance relative to other participating laboratories and aggregate and subgroup performance over time, dividing participants into best and median performers and performers with the most room to improve. Each monitor's patterns of change present percentile distributions of subscribers' performance in relation to monitoring durations and numbers of participating subscribers. Changes over time in defect frequencies and the cycle duration quantify effects on performance of monitor participation. All monitors showed significant decreases in defect rates as the 7 monitors ran variously for 6, 6, 7, 11, 12, 13, and 13 years. The most striking decreases occurred among performers who initially had the most room to improve and among subscribers who participated the longest. All 7 monitors registered significant improvement. Participation effects improved between 0.85% and 5.1% per quarter of participation. Using statistical quality measures, collecting data monthly, and receiving reports quarterly and yearly, subscribers to a comparative monitoring program documented significant decreases in defect rates and shortening of a cycle time for 6 to 13 years in all 7 ongoing clinical laboratory quality monitors.

  18. Request for Naval Reactors Comment on Proposed Prometheus Space Flight Nuclear Reactor High Tier Reactor Safety Requirements and for Naval Reactors Approval to Transmit These Requirements to JPL

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    D. Kokkinos

    2005-04-28

    The purpose of this letter is to request Naval Reactors comments on the nuclear reactor high tier requirements for the PROMETHEUS space flight reactor design, pre-launch operations, launch, ascent, operation, and disposal, and to request Naval Reactors approval to transmit these requirements to Jet Propulsion Laboratory to ensure consistency between the reactor safety requirements and the spacecraft safety requirements. The proposed PROMETHEUS nuclear reactor high tier safety requirements are consistent with the long standing safety culture of the Naval Reactors Program and its commitment to protecting the health and safety of the public and the environment. In addition, the philosophymore » on which these requirements are based is consistent with the Nuclear Safety Policy Working Group recommendations on space nuclear propulsion safety (Reference 1), DOE Nuclear Safety Criteria and Specifications for Space Nuclear Reactors (Reference 2), the Nuclear Space Power Safety and Facility Guidelines Study of the Applied Physics Laboratory.« less

  19. Quarterly report of RCRA groundwater monitoring data for period January 1, 1993 through March 31, 1993

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1993-07-01

    Hanford Site interim-status groundwater monitoring projects are conducted as either background, indicator parameter evaluation, or groundwater quality assessment monitoring programs as defined in the Resource Conservation and Recovery Act of 1976 (RCRA); and Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities, as amended (40 Code of Federal Regulations [CFR] 265). Compliance with the 40 CFR 265 regulations is required by the Washington Administrative Code (WAC) 173-303. This report contains data from Hanford Site groundwater monitoring projects. This quarterly report contains data received between March 8 and May 24, 1993, which are the cutoffmore » dates for this reporting period. This report may contain not only data from the January through March quarter but also data from earlier sampling events that were not previously reported.« less

  20. Researcher Poses with a Nuclear Rocket Model

    NASA Image and Video Library

    1961-11-21

    A researcher at the NASA Lewis Research Center with slide ruler poses with models of the earth and a nuclear-propelled rocket. The Nuclear Engine for Rocket Vehicle Applications (NERVA) was a joint NASA and Atomic Energy Commission (AEC) endeavor to develop a nuclear-powered rocket for both long-range missions to Mars and as a possible upper-stage for the Apollo Program. The early portion of the program consisted of basic reactor and fuel system research. This was followed by a series of Kiwi reactors built to test nuclear rocket principles in a non-flying nuclear engine. The next phase, NERVA, would create an entire flyable engine. The AEC was responsible for designing the nuclear reactor and overall engine. NASA Lewis was responsible for developing the liquid-hydrogen fuel system. The nuclear rocket model in this photograph includes a reactor at the far right with a hydrogen propellant tank and large radiator below. The payload or crew would be at the far left, distanced from the reactor.

  1. 7 CFR 1486.500 - What are the reporting requirements of the program?

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... the project, both electronically (preferably in PDF format) and in hard copy. (3) Reporting requirements and formats for both quarterly progress reports and final performance reports are specified in the...

  2. Saturn Apollo Program

    NASA Image and Video Library

    1964-02-01

    Temporary quarters in the Huntsville Industrial Center (HIC) building located in downtown Huntsville, Alabama, as Marshall Space Flight Center (MSFC) grew. This image shows drafting specialists from the Propulsion and Vehicle Engineering Laboratory at work in the HIC building.

  3. HEDL FACILITIES CATALOG 400 AREA

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    MAYANCSIK BA

    1987-03-01

    The purpose of this project is to provide a sodium-cooled fast flux test reactor designed specifically for irradiation testing of fuels and materials and for long-term testing and evaluation of plant components and systems for the Liquid Metal Reactor (LMR) Program. The FFTF includes the reactor, heat removal equipment and structures, containment, core component handling and examination, instrumentation and control, and utilities and other essential services. The complex array of buildings and equipment are arranged around the Reactor Containment Building.

  4. N.S. SAVANNAH, DRAFT OF FINAL SAFEGUARDS REPORT TEST, START-UP AND TRIALS, NEW YORK SHIPBUILDING CORPORATION

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    None

    1960-04-01

    The N. S. Savannah program for testing, start-up, and initial operation of all reactor and propulsion components and systems is discussed. Definitions of test phases are given and various stages of the test program are outlined. A list of tests for the various reactor, propulsion, and other system components is included. (C.J.G.)

  5. IEA-R1 Nuclear Research Reactor: 58 Years of Operating Experience and Utilization for Research, Teaching and Radioisotopes Production

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cardenas, Jose Patricio Nahuel; Filho, Tufic Madi; Saxena, Rajendra

    IEA-R1 research reactor at the Instituto de Pesquisas Energeticas e Nucleares (Nuclear and Energy Research Institute) IPEN, Sao Paulo, Brazil is the largest power research reactor in Brazil, with a maximum power rating of 5 MWth. It is being used for basic and applied research in the nuclear and neutron related sciences, for the production of radioisotopes for medical and industrial applications, and for providing services of neutron activation analysis, real time neutron radiography, and neutron transmutation doping of silicon. IEA-R1 is a swimming pool reactor, with light water as the coolant and moderator, and graphite and beryllium as reflectors.more » The reactor was commissioned on September 16, 1957 and achieved its first criticality. It is currently operating at 4.5 MWth with a 60-hour cycle per week. In the early sixties, IPEN produced {sup 131}I, {sup 32}P, {sup 198}Au, {sup 24}Na, {sup 35}S, {sup 51}Cr and labeled compounds for medical use. During the past several years, a concerted effort has been made in order to upgrade the reactor power to 5 MWth through refurbishment and modernization programs. One of the reasons for this decision was to produce {sup 99}Mo at IPEN. The reactor cycle will be gradually increased to 120 hours per week continuous operation. It is anticipated that these programs will assure the safe and sustainable operation of the IEA-R1 reactor for several more years, to produce important primary radioisotopes {sup 99}Mo, {sup 125}I, {sup 131}I, {sup 153}Sm and {sup 192}Ir. Currently, all aspects of dealing with fuel element fabrication, fuel transportation, isotope processing, and spent fuel storage are handled by IPEN at the site. The reactor modernization program is slated for completion by 2015. This paper describes 58 years of operating experience and utilization of the IEA-R1 research reactor for research, teaching and radioisotopes production. (authors)« less

  6. Testing piezoelectric sensors in a nuclear reactor environment

    NASA Astrophysics Data System (ADS)

    Reinhardt, Brian T.; Suprock, Andy; Tittmann, Bernhard

    2017-02-01

    Several Department of Energy Office of Nuclear Energy (DOE-NE) programs, such as the Fuel Cycle Research and Development (FCRD), Advanced Reactor Concepts (ARC), Light Water Reactor Sustainability, and Next Generation Nuclear Power Plants (NGNP), are investigating new fuels, materials, and inspection paradigms for advanced and existing reactors. A key objective of such programs is to understand the performance of these fuels and materials during irradiation. In DOE-NE's FCRD program, ultrasonic based technology was identified as a key approach that should be pursued to obtain the high-fidelity, high-accuracy data required to characterize the behavior and performance of new candidate fuels and structural materials during irradiation testing. The radiation, high temperatures, and pressure can limit the available tools and characterization methods. In this work piezoelectric transducers capable of making these measurements are developed. Specifically, three piezoelectric sensors (Bismuth Titanate, Aluminum Nitride, and Zinc Oxide) are tested in the Massachusetts Institute of Technology Research reactor to a fast neutron fluence of 8.65×1020 nf/cm2. It is demonstrated that Bismuth Titanate is capable of transduction up to 5 × 1020 nf/cm2, Zinc Oxide is capable of transduction up to at least 6.27 × 1020 nf/cm2, and Aluminum Nitride is capable of transduction up to at least 8.65 × 1020 nf/cm2.

  7. Strengthening the fission reactor nuclear science and engineering program at UCLA. Final technical report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Okrent, D.

    1997-06-23

    This is the final report on DOE Award No. DE-FG03-92ER75838 A000, a three year matching grant program with Pacific Gas and Electric Company (PG and E) to support strengthening of the fission reactor nuclear science and engineering program at UCLA. The program began on September 30, 1992. The program has enabled UCLA to use its strong existing background to train students in technological problems which simultaneously are of interest to the industry and of specific interest to PG and E. The program included undergraduate scholarships, graduate traineeships and distinguished lecturers. Four topics were selected for research the first year, withmore » the benefit of active collaboration with personnel from PG and E. These topics remained the same during the second year of this program. During the third year, two topics ended with the departure o the students involved (reflux cooling in a PWR during a shutdown and erosion/corrosion of carbon steel piping). Two new topics (long-term risk and fuel relocation within the reactor vessel) were added; hence, the topics during the third year award were the following: reflux condensation and the effect of non-condensable gases; erosion/corrosion of carbon steel piping; use of artificial intelligence in severe accident diagnosis for PWRs (diagnosis of plant status during a PWR station blackout scenario); the influence on risk of organization and management quality; considerations of long term risk from the disposal of hazardous wastes; and a probabilistic treatment of fuel motion and fuel relocation within the reactor vessel during a severe core damage accident.« less

  8. Collecting costs of community prevention programs: communities putting prevention to work initiative.

    PubMed

    Khavjou, Olga A; Honeycutt, Amanda A; Hoerger, Thomas J; Trogdon, Justin G; Cash, Amanda J

    2014-08-01

    Community-based programs require substantial investments of resources; however, evaluations of these programs usually lack analyses of program costs. Costs of community-based programs reported in previous literature are limited and have been estimated retrospectively. To describe a prospective cost data collection approach developed for the Communities Putting Prevention to Work (CPPW) program capturing costs for community-based tobacco use and obesity prevention strategies. A web-based cost data collection instrument was developed using an activity-based costing approach. Respondents reported quarterly expenditures on labor; consultants; materials, travel, and services; overhead; partner efforts; and in-kind contributions. Costs were allocated across CPPW objectives and strategies organized around five categories: media, access, point of decision/promotion, price, and social support and services. The instrument was developed in 2010, quarterly data collections took place in 2011-2013, and preliminary analysis was conducted in 2013. Preliminary descriptive statistics are presented for the cost data collected from 51 respondents. More than 50% of program costs were for partner organizations, and over 20% of costs were for labor hours. Tobacco communities devoted the majority of their efforts to media strategies. Obesity communities spent more than half of their resources on access strategies. Collecting accurate cost information on health promotion and disease prevention programs presents many challenges. The approach presented in this paper is one of the first efforts successfully collecting these types of data and can be replicated for collecting costs from other programs. Copyright © 2014 American Journal of Preventive Medicine. All rights reserved.

  9. Technology development for cobalt F-T catalysts. Quarterly technical progress report number 10, January 1--March 31, 1995

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Singleton, A.H.

    1995-06-28

    The goal of this project is the development of a commercially-viable, cobalt-based Fischer-Tropsch (F-T) catalyst for use in a slurry bubble column reactor. The major objectives of this work are (1) to develop a cobalt-based F-T catalyst with low (< 5%) methane selectivity, (2) to develop a cobalt-based F-T catalyst with water-gas shift activity, and (3) to combine both these improvements into one catalyst. The project consists of five major tasks: catalyst development; catalyst testing; catalyst reproducibility tests; catalyst aging tests; and preliminary design and cost estimate for a demonstrate scale catalyst production facility. Technical accomplishments during this reporting periodmore » include the following. It appears that the higher activity obtained for the catalysts prepared using an organic solution and reduced directly without prior calcination was the result of higher dispersions obtained under such pretreatment. A Ru-promoted Co catalyst on alumina with 30% Co loading exhibited a 4-fold increase in dispersion and a 2-fold increase in activity in the fixed-bed reactor from that obtained with the non-promoted catalyst. Several reactor runs have again focused on pushing conversion to higher levels. The maximum conversion obtained has been 49.7% with 26g catalyst. Further investigations of the effect of reaction temperature on the performance of Co catalysts during F-T synthesis were started using a low activity catalyst and one of the most active catalysts. The three 1 kg catalyst batches prepared by Calsicat for the reproducibility and aging studies were tested in both the fixed-bed and slurry bubble column reactors under the standard reaction conditions. The effects of adding various promoters to some cobalt catalysts have also been addressed. Results are presented and discussed.« less

  10. United States Air Force Statistical Digest, Fiscal Year 1965, Twentieth Edition

    DTIC Science & Technology

    1965-09-30

    prOVided by the USAF under Military Assistance Program . MAP EMPLOYEES - Category of civilian personnel engaged in activities reqUired in carrying out the...92 - USAF CIVIUAN EMPLOYEES IN SALARIED AND WAGE BOARD GROUPS EMPLOYED UNDER MILITARY ASSISTANCE PROGRAM (MAP), WORLO-WIDE, AT END OF QUARTER - FY...statistical material for tary Assistance Program (MAP), and re- the digest. AFCHO will furnish a chronology lated studies and historical events. of

  11. Commercial-scale demonstration of the Liquid Phase Methanol (LPMEOH{trademark}) process. Technical progress report number 11, January 1--March 31, 1997

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1997-06-11

    During this quarter, the third draft of the Topical Report on Process Economics Studies was issued for review. A recommendation to continue with design verification testing on the coproduction of methanol and dimethyl ether (DME) was made. A liquid phase dimethyl ether (LPDME) catalyst system with reasonable long-term activity and stability is being developed, and a decision to proceed with a proof-of-concept test run at the LaPorte Alternative Fuels Development Unit (AFDU) is pending the release of a memo from Air Products on the catalyst targets and corresponding economics for a commercially successful LPDME catalyst. The off-site product-use test planmore » is to be updated in June of 1997. During this quarter, Air Products and Acurex Environmental Corporation continued developing the listing of product-use test participants who are involved in fuel cell, transportation, and stationary power plant applications. Start-up activities (Task 3.1) began during the reporting period, and coal-derived synthesis gas (syngas) was introduced to the demonstration unit. The recycle compressor was tested successfully on syngas at line pressure of 700 psig, and the reactor loop reached 220 C for carbonyl burnout. Iron carbonyl in the balanced gas feed remained below the 10 ppbv detection limit for all samples but one. Within the reactor loop, iron carbonyl levels peaked out near 200 ppbv after about 40 hours on-stream, before decreasing to between 10--20 ppbv at 160 hours on -stream. Nickel carbonyl measurements reached a peak of about 60 ppbv, and decreased at all sampling locations to below the 10 ppbv detection limit by 70 hours on-stream. Catalyst activation of the nine 2,250 lb batches required for the initial catalyst charge began and concluded. All batches met or slightly exceeded the theoretical maximum uptake of 2.82 SCF of reducing gas/lb catalyst.« less

  12. Exploratory study of several advanced nuclear-MHD power plant systems.

    NASA Technical Reports Server (NTRS)

    Williams, J. R.; Clement, J. D.; Rosa, R. J.; Yang, Y. Y.

    1973-01-01

    In order for efficient multimegawatt closed cycle nuclear-MHD systems to become practical, long-life gas cooled reactors with exit temperatures of about 2500 K or higher must be developed. Four types of nuclear reactors which have the potential of achieving this goal are the NERVA-type solid core reactor, the colloid core (rotating fluidized bed) reactor, the 'light bulb' gas core reactor, and the 'coaxial flow' gas core reactor. Research programs aimed at developing these reactors have progressed rapidly in recent years so that prototype power reactors could be operating by 1980. Three types of power plant systems which use these reactors have been analyzed to determine the operating characteristics, critical parameters and performance of these power plants. Overall thermal efficiencies as high as 80% are projected, using an MHD turbine-compressor cycle with steam bottoming, and slightly lower efficiencies are projected for an MHD motor-compressor cycle.

  13. Design and manufacture of a D-shape coil-based toroid-type HTS DC reactor using 2nd generation HTS wire

    NASA Astrophysics Data System (ADS)

    Kim, Kwangmin; Go, Byeong-Soo; Sung, Hae-Jin; Park, Hea-chul; Kim, Seokho; Lee, Sangjin; Jin, Yoon-Su; Oh, Yunsang; Park, Minwon; Yu, In-Keun

    2014-09-01

    This paper describes the design specifications and performance of a real toroid-type high temperature superconducting (HTS) DC reactor. The HTS DC reactor was designed using 2G HTS wires. The HTS coils of the toroid-type DC reactor magnet were made in the form of a D-shape. The target inductance of the HTS DC reactor was 400 mH. The expected operating temperature was under 20 K. The electromagnetic performance of the toroid-type HTS DC reactor magnet was analyzed using the finite element method program. A conduction cooling method was adopted for reactor magnet cooling. Performances of the toroid-type HTS DC reactor were analyzed through experiments conducted under the steady-state and charge conditions. The fundamental design specifications and the data obtained from this research will be applied to the design of a commercial-type HTS DC reactor.

  14. Atmospheric Radiation Measurement Program Climate Research Facility Operations Quarterly Report July 1 – September 30, 2008

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sisterson, DL

    2008-09-30

    Individual raw data streams from instrumentation at the Atmospheric Radiation Measurement (ARM) Program Climate Research Facility (ACRF) fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near real-time. Raw and processed data are then sent daily to the ACRF Archive, where they are made available to users. For each instrument, we calculate the ratio of the actual number of data records received daily at the Archive to the expected number of data records. The results are tabulated by (1) individual data stream, site, and month formore » the current year and (2) site and fiscal year (FY) dating back to 1998. The U.S. Department of Energy (DOE) requires national user facilities to report time-based operating data. The requirements concern the actual hours of operation (ACTUAL); the estimated maximum operation or uptime goal (OPSMAX), which accounts for planned downtime; and the VARIANCE [1 – (ACTUAL/OPSMAX)], which accounts for unplanned downtime. The OPSMAX time for the fourth quarter of FY 2008 for the Southern Great Plains (SGP) site is 2,097.60 hours (0.95 x 2,208 hours this quarter). The OPSMAX for the North Slope Alaska (NSA) locale is 1,987.20 hours (0.90 x 2,208), and for the Tropical Western Pacific (TWP) locale is 1,876.80 hours (0.85 x 2,208). The OPSMAX time for the ARM Mobile Facility (AMF) is not reported this quarter because the data have not yet been released from China to the DMF for processing. The differences in OPSMAX performance reflect the complexity of local logistics and the frequency of extreme weather events. It is impractical to measure OPSMAX for each instrument or data stream. Data availability reported here refers to the average of the individual, continuous data streams that have been received by the Archive. Data not at the Archive are caused by downtime (scheduled or unplanned) of the individual instruments. Therefore, data availability is directly related to individual instrument uptime. Thus, the average percentage of data in the Archive represents the average percentage of the time (24 hours per day, 92 days for this quarter) the instruments were operating this quarter.« less

  15. Oil reserve: status of Strategic Petroleum Reserve activities as of December 31, 1985

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    This report discusses events and activities related to the administration's progress in filling, developing, and operating the Strategic Petroleum Reserve (SPR) during the first quarter of fiscal year 1986. Specifically, it notes that: DOE added 4.5 million barrels of oil to the SPR, bringing the total to 493.3 million barrels. The oil fill rate averaged about 49,000 barrels per day during the quarter. DOE made payments of $178 million for oil acquisition and transportation, had unpaid obligations of about $140 million, and had about $668 million in unobligated funds. The storage capacity development program proceeded during the quarter; however, themore » West Hackberry, Louisiana site's leaching program was stopped in December due to a leak in the brine disposal line. DOE held an SPR drawdown test sale and distribution exercise. Approximately 1 million barrels of oil were competitively sold to oil company bidders and subsequently withdrawn from DOE storage sites for delivery. The Congress passed a continuing resolution for fiscal year 1986 providing about $113 million for continued construction of storage capacity as directed by the fiscal year 1985 Supplemental Appropriations Act. On December 27, 1985, DOE formally notified cognizant congressional committees that it was planning to submit a deferral of funds for SPR storage facilities development. This report also presents information on (1) the implementation of recommendations made in the DOE Oak Ridge Operations Office's reports on its baseline assessment of the SPR Project Office and its review of allegations about mismanagement or misconduct within the SPR program, (2) DOE's compliance with the Cargo Preference Act of 1954 during the 1985 crude oil procurement program, (3) DOE's program to analyze the quality of oil in filled storage caverns, and (4) DOE's pipeline construction and marine terminal enhancements to improve the SPR oil distribution system.« less

  16. Models of MOS and SOS devices

    NASA Technical Reports Server (NTRS)

    Gassaway, J. D.; Mahmood, Q.; Trotter, J. D.

    1980-01-01

    Quarterly report describes progress in three programs: dc sputtering machine for aluminum and aluminum alloys; two dimensional computer modeling of MOS transistors; and development of computer techniques for calculating redistribution diffusion of dopants in silicon on sapphire films.

  17. 77 FR 31641 - Comment Request for Information Collection for Employment and Training Administration Financial...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-29

    ... requested data can be provided in the desired format, reporting burden (time and financial resources) is... comments concerning the collection of data for quarterly financial reporting on federally funded programs...

  18. ODOT research news : fall quarter 2001.

    DOT National Transportation Integrated Search

    2001-01-01

    The ODOT Research News including: 1) Research Management Peer Exchange. Six research experts from other agencies, other states, and FHWA interviewed ODOT staff and our research partners to collect their views of the program. 2) Automated Data Collect...

  19. Who purchases nonprescription syringes? Characterizing customers of the Expanded Syringe Access Program (ESAP).

    PubMed

    Battles, Haven B; Rowe, Kirsten A; Ortega-Peluso, Christina; Klein, Susan J; Tesoriero, James M

    2009-11-01

    This study represents the first attempt in the USA to survey pharmacy nonprescription syringe customers at their point of purchase. We surveyed 62 individuals purchasing nonprescription syringes in seven pharmacies located in NYC and Albany, NY, USA. Three quarters of respondents purchased for illicit use, and 36% purchased for medical use, with differences found by race and gender. Half got their syringes from pharmacies "most of the time." Half had ever been refused a syringe purchase in a NYS pharmacy, with men, Blacks, and Hispanics reporting higher levels of refusals than women or whites. Two thirds reported syringe reuse but very few reported sharing. While approximately one quarter safely obtained and disposed of syringes "most of the time," two thirds used both safe and unsafe methods. Pharmacy-based syringe access programs are essential in areas not served by syringe exchanges.

  20. Inertial Confinement Fusion Quarterly Report: April--June 1993. Volume 3, Number 3

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    MacGowan, B.J.; Kotowski, M.; Schleich, D.

    1993-11-01

    This issue of the ICF Quarterly contains six articles describing recent advances in Lawrence Livermore National Laboratory`s inertial confinement fusion (ICF) program. The current emphasis of the ICF program is in support of DOE`s National Ignition Facility (NIF) initiative for demonstrating ignition and gain with a 1-2 MJ glass laser. The articles describe recent Nova experiments and investigations tailored towards enhancing understanding of the key physics and technological issues for the NIF. Titles of the articles are: development of large-aperture KDP crystals; inner-shell photo-ionized X-ray lasers; X-ray radiographic measurements of radiation-driven shock and interface motion in solid density materials; themore » role of nodule defects in laser-induced damage of multilayer optical coatings; techniques for Mbar to near-Gbar equation-of-state measurements with the Nova laser; parametric instabilities and laser-beam smoothing.« less

  1. Nuclear Engine System Simulation (NESS). Volume 1: Program user's guide

    NASA Astrophysics Data System (ADS)

    Pelaccio, Dennis G.; Scheil, Christine M.; Petrosky, Lyman J.

    1993-03-01

    A Nuclear Thermal Propulsion (NTP) engine system design analysis tool is required to support current and future Space Exploration Initiative (SEI) propulsion and vehicle design studies. Currently available NTP engine design models are those developed during the NERVA program in the 1960's and early 1970's and are highly unique to that design or are modifications of current liquid propulsion system design models. To date, NTP engine-based liquid design models lack integrated design of key NTP engine design features in the areas of reactor, shielding, multi-propellant capability, and multi-redundant pump feed fuel systems. Additionally, since the SEI effort is in the initial development stage, a robust, verified NTP analysis design tool could be of great use to the community. This effort developed an NTP engine system design analysis program (tool), known as the Nuclear Engine System Simulation (NESS) program, to support ongoing and future engine system and stage design study efforts. In this effort, Science Applications International Corporation's (SAIC) NTP version of the Expanded Liquid Engine Simulation (ELES) program was modified extensively to include Westinghouse Electric Corporation's near-term solid-core reactor design model. The ELES program has extensive capability to conduct preliminary system design analysis of liquid rocket systems and vehicles. The program is modular in nature and is versatile in terms of modeling state-of-the-art component and system options as discussed. The Westinghouse reactor design model, which was integrated in the NESS program, is based on the near-term solid-core ENABLER NTP reactor design concept. This program is now capable of accurately modeling (characterizing) a complete near-term solid-core NTP engine system in great detail, for a number of design options, in an efficient manner. The following discussion summarizes the overall analysis methodology, key assumptions, and capabilities associated with the NESS presents an example problem, and compares the results to related NTP engine system designs. Initial installation instructions and program disks are in Volume 2 of the NESS Program User's Guide.

  2. Nuclear Engine System Simulation (NESS). Volume 1: Program user's guide

    NASA Technical Reports Server (NTRS)

    Pelaccio, Dennis G.; Scheil, Christine M.; Petrosky, Lyman J.

    1993-01-01

    A Nuclear Thermal Propulsion (NTP) engine system design analysis tool is required to support current and future Space Exploration Initiative (SEI) propulsion and vehicle design studies. Currently available NTP engine design models are those developed during the NERVA program in the 1960's and early 1970's and are highly unique to that design or are modifications of current liquid propulsion system design models. To date, NTP engine-based liquid design models lack integrated design of key NTP engine design features in the areas of reactor, shielding, multi-propellant capability, and multi-redundant pump feed fuel systems. Additionally, since the SEI effort is in the initial development stage, a robust, verified NTP analysis design tool could be of great use to the community. This effort developed an NTP engine system design analysis program (tool), known as the Nuclear Engine System Simulation (NESS) program, to support ongoing and future engine system and stage design study efforts. In this effort, Science Applications International Corporation's (SAIC) NTP version of the Expanded Liquid Engine Simulation (ELES) program was modified extensively to include Westinghouse Electric Corporation's near-term solid-core reactor design model. The ELES program has extensive capability to conduct preliminary system design analysis of liquid rocket systems and vehicles. The program is modular in nature and is versatile in terms of modeling state-of-the-art component and system options as discussed. The Westinghouse reactor design model, which was integrated in the NESS program, is based on the near-term solid-core ENABLER NTP reactor design concept. This program is now capable of accurately modeling (characterizing) a complete near-term solid-core NTP engine system in great detail, for a number of design options, in an efficient manner. The following discussion summarizes the overall analysis methodology, key assumptions, and capabilities associated with the NESS presents an example problem, and compares the results to related NTP engine system designs. Initial installation instructions and program disks are in Volume 2 of the NESS Program User's Guide.

  3. 76 FR 78267 - Medicare and Medicaid Programs; Quarterly Listing of Program Issuances-July Through September 2011

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-16

    ... provisions of the Social Security Act (the Act) and Public Health Service Act. We also issue various manuals..., there is a 3-month lapse between the information available on the Web site and information covered by... notice that provided only Web links to the addenda, or provide this information on a newly- created CMS...

  4. Training Peer Sexual Health Educators: Changes in Knowledge, Counseling Self-Efficacy, and Sexual Risk Behavior

    ERIC Educational Resources Information Center

    Ehrhardt, Britt L.; Krumboltz, John D.; Koopman, Cheryl

    2007-01-01

    Peer sexual health education programs are widespread on college campuses, but little research has assessed the effect of these programs on the peer educators. This study employed a repeated measures design to examine changes over the academic quarter in the knowledge, counseling self-efficacy, and sexual behavior of 70 college students enrolled in…

  5. Investigation of a Leadership Development Program.

    DTIC Science & Technology

    1998-08-04

    by leadership training. A quantitative approach was taken, using Sashkin’s Visionary Leadership Theory (VLT) to study the effects of a certificated... Theory , research, and managerial application. New York: Free Press. Bass, B. M. (1996). A new paradigm of leadership : An inquiry into...factor theory of leadership . Administrative Science Quarterly, 11, 238-263. Investigation of a Leadership Development Program Boyd, J. T., Jr. (1988

  6. Demographic Trends in Social Work over a Quarter-Century in an Increasingly Female Profession

    ERIC Educational Resources Information Center

    Schilling, Robert; Morrish, Jennifer Naranjo; Liu, Gan

    2008-01-01

    This article depicts the changing demographic portrait of social work education in the United States from 1974 through 2000 and considers the demographic shifts in the profession of social work. During this period, BSW and joint MSW-BSW programs increased from 150 to 404, MSW programs increased from 79 to 139, and social work doctoral programs…

  7. Communication Sciences Laboratory Quarterly Progress Report, Volume 9, Number 3: Research Programs of Some of the Newer Members of CSL.

    ERIC Educational Resources Information Center

    Feinstein, Stephen H.; And Others

    The research reported in these papers covers a variety of communication problems. The first paper covers research on sound navigation by the blind and involves echo perception research and relevant aspects of underwater sound localization. The second paper describes a research program in acoustic phonetics and concerns such related issues as…

  8. Educational Technology Program. Quarterly Technical Summary, Period Ending 31 May 1970.

    ERIC Educational Resources Information Center

    Frick, Frederick C.

    An overview of the Lincoln Training System (LTS) and descriptions of the hardward and software of the LTS-1 and LTS-2 systems are provided. The overall program seeks to develop, test, and evaluate technical aids to vocational training systems. These are appropriate to this field because the high costs need to be reduced and because there are clear…

  9. Feasibility of a Catch-Up HPV Vaccination Program among College Students Attending a Large Rural University in the South

    ERIC Educational Resources Information Center

    Richman, Alice R.; Haithcox-Dennis, Melissa J.; Allsbrook, Ashley R.

    2012-01-01

    Our study explored the eligibility and willingness of students to participate in a university-wide catch-up Human papillomavirus (HPV) vaccination program. A total of 1804 electronic surveys (82% response) assessing demographics, HPV knowledge, eligibility, and willingness were gathered. HPV knowledge was moderate, with just over a quarter (26%)…

  10. The Journal of Staff, Program, & Organization Development, Volume 14, Numbers 1-4, 1996-97. New Forums Faculty Development Series.

    ERIC Educational Resources Information Center

    Neal, Edward, Ed.

    1997-01-01

    This quarterly publication serves as a medium for the exchange of ideas regarding the planning, design, implementation, and evaluation of professional development practices at two- and four-year colleges. The four issues in volume 14 feature the following articles: (1) "A Home-Grown Faculty Development Program," (Jane T. Rauton); (2) "Creating…

  11. Making Improvements to The Army Distributed Learning Program

    DTIC Science & Technology

    2012-01-01

    Learning (pre/post comparisons). e Army could develop an IT platform to administer course pretests and posttests . Automatic scoring/reporting... groups with proponent schools, DL contractors, and TRADOC head- quarters sta; reviews of Army processes for developing courseware; and an analysis...Lessons ORD Operational Requirements Document PB President’s Budget PCO Procuring Contract Oce PEG Program Evaluation Group PEO EIS U.S. Army

  12. Reactor Statics Module, RS-9: Multigroup Diffusion Program Using an Exponential Acceleration Technique.

    ERIC Educational Resources Information Center

    Macek, Victor C.

    The nine Reactor Statics Modules are designed to introduce students to the use of numerical methods and digital computers for calculation of neutron flux distributions in space and energy which are needed to calculate criticality, power distribution, and fuel burnup for both slow neutron and fast neutron fission reactors. The last module, RS-9,…

  13. Hanford Laboratories monthly activities report, March 1964

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1964-04-15

    The monthly report for the Hanford Laboratories Operation, March 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics operation, and programming operations are discussed.

  14. CERCA LEU fuel assemblies testing in Maria Reactor - safety analysis summary and testing program scope.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pytel, K.; Mieleszczenko, W.; Lechniak, J.

    2010-03-01

    The presented paper contains neutronic and thermal-hydraulic (for steady and unsteady states) calculation results prepared to support annex to Safety Analysis Report for MARIA reactor in order to obtain approval for program of testing low-enriched uranium (LEU) lead test fuel assemblies (LTFA) manufactured by CERCA. This includes presentation of the limits and operational constraints to be in effect during the fuel testing investigations. Also, the scope of testing program (which began in August 2009), including additional measurements and monitoring procedures, is described.

  15. Effects of Levels of Automation for Advanced Small Modular Reactors: Impacts on Performance, Workload, and Situation Awareness

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Johanna Oxstrand; Katya Le Blanc

    The Human-Automation Collaboration (HAC) research effort is a part of the Department of Energy (DOE) sponsored Advanced Small Modular Reactor (AdvSMR) program conducted at Idaho National Laboratory (INL). The DOE AdvSMR program focuses on plant design and management, reduction of capital costs as well as plant operations and maintenance costs (O&M), and factory production costs benefits.

  16. Long-term outcomes of an antimicrobial stewardship program implemented in a hospital with low baseline antibiotic use.

    PubMed

    Jenkins, Timothy C; Knepper, Bryan C; Shihadeh, Katherine; Haas, Michelle K; Sabel, Allison L; Steele, Andrew W; Wilson, Michael L; Price, Connie S; Burman, William J; Mehler, Philip S

    2015-06-01

    To evaluate the long-term outcomes of an antimicrobial stewardship program (ASP) implemented in a hospital with low baseline antibiotic use. Quasi-experimental, interrupted time-series study. Public safety net hospital with 525 beds. Implementation of a formal ASP in July 2008. We conducted a time-series analysis to evaluate the impact of the ASP over a 6.25-year period (July 1, 2008-September 30, 2014) while controlling for trends during a 3-year preintervention period (July 1, 2005-June 30, 2008). The primary outcome measures were total antibacterial and antipseudomonal use in days of therapy (DOT) per 1,000 patient-days (PD). Secondary outcomes included antimicrobial costs and resistance, hospital-onset Clostridium difficile infection, and other patient-centered measures. During the preintervention period, total antibacterial and antipseudomonal use were declining (-9.2 and -5.5 DOT/1,000 PD per quarter, respectively). During the stewardship period, both continued to decline, although at lower rates (-3.7 and -2.2 DOT/1,000 PD, respectively), resulting in a slope change of 5.5 DOT/1,000 PD per quarter for total antibacterial use (P=.10) and 3.3 DOT/1,000 PD per quarter for antipseudomonal use (P=.01). Antibiotic expenditures declined markedly during the stewardship period (-$295.42/1,000 PD per quarter, P=.002). There were variable changes in antimicrobial resistance and few apparent changes in C. difficile infection and other patient-centered outcomes. In a hospital with low baseline antibiotic use, implementation of an ASP was associated with sustained reductions in total antibacterial and antipseudomonal use and declining antibiotic expenditures. Common ASP outcome measures have limitations.

  17. Long-Term Outcomes of an Antimicrobial Stewardship Program Implemented in a Hospital with Low Baseline Antibiotic Use

    PubMed Central

    Jenkins, Timothy C.; Knepper, Bryan C.; Shihadeh, Katherine; Haas, Michelle K.; Sabel, Allison L.; Steele, Andrew W.; Wilson, Michael L.; Price, Connie S.; Burman, William J.; Mehler, Philip S.

    2016-01-01

    Objective To evaluate the long-term outcomes of an antimicrobial stewardship program (ASP) implemented in a hospital with low baseline antibiotic use Design Quasi-experimental, interrupted-time series study Setting 525-bed public safety-net hospital Intervention Implementation of a formal ASP in July 2008 Methods We conducted a time-series analysis to evaluate the impact of the ASP over a 6.25-year period (July 1, 2008 – September 30, 2014) while controlling for trends during a 3-year preintervention period (July 1, 2005 – June 30, 2008). The primary outcome measures were total antibacterial and antipseudomonal use in days of therapy (DOT) per 1000 patient-days (PD). Secondary outcomes included antimicrobial costs and resistance, hospital-onset C. difficile infection, and other patient-centered measures. Results During the preintervention period, total antibacterial and antipseudomonal use were declining (−9.2 and −5.5 DOT/1000 PD per quarter, respectively). During the stewardship period, both continued to decline, although at lower rates (−3.7 and −2.2 DOT/1000 PD, respectively), resulting in a slope change of 5.5 DOT/1000 PD per quarter for total antibacterial use (P = .10) and 3.3 DOT/100 PD per quarter for antipseudomonal use (P = .01). Antibiotic expenditures declined markedly during the stewardship period (−$295.42/1000PD per quarter, p=.002). There were variable changes in antimicrobial resistance and few apparent changes in C. difficile infection and other patient-centered outcomes. Conclusion In a hospital with low baseline antibiotic use, implementation of an ASP was associated with sustained reductions in total antibacterial and antipseudomonal use and declining antibiotic expenditures; however, this study highlights limitations of commonly used stewardship outcome measures. PMID:25740560

  18. Method for depleting BWRs using optimal control rod patterns

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Taner, M.S.; Levine, S.H.; Hsiao, M.Y.

    1991-01-01

    Control rod (CR) programming is an essential core management activity for boiling water reactors (BWRs). After establishing a core reload design for a BWR, CR programming is performed to develop a sequence of exposure-dependent CR patterns that assure the safe and effective depletion of the core through a reactor cycle. A time-variant target power distribution approach has been assumed in this study. The authors have developed OCTOPUS to implement a new two-step method for designing semioptimal CR programs for BWRs. The optimization procedure of OCTOPUS is based on the method of approximation programming and uses the SIMULATE-E code for nucleonicsmore » calculations.« less

  19. Atmospheric Radiation Measurement program climate research facilities quarterly report April 1 - June 30, 2009.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sisterson, D. L.

    2009-07-14

    Individual raw data streams from instrumentation at the Atmospheric Radiation Measurement (ARM) Program Climate Research Facility (ACRF) fixed and mobile sites are collected and sent to the Data Management Facility (DMF) at Pacific Northwest National Laboratory (PNNL) for processing in near-real time. Raw and processed data are then sent approximately daily to the ACRF Archive, where they are made available to users. For each instrument, we calculate the ratio of the actual number of data records received daily at the archive to the expected number of data records. The results are tabulated by (1) individual data stream, site, and monthmore » for the current year and (2) site and fiscal year (FY) dating back to 1998. The U.S. Department of Energy (DOE) requires national user facilities to report time-based operating data. The requirements concern the actual hours of operation (ACTUAL); the estimated maximum operation or uptime goal (OPSMAX), which accounts for planned downtime; and the VARIANCE [1 - (ACTUAL/OPSMAX)], which accounts for unplanned downtime. The OPSMAX time for the third quarter of FY 2009 for the Southern Great Plains (SGP) site is 2,074.80 hours (0.95 x 2,184 hours this quarter); for the North Slope Alaska (NSA) locale it is 1,965.60 hours (0.90 x 2,184); and for the Tropical Western Pacific (TWP) locale it is 1,856.40 hours (0.85 x 2,184). The ARM Mobile Facility (AMF) was officially operational May 1 in Graciosa Island, the Azores, Portugal, so the OPSMAX time this quarter is 1390.80 hours (0.95 x 1464). The differences in OPSMAX performance reflect the complexity of local logistics and the frequency of extreme weather events. It is impractical to measure OPSMAX for each instrument or data stream. Data availability reported here refers to the average of the individual, continuous data streams that have been received by the Archive. Data not at the Archive are caused by downtime (scheduled or unplanned) of the individual instruments. Therefore, data availability is directly related to individual instrument uptime. Thus, the average percentage of data in the Archive represents the average percentage of the time (24 hours per day, 91 days for this quarter) the instruments were operating this quarter. Table 1 shows the accumulated maximum operation time (planned uptime), actual hours of operation, and variance (unplanned downtime) for April 1 - June 30, 2009, for the fixed sites. Because the AMF operates episodically, the AMF statistics are reported separately and are not included in the aggregate average with the fixed sites. The AMF statistics for this reporting period were not available at the time of this report. The third quarter comprises a total of 2,184 hours for the fixed sites. The average well exceeded our goal this quarter.« less

  20. Hanford Laboratories monthly activities report, February 1964

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1964-03-16

    This is the monthly report for the Hanford Laboratories Operation, February, 1964. Reactor fuels, chemistry, dosimetry, separation process, reactor technology financial activities, biology operation, physics and instrumentation research, employee relations, applied mathematics, programming, and radiation protection are discussed.

  1. 10 CFR 140.5 - Communications.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ...: ATTN: Document Control Desk, Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Federal and State Materials and Environmental Management Programs, or..., Rockville, Maryland; or, where practicable, by electronic submission, for example, via Electronic...

  2. 10 CFR 140.5 - Communications.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ...: ATTN: Document Control Desk, Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Federal and State Materials and Environmental Management Programs, or..., Rockville, Maryland; or, where practicable, by electronic submission, for example, via Electronic...

  3. Biaxial Creep Specimen Fabrication

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    JL Bump; RF Luther

    This report documents the results of the weld development and abbreviated weld qualification efforts performed by Pacific Northwest National Laboratory (PNNL) for refractory metal and superalloy biaxial creep specimens. Biaxial creep specimens were to be assembled, electron beam welded, laser-seal welded, and pressurized at PNNL for both in-pile (JOYO reactor, O-arai, Japan) and out-of-pile creep testing. The objective of this test campaign was to evaluate the creep behavior of primary cladding and structural alloys under consideration for the Prometheus space reactor. PNNL successfully developed electron beam weld parameters for six of these materials prior to the termination of the Navalmore » Reactors program effort to deliver a space reactor for Project Prometheus. These materials were FS-85, ASTAR-811C, T-111, Alloy 617, Haynes 230, and Nirnonic PE16. Early termination of the NR space program precluded the development of laser welding parameters for post-pressurization seal weldments.« less

  4. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Davis, R. S.

    The following are specific topics of this paper: 1.There is much creativity in the manner in which Dimensional Generator can be applied to a specific programming task [2]. This paper tells how Dimensional Generator was applied to a reactor-physics task. 2. In this first practical use, Dimensional Generator itself proved not to need change, but a better user interface was found necessary, essentially because the relevance of Dimensional Generator to reactor physics was initially underestimated. It is briefly described. 3. The use of Dimensional Generator helps make reactor-physics source code somewhat simpler. That is explained here with brief examples frommore » BURFEL-PC and WIMSBURF. 4. Most importantly, with the help of Dimensional Generator, all erroneous physical expressions were automatically detected. The errors are detailed here (in spite of the author's embarrassment) because they show clearly, both in theory and in practice, how Dimensional Generator offers quality enhancement of reactor-physics programming. (authors)« less

  5. Final summary report for 1989 inservice inspection (ISI) of SRS (Savannah River Site) 100-P Reactor tank

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Morrison, J.M.; Loibl, M.W.

    1989-12-15

    The integrity of the SRS reactor tanks is a key factor affecting their suitability for continued service since, unlike the external piping system and components, the tanks are virtually irreplaceable. Cracking in various areas of the process water piping systems has occurred beginning in 1960 as a result of several degradation mechanisms, chiefly intergranular stress corrosion cracking (IGSCC) and chloride-induced transgranular cracking. IGSCC, currently the primary degradation mechanism, also occurred in the knuckle'' region (tank wall-to-bottom tube sheet transition piece) unique to C Reactor and was eventually responsible for that reactor being deactivated in 1985. A program of visual examinationsmore » of the SRS reactor tanks was initiated in 1968, which used a specially designed immersible periscope. Under that program the condition of the accessible tank welds and associated heat affected zones (HAZ) was evaluated on a five-year frequency. Prior to 1986, the scope of these inspections comprised approximately 20 percent of the accessible weld area. In late 1986 and early 1987 the scope of the inspections was expanded and a 100 percent visual inspection of accessible welds was performed of the P-, L-, and K-Reactor tanks. Supplemental dye penetrant examinations were performed in L Reactor on selected areas which showed visual indications. No evidence of cracking was detected in any of these inspections of the P-, L-, and K-Reactor tanks. 17 refs., 7 figs.« less

  6. Analysis of JKT01 Neutron Flux Detector Measurements In RSG-GAS Reactor Using LabVIEW

    NASA Astrophysics Data System (ADS)

    Rokhmadi; Nur Rachman, Agus; Sujarwono; Taryo, Taswanda; Sunaryo, Geni Rina

    2018-02-01

    The RSG-GAS Reactor, one of the Indonesia research reactors and located in Serpong, is owned by the National Nuclear Energy Agency (BATAN). The RSG-GAS reactor has operated since 1987 and some instrumentation and control systems are considered to be degraded and ageing. It is therefore, necessary to evaluate the safety of all instrumentation and controls and one of the component systems to be evaluated is the performance of JKT01 neutron flux detector. Neutron Flux Detector JKT01 basically detects neutron fluxes in the reactor core and converts it into electrical signals. The electrical signal is then forwarded to the amplifier (Amplifier) to become the input of the reactor protection system. One output of it is transferred to the Main Control Room (RKU) showing on the analog meter as an indicator used by the reactor operator. To simulate all of this matter, a program to simulate the output of the JKT01 Neutron Flux Detector using LabVIEW was developed. The simulated data is estimated using a lot of equations also formulated in LabVIEW. The calculation results are also displayed on the interface using LabVIEW available in the PC. By using this simulation program, it is successful to perform anomaly detection experiments on the JKT01 detector of RSG-GAS Reactor. The simulation results showed that the anomaly JKT01 neutron flux using electrical-current-base are respectively, 1.5×,1.7× and 2.0×.

  7. Looking Forward: The Promise of Widespread Implementation of Parent Training Programs

    PubMed Central

    Forgatch, Marion S.; Patterson, Gerald R.; Gewirtz, Abigail H.

    2013-01-01

    Over the past quarter century a body of parent training programs has been developed and validated as effective in reducing child behavior problems, but few of these have made their way into routine practice. This article describes the long and winding road of implementation as applied to children's mental health. Adopting Rogers' (1995) diffusion framework and Fixsen and colleagues' implementation framework (Fixsen, Naoom, Blase, Friedman, & Wallace, 2005), we review more than a decade of research on the implementation of Parent Management Training – Oregon Model (PMTO®). Data from US and international PMTO implementations are used to illustrate the payoffs and the challenges of making empirically supported interventions routine practice in the community. Technological advances that break down barriers to communication across distances, the availability of efficacious programs suitable for implementation, and the urgent need for high quality mental health care provide strong rationales for prioritizing attention to implementation. Over the next quarter of a century, the challenge is to reduce the prevalence of children's psychopathology by creating science-based delivery systems to reach families in need, everywhere. PMID:24443650

  8. Special Inspector General for Afghanistan Reconstruction Quarterly Report to the United States Congress

    DTIC Science & Technology

    2011-04-30

    U.S. Justice Sector Support Program Operating under INL, the Justice Sector Support Program ( JSSP ) aims to develop the capacity of the Afghan criminal...investigators graduated from JSSP legal training programs.252 The JSSP also added to the number of U.S. and local Afghan lawyers on its staff, growing...drafting guidelines for an extension of the JSSP based on experiences in the preceding year. Anticipated changes include moving some functions into the

  9. Amarillo National Resource Center for Plutonium. Quarterly technical progress report, May 1, 1997--July 31, 1997

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    Progress summaries are provided from the Amarillo National Center for Plutonium. Programs include the plutonium information resource center, environment, public health, and safety, education and training, nuclear and other material studies.

  10. 77 FR 71445 - Regulatory and Administrative Waivers Granted for Multifamily Housing Programs To Assist With...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-30

    ... property, loss of life, and displacement of individuals and families from their homes and communities. The... is published quarterly. Since the damage to property and the displacement of families and individuals...

  11. Follow These Step-by-Step Instructions to Prevent Avoidable Tumbles at School.

    ERIC Educational Resources Information Center

    Pater, Robert; And Others

    1987-01-01

    Almost a quarter of disabling work injuries among school employees are caused by slips and falls. Outlines prevention steps and safety programs that can help lower the possibilities of accidents from falls in schools. (MD)

  12. Methods and codes for neutronic calculations of the MARIA research reactor.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Andrzejewski, K.; Kulikowska, T.; Bretscher, M. M.

    2002-02-18

    The core of the MARIA high flux multipurpose research reactor is highly heterogeneous. It consists of beryllium blocks arranged in 6 x 8 matrix, tubular fuel assemblies, control rods and irradiation channels. The reflector is also heterogeneous and consists of graphite blocks clad with aluminum. Its structure is perturbed by the experimental beam tubes. This paper presents methods and codes used to calculate the MARIA reactor neutronics characteristics and experience gained thus far at IAE and ANL. At ANL the methods of MARIA calculations were developed in connection with the RERTR program. At IAE the package of programs was developedmore » to help its operator in optimization of fuel utilization.« less

  13. Lunar in-core thermionic nuclear reactor power system conceptual design

    NASA Technical Reports Server (NTRS)

    Mason, Lee S.; Schmitz, Paul C.; Gallup, Donald R.

    1991-01-01

    This paper presents a conceptual design of a lunar in-core thermionic reactor power system. The concept consists of a thermionic reactor located in a lunar excavation with surface mounted waste heat radiators. The system was integrated with a proposed lunar base concept representative of recent NASA Space Exploration Initiative studies. The reference mission is a permanently-inhabited lunar base requiring a 550 kWe, 7 year life central power station. Performance parameters and assumptions were based on the Thermionic Fuel Element (TFE) Verification Program. Five design cases were analyzed ranging from conservative to advanced. The cases were selected to provide sensitivity effects on the achievement of TFE program goals.

  14. THE SM-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM, NOVEMBER 1954- DECEMBER 1960

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pressman, M; Pruett, P B

    1961-08-31

    BS>An environmental radiological monitoring program was conducted. All data obtained during a period extending from l 1/2 years prior to SM-1 reactor start-up through more than 3 years of reactor operation are summarized. The period extended from November 1954 through December 1960. Samples assayed for radioactivity include river water and bottom silt, SM-1 condenser cooling water, subsurface ground water, rain and snow, atmospheric particles obtained by air filtration and fallout, and biota. The report concludes that after more than 3 years of SM-1 reactor operation, no significant increase has been noted in the radiological background level in the Fort Belvoirmore » area.« less

  15. The current state of the Russian reduced enrichment research reactors program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Aden, V.G.; Kartashov, E.F.; Lukichev, V.A.

    1997-08-01

    During the last year after the 16-th International Conference on Reducing Fuel Enrichment in Research Reactors held in October, 1993 in Oarai, Japan, the conclusive stage of the Program on reducing fuel enrichment (to 20% in U-235) in research reactors was finally made up in Russia. The Program was started late in 70th and the first stage of the Program was completed by 1986 which allowed to reduce fuel enrichment from 80-90% to 36%. The completion of the Program current stage, which is counted for 5-6 years, will exclude the use of the fuel enriched by more than 20% frommore » RF to other countries such as: Poland, Czeck Republick, Hungary, Roumania, Bulgaria, Libya, Viet-Nam, North Korea, Egypt, Latvia, Ukraine, Uzbekistan and Kazakhstan. In 1994 the Program, approved by RF Minatom authorities, has received the status of an inter-branch program since it was admitted by the RF Ministry for Science and Technical Policy. The Head of RF Minatom central administrative division N.I.Ermakov was nominated as the Head of the Russian Program, V.G.Aden, RDIPE Deputy Director, was nominated as the scientific leader. The Program was submitted to the Commission for Scientific, Technical and Economical Cooperation between USA and Russia headed by Vice-President A. Gore and Prime Minister V. Chemomyrdin and was given support also.« less

  16. Characterization of oxidized coal surfaces: Quarterly report, May 1988--September 1988

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hercules, D. M.

    1988-01-01

    Laser mass spectra have been obtained of 2-fluoro-1-methylpyridinium (FMP) derivatized coal consistent with a prime objective of this research. This reagent, specific for the hydroxy functionality, produced major peaks at m/z 184 and 199 in the spectra of Pocahontas coal following derivatization. A gas phase reactor was built in order to enhance coal derivatization. Gas phase derivatization was accomplished on model compounds. Derivatization was carried out on Illinois No. 6 coal and analyzed with DRIFTS to determine the extent of derivatization. Oxidation indices of the oxidized coal decreased upon reacting with 2,4-dinitrophenylhydrazine, a derivatizing agent specific for carbonyl groups, confirmingmore » that the derivatization reaction had taken place. 5 refs., 5 figs.« less

  17. Production of aluminum-silicon alloy and ferrosilicon and commercial purity aluminum by the direct reduction process. Third interim technical report, Phase C for the period 1980 July 1-1980 September 30

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bruno, M.J.

    1980-10-01

    Pilot reactor VSR-3 operation in the third quarter was directed to tapping molten alloy product. Modifications to the hearth region included a tapping furnace to maintain taphole temperature, a graphite ring filter to separate carbides from matal and an alumina liner to eliminate carbiding from reaction of alloy with the graphite hearth walls. Tapping was not successful, however, due to high alloy viscosity from a large concentration of carbides. Three runs were made on the pilot crystallizer to determine the effects of alloy composition, cooling rate, tamping rate, remelt temperature and rate on eutectic Al-Si yield.

  18. Eddy Current Flow Measurements in the FFTF

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Nielsen, Deborah L.; Polzin, David L.; Omberg, Ronald P.

    2017-02-02

    The Fast Flux Test Facility (FFTF) is the most recent liquid metal reactor (LMR) to be designed, constructed, and operated by the U.S. Department of Energy (DOE). The 400-MWt sodium-cooled, fast-neutron flux reactor plant was designed for irradiation testing of nuclear reactor fuels and materials for liquid metal fast breeder reactors. Following shut down of the Clinch River Breeder Reactor Plant (CRBRP) project in 1983, FFTF continued to play a key role in providing a test bed for demonstrating performance of advanced fuel designs and demonstrating operation, maintenance, and safety of advanced liquid metal reactors. The FFTF Program provides valuablemore » information for potential follow-on reactor projects in the areas of plant system and component design, component fabrication, fuel design and performance, prototype testing, site construction, and reactor control and operations. This report provides HEDL-TC-1344, “ECFM Flow Measurements in the FFTF Using Phase-Sensitive Detectors”, March 1979.« less

  19. Gaseous fuel reactors for power systems

    NASA Technical Reports Server (NTRS)

    Kendall, J. S.; Rodgers, R. J.

    1977-01-01

    Gaseous-fuel nuclear reactors have significant advantages as energy sources for closed-cycle power systems. The advantages arise from the removal of temperature limits associated with conventional reactor fuel elements, the wide variety of methods of extracting energy from fissioning gases, and inherent low fissile and fission product in-core inventory due to continuous fuel reprocessing. Example power cycles and their general performance characteristics are discussed. Efficiencies of gaseous fuel reactor systems are shown to be high with resulting minimal environmental effects. A technical overview of the NASA-funded research program in gaseous fuel reactors is described and results of recent tests of uranium hexafluoride (UF6)-fueled critical assemblies are presented.

  20. PLASTIC-SASS--A COMPUTER PROGRAM FOR STRESSES AND DEFLECTIONS IN A REACTOR SUBASSEMBLY UNDER THERMAL, HYDRAULIC, AND FUEL EXPANSION LOADS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Friedrich, C.M.

    1963-05-01

    PLASTlC-SASS, an ALTAC-3 computer program that determines stresses and deflections in a flat-plate, rectangular reactor subassembly is described. Elastic, plastic, and creep properties are used to calculate the results of temperature, pressure, and fuel expansion. Plate deflections increase or decrease local channel thicknesses and thus produce a hydraulic load which is a function of fuel plate deflection. (auth)

  1. Progress in the Production of JP-8 Based Hydrogen and Advanced Tactical Fuels for Military Applications

    DTIC Science & Technology

    2011-02-01

    of a multi- year program to develop, optimize, and demonstrate the military viability of a technology for on-demand production of high...continuous reactor system used for kinetic rate data experiment 86 52 Schematic of a differential reactor. The catalyst bed is kept small , and...program to develop, optimize, and demonstrate the military viability of a technology for on-demand production of high-pressure hydrogen for fuel

  2. Nonproliferation and Threat Reduction Assistance: U.S. Programs in the Former Soviet Union

    DTIC Science & Technology

    2011-04-26

    large - scale former BW-related facilities so that they can perform peaceful research issues such as infectious diseases. The Global Threat Reduction...indicated that it may not pursue the MOX program to eliminate its plutonium, opting instead for the construction of fast breeder reactors that could...burn plutonium directly for energy production. The United States might not fund this effort, as many in the United States argue that breeder reactors

  3. Progress of the RERTR program in 2001.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Travelli, A.

    2002-03-07

    This paper describes the 2001 progress achieved by the Reduced Enrichment for Research and Test Reactors (RERTR) Program in collaboration with its many international partners. Postirradiation examinations of microplates have continued to reveal excellent irradiation behavior of U-Mo dispersion fuels in a variety of compositions and irradiating conditions. Irradiation of two new batches of miniplates of greater sizes was completed in the ATR to investigate the swelling behavior of these fuels under prototypic conditions. These materials hold the promise of achieving the program goal of developing LEU research reactor fuels with uranium densities in the 8-9 g/cm{sup 3} range. Qualificationmore » of the U-Mo dispersion fuels has been delayed by a patent issue involving KAERI. Test fuel elements with uranium density of 6 g/cm{sup 3} are being fabricated by BWXT and are expected to begin undergoing irradiation in the HFR-Petten reactor around March 2003, with a goal of qualifying this fuel by mid-2005. U-Mo fuel with uranium density of 8-9 g/cm{sup 3} is expected to be qualified by mid-2007. Final irradiation tests of LEU {sup 99}Mo targets in the RAS-GAS reactor at BATAN, in Indonesia, had to be postponed because of the 9/11 attacks, but the results collected to date indicate that these targets will soon be ready for commercial production. Excellent cooperation is also in progress with the CNEA in Argentina, MDSN/AECL in Canada, and ANSTO in Australia. Irradiation testing of five WWR-M2 tube-type fuel assemblies fabricated by the NZChK and containing LEU UO{sub 2} dispersion fuel was successfully completed within the Russian RERTR program. A new LEU U-Mo pin-type fuel that could be used to convert most Russian-designed research reactors has been developed by VNIINM and is ready for testing. Four additional shipments containing 822 spent fuel assemblies from foreign research reactors were accepted by the U.S. by September 30, 2001. Altogether, 4,562 spent fuel assemblies from foreign research reactors had been received by that date by the U.S. under the FRR SNF acceptance policy. The RERTR program is aggressively pursuing qualification of high-density LEU U-Mo dispersion fuels, with the dual goal of enabling further conversions and of developing a substitute for LEU silicide fuels that can be more easily disposed of after expiration of the U.S. FRR SNF Acceptance Program. As in the past, the success of the RERTR program will depend on the international friendship and cooperation that has always been its trademark.« less

  4. Review of the TREAT Conversion Conceptual Design and Fuel Qualification Plan

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Diamond, David

    The U.S. Department of Energy (DOE) is preparing to re establish the capability to conduct transient testing of nuclear fuels at the Idaho National Laboratory (INL) Transient Reactor Test (TREAT) facility. The original TREAT core went critical in February 1959 and operated for more than 6,000 reactor startups before plant operations were suspended in 1994. DOE is now planning to restart the reactor using the plant's original high-enriched uranium (HEU) fuel. At the same time, the National Nuclear Security Administration (NNSA) Office of Material Management and Minimization Reactor Conversion Program is supporting analyses and fuel fabrication studies that will allowmore » for reactor conversion to low-enriched uranium (LEU) fuel (i.e., fuel with less than 20% by weight 235U content) after plant restart. The TREAT Conversion Program's objectives are to perform the design work necessary to generate an LEU replacement core, to restore the capability to fabricate TREAT fuel element assemblies, and to implement the physical and operational changes required to convert the TREAT facility to use LEU fuel.« less

  5. Current Abstracts Nuclear Reactors and Technology

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Bales, J.D.; Hicks, S.C.

    1993-01-01

    This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`smore » Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.« less

  6. The CABRI fast neutron Hodoscope: Renovation, qualification program and first results following the experimental reactor restart

    NASA Astrophysics Data System (ADS)

    Chevalier, V.; Mirotta, S.; Guillot, J.; Biard, B.

    2018-01-01

    The CABRI experimental pulse reactor, located at the Cadarache nuclear research center, southern France, is devoted to the study of Reactivity Initiated Accidents (RIA). For the purpose of the CABRI International Program (CIP), managed and funded by IRSN, in the framework of an OECD/NEA agreement, a huge renovation of the facility has been conducted since 2003. The Cabri Water Loop was then installed to ensure prototypical Pressurized Water Reactor (PWR) conditions for testing irradiated fuel rods. The hodoscope installed in the CABRI reactor is a unique online fuel motion monitoring system, operated by IRSN and dedicated to the measurement of the fast neutrons emitted by the tested rod during the power pulse. It is one of the distinctive features of the CABRI reactor facility, which is operated by CEA. The system is able to determine the fuel motion, if any, with a time resolution of 1 ms and a spatial resolution of 3 mm. The hodoscope equipment has been upgraded as well during the CABRI facility renovation. This paper presents the main outcomes achieved with the hodoscope since October 2015, date of the first criticality of the CABRI reactor in its new Cabri Water Loop configuration. Results obtained during reactor commissioning phase functioning, either in steady-state mode (at low and high power, up to 23 MW) or in transient mode (start-up, possibly beyond 20 GW), are discussed.

  7. Mission analysis of photovoltaic solar energy systems. Quarterly progress report, 1 March 1976-31 May 1976

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Leonard, S.L.; Munjal, P.K.; Rattin, E.J.

    1976-06-01

    The main emphasis of the activity during the second quarter of this project continued to be on Task 1, Analysis of Near-Term Missions, and on Task 2, Analysis of Major Mid-Term Missions. In addition, considerable progress was also made on Task 6, Comparison of the True Societal Costs of Conventional and Photovoltaic Power Production, and starts were made on Task 3, Review and Updating of the ERDA Technology Implementation Plan, and Task 4, Critical External Issues. As was planned, work on Task 5, Impact of Incentives, was deferred to the second half of the program. Progress is reported. (WHK)

  8. Hanford Laboratories Operation monthly activities report, September 1961

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1961-10-16

    This is the monthly report for the Hanford Laboratories Operation September 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

  9. 77 FR 68162 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Regulatory...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-15

    ... Water Reactors,'' Revision 2, and Regulatory Guide 1.79.1, ``Initial Test Program of Emergency Core... White Flint North building, 11555 Rockville Pike, Rockville, MD. After registering with security, please...

  10. Survey on New Perkins Loan Proposal: NASFAA Survey Results Show Most Schools Oppose Proposed Perkins Loan Changes. Quick Scan Survey Results

    ERIC Educational Resources Information Center

    National Association of Student Financial Aid Administrators (NJ1), 2009

    2009-01-01

    More than three-quarters of postsecondary institutions (79 percent) would prefer expanding the current Perkins Loan program rather than replacing it with the Direct Perkins Loan program being proposed in Congress, according to a recent survey of NASFAA-member schools. In fact, increasing unsubsidized Stafford Loan limits (80 percent) and lowering…

  11. Who's Afraid of the Big Bad Core? The Common Core Standards and Out-of-School Time Programs

    ERIC Educational Resources Information Center

    Marten, Suzanne; Hill, Sara; Lawrence, Anne

    2014-01-01

    The Robert Bowne Foundation for out-of-school time (OST) supports the development of quality programs that offer literacy education in the out-of-school hours to children and youth of New York City, especially young people from disadvantaged communities. The foundation's networking meetings, now in their 10th year, offer quarterly forums in which…

  12. Programmatic Research to Develop and Disseminate Improved Instructional Technology for Handicapped Children. Project MORE Quarterly Progress Report, September 1 to December 1, 1972.

    ERIC Educational Resources Information Center

    Schiefelbusch, Richard L.; Lent, James R.

    During the past reporting period the curriculum development staff of Project MORE (Mediated Operational Research for Education) has made substantial progress in attaining its program objectives. Design and development phases have proceeded on schedule. Four programs are currently in the field-testing stage, and four others are under development.…

  13. Overview of DOE-NE Proliferation and Terrorism Risk Assessment

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sadasivan, Pratap

    2012-08-24

    Research objectives are: (1) Develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of current reactors; (2) Develop improvements in the affordability of new reactors to enable nuclear energy; (3) Develop Sustainable Nuclear Fuel Cycles; and (4) Understand and minimize the risks of nuclear proliferation and terrorism. The goal is to enable the use of risk information to inform NE R&D program planning. The PTRA program supports DOE-NE's goal of using risk information to inform R&D program planning. The FY12 PTRA program is focused on terrorism risk. The program includes a mixmore » of innovative methods that support the general practice of risk assessments, and selected applications.« less

  14. Preliminary design and hazards report. Boiling Reactor Experiment V (BORAX V)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rice, R. E.

    1960-02-01

    The preliminary objectives of the proposed BORAX V program are to test nuclear superheating concepts and to advance the technology of boiling-water-reactor design by performing experiments which will improve the understanding of factors limiting the stability of boiling reactors at high power densities. The reactor vessel is a cylinder with ellipsoidal heads, made of carbon steel clad internally with stainless steel. Each of the three cores is 24 in. high and has an effective diameter of 39 in. This is a preliminary report. (W.D.M.)

  15. Naval Reactors Prime Contractor Team (NRPCT) Experiences and Considerations With Irradiation Test Performance in an International Environment

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    MH Lane

    2006-02-15

    This letter forwards a compilation of knowledge gained regarding international interactions and issues associated with Project Prometheus. The following topics are discussed herein: (1) Assessment of international fast reactor capability and availability; (2) Japanese fast reactor (JOYO) contracting strategy; (3) NRPCT/Program Office international contract follow; (4) Completion of the Japan Atomic Energy Agency (JAEA)/Pacific Northwest National Laboratory (PNNL) contract for manufacture of reactor test components; (5) US/Japanese Departmental interactions and required Treaties and Agreements; and (6) Non-technical details--interactions and considerations.

  16. The Rockwell SR-100G reactor turboelectric space power system

    NASA Technical Reports Server (NTRS)

    Anderson, R. V.

    1985-01-01

    During FY 1982 and 1983, Rockwell International performed system and subsystem studies for space reactor power systems. These studies drew on the expertise gained from the design and flight of the SNAP-10A space nuclear reactor system. These studies, performed for the SP-100 Program, culminated in the selection of a reactor-turboelectric (gas Brayton) system for the SP-100 application; this system is called the SR-100G. This paper describes the features of the system and provides references where more detailed information can be obtained.

  17. Cladding and duct materials for advanced nuclear recycle reactors

    NASA Astrophysics Data System (ADS)

    Allen, T. R.; Busby, J. T.; Klueh, R. L.; Maloy, S. A.; Toloczko, M. B.

    2008-01-01

    The expanded use of nuclear energy without risk of nuclear weapons proliferation and with safe nuclear waste disposal is a primary goal of the Global Nuclear Energy Partnership (GNEP). To achieve that goal the GNEP is exploring advanced technologies for recycling spent nuclear fuel that do not separate pure plutonium, and advanced reactors that consume transuranic elements from recycled spent fuel. The GNEP’s objectives will place high demands on reactor clad and structural materials. This article discusses the materials requirements of the GNEP’s advanced nuclear recycle reactors program.

  18. Next generation fuel irradiation capability in the High Flux Reactor Petten

    NASA Astrophysics Data System (ADS)

    Fütterer, Michael A.; D'Agata, Elio; Laurie, Mathias; Marmier, Alain; Scaffidi-Argentina, Francesco; Raison, Philippe; Bakker, Klaas; de Groot, Sander; Klaassen, Frodo

    2009-07-01

    This paper describes selected equipment and expertise on fuel irradiation testing at the High Flux Reactor (HFR) in Petten, The Netherlands. The reactor went critical in 1961 and holds an operating license up to at least 2015. While HFR has initially focused on Light Water Reactor fuel and materials, it also played a decisive role since the 1970s in the German High Temperature Reactor (HTR) development program. A variety of tests related to fast reactor development in Europe were carried out for next generation fuel and materials, in particular for Very High Temperature Reactor (V/HTR) fuel, fuel for closed fuel cycles (U-Pu and Th-U fuel cycle) and transmutation, as well as for other innovative fuel types. The HFR constitutes a significant European infrastructure tool for the development of next generation reactors. Experimental facilities addressed include V/HTR fuel tests, a coated particle irradiation rig, and tests on fast reactor, transmutation and thorium fuel. The rationales for these tests are given, results are provided and further work is outlined.

  19. The IRIS Spool-Type Reactor Coolant Pump

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kujawski, J.M.; Kitch, D.M.; Conway, L.E.

    2002-07-01

    IRIS (International Reactor Innovative and Secure) is a light water cooled, 335 MWe power reactor which is being designed by an international consortium as part of the US DOE NERI Program. IRIS features an integral reactor vessel that contains all the major reactor coolant system components including the reactor core, the coolant pumps, the steam generators and the pressurizer. This integral design approach eliminates the large coolant loop piping, and thus eliminates large loss-of-coolant accidents (LOCAs) as well as the individual component pressure vessels and supports. In addition, IRIS is being designed with a long life core and enhanced safetymore » to address the requirements defined by the US DOE for Generation IV reactors. One of the innovative features of the IRIS design is the adoption of a reactor coolant pump (called 'spool' pump) which is completely contained inside the reactor vessel. Background, status and future developments of the IRIS spool pump are presented in this paper. (authors)« less

  20. LOOP marine and estuarine monitoring program, 1978-95 : volume 6 : sediment quality.

    DOT National Transportation Integrated Search

    1998-01-01

    The Louisiana Offshore Oil Port (LOOP) facilities in coastal Louisiana provide the United States with the country's only Superport for off-loading deep draft tankers. Sediment samples were collected quarterly from 1970 through 1995 at designated stat...

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