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Sample records for fort shevchenko reactor

  1. Primary coolant chemistry of the Peach Bottom and Fort St. Vrain high-temperature gas-cooled reactors

    International Nuclear Information System (INIS)

    Burnette, R.D.; Baldwin, N.L.

    1980-11-01

    The chemical impurities in the primary coolants of the Peach Bottom and Fort St. Vrain reactors are discussed. The impurity mixtures in the two plants were quite different because the sources of the impurities were different. In the Peach Bottom reactor, the impurities were dominated by H 2 and CH 4 , which are decomposition products of oil. In the Fort St. Vrain reactor, there were high levels of CO, CO 2 , and H 2 O. Although oil ingress at Peach Bottom created carbon deposits on virtually all surfaces, its effect on reactor operation was negligible. Slow outgassing of water from the thermal insulation at Fort St. Vrain caused delays in reactor startup. The overall graphite oxidation in both plants was negligible

  2. Primary coolant chemistry of the Peach Bottom and Fort St. Vrain high temperature gas-cooled reactors

    International Nuclear Information System (INIS)

    Burnette, R.D.; Baldwin, N.L.

    1981-01-01

    The chemical impurities in the primary coolants of the Peach Bottom and Fort St. Vrain reactors are discussed. The impurity mixtures in the two plants were quite different because the sources of the impurities were different. In the Peach Bottom reactor, the impurities were dominated by H 2 and CH 4 , which are decomposition products of oil. In the Fort St. Vrain reactor, there were high levels of CO, CO 2 , and H 2 O. Although oil ingress at Peach Bottom created carbon deposits on virtually all surfaces, its effect on reactor operation was negligible. Slow outgassing of water from the thermal insulation at Fort St. Vrain caused delays in reactor startup. The overall graphite oxidation in both plants was negligible. (author)

  3. CHAP-2 heat-transfer analysis of the Fort St. Vrain reactor core

    International Nuclear Information System (INIS)

    Kotas, J.F.; Stroh, K.R.

    1983-01-01

    The Los Alamos National Laboratory is developing the Composite High-Temperature Gas-Cooled Reactor Analysis Program (CHAP) to provide advanced best-estimate predictions of postulated accidents in gas-cooled reactor plants. The CHAP-2 reactor-core model uses the finite-element method to initialize a two-dimensional temperature map of the Fort St. Vrain (FSV) core and its top and bottom reflectors. The code generates a finite-element mesh, initializes noding and boundary conditions, and solves the nonlinear Laplace heat equation using temperature-dependent thermal conductivities, variable coolant-channel-convection heat-transfer coefficients, and specified internal fuel and moderator heat-generation rates. This paper discusses this method and analyzes an FSV reactor-core accident that simulates a control-rod withdrawal at full power

  4. FLODIS: a computer model to determine the flow distribution and thermal response of the Fort St. Vrain reactor

    Energy Technology Data Exchange (ETDEWEB)

    Paul, D.D.

    1976-06-01

    FLODIS is a combined heat transfer and fluid flow analysis calculation written specifically for the core of the Fort St. Vrain reactor. It is a lumped-node representation of the 37 refueling regions in the active core. Heat conduction to the coolant and in the axial direction is represented; however, the effect of conduction between refueling regions is not included. The calculation uses the specified operating conditions for the reactor at power to determine appropriate loss coefficients for the variable orifices in each refueling region. Flow distributions following reactor trip and a reduction in coolant pressure and flow are determined assuming that the orifice coefficients remain constant. Iterative techniques are used to determine the distribution of coolant flow as a function of time during the transient. Results are presented for the evaluation of the transient for the Fort St. Vrain reactor following depressurization and cooling with two circulators operating at 8000 rpm.

  5. FLODIS: a computer model to determine the flow distribution and thermal response of the Fort St. Vrain reactor

    International Nuclear Information System (INIS)

    Paul, D.D.

    1976-06-01

    FLODIS is a combined heat transfer and fluid flow analysis calculation written specifically for the core of the Fort St. Vrain reactor. It is a lumped-node representation of the 37 refueling regions in the active core. Heat conduction to the coolant and in the axial direction is represented; however, the effect of conduction between refueling regions is not included. The calculation uses the specified operating conditions for the reactor at power to determine appropriate loss coefficients for the variable orifices in each refueling region. Flow distributions following reactor trip and a reduction in coolant pressure and flow are determined assuming that the orifice coefficients remain constant. Iterative techniques are used to determine the distribution of coolant flow as a function of time during the transient. Results are presented for the evaluation of the transient for the Fort St. Vrain reactor following depressurization and cooling with two circulators operating at 8000 rpm

  6. Depressurization accident analyses for the Fort St. Vrain Reactor

    International Nuclear Information System (INIS)

    Paul, D.D.

    1976-01-01

    Design-basis depressurization accident analyses for the Fort St. Vrain reactor were performed using the FLODIS (Ref. 4) code. The FLODIS code models the active core, side reflector, gas annulus between the core barrel and the PCRV liner, and the PCRV cooling system. Results are presented for the Pelton circulators operating at 10,550, 8800, and 7000 rpm. Maximum temperatures of selected components are plotted as a function of time during the transient. None of the components studied exceeded the temperature at which failure or damage may occur. However, there must be sufficient mixing of the outlet gas in the lower plenum to insure the integrity of the steel liners of the steam generator inlet ducts

  7. Fort St. Vrain reactor performance and operation to full power

    International Nuclear Information System (INIS)

    Simon, W.A.; Bramblett, G.C.

    1982-01-01

    The Fort St. Vrain Nuclear Generating Station, powered by a high-temperature gas-cooled reactor (HTGR), has now been tested to full thermal power. Testing was conducted for the dual purposes of demonstrating component and system capability as a part of the rise-to-power program and determining core fluctuation/redistribution behavior under full power conditions. Both objectives were met. Full power performance of all major components and the achievement of nearly all design objectives has been verified. In addition, the tests showed that the fluctuation phenomenon has been corrected. Core region outlet temperature redistributions have been characterized, related to a physical mechanism, and shown to be inconsequential for overall plant operation

  8. The WIMS-E module W-FORTE

    International Nuclear Information System (INIS)

    Roth, M.J.

    1983-09-01

    There are three distinct versions of the WIMS lattice cell program. WIMS-E is the most general, WIMSD4 is restricted to clusters or to one dimensional slab or annular geometry, and LWRWIMS is designed principally for light water reactor geometries. W-FORTE is used to transfer data from WIMSD4 or LWRWIMS to WIMS-E. A description of the W-FORTE module is given, and includes the relevant data for WIMSD4, LWRWIMS and W-FORTE. (UK)

  9. Fort Saint Vrain operational experience

    International Nuclear Information System (INIS)

    Fuller, C.H.

    1989-01-01

    Fort St. Vrain (FSV), on the system of the Public Service Company of Colorado, is the only high temperature gas-cooled (HTGR) power reactor in the United States. The plant features a helium-cooled reactor with a uranium-thorium fuel cycle. The paper describes the experience made during its operation. (author). 2 refs, 4 figs, 2 tabs

  10. Guide to General Atomic studies of hypothetical nuclear driven accidents for the Fort St. Vrain reactor

    International Nuclear Information System (INIS)

    Wei, T.; Tobias, M.

    1974-03-01

    The work of the General Atomic Company (GAC) in preparing those portions of the Final Safety Analysis Report for the Fort St. Vrain Reactor (FSV) having to do with hypothetical nuclear driven accidents has been reviewed and a guide to this literature has been prepared. The sources for this study are the Final Safety Analysis Report itself, the Quarterly and Monthly Progress Reports, Topical Reports, and Technical Specifications. The problems considered and the methods used are outlined. An appendix gives a systematic analysis which was used as a guide in organizing the references. (U.S.)

  11. Fort St. Vrain core performance

    International Nuclear Information System (INIS)

    McEachern, D.W.; Brown, J.R.; Heller, R.A.; Franek, W.J.

    1977-07-01

    The Fort St. Vrain High Temperature Gas Cooled Reactor core performance has been evaluated during the startup testing phase of the reactor operation. The reactor is graphite moderated, helium cooled, and uses coated particle fuel and on-line flow control to each of the 37 refueling regions. Principal objectives of startup testing were to determine: core and control system reactivity, radial power distribution, flow control capability, and initial fission product release. Information from the core demonstrates that Technical Specifications are being met, performance of the core and fuel is as expected, flow and reactivity control are predictable and simple for the operator to carry out

  12. Fort St. Vrain circulator operating experience

    International Nuclear Information System (INIS)

    Brey, H.L.

    1988-01-01

    Fort St. Vrain, on the system of Public Service Company of Colorado, is the only high-temperature gas-cooled power reactor in the United States. Four helium circulators are utilized in this plant to transfer heat from the reactor to the steam generators. These unique machines have a single stage axial flow helium compressor driven by a single stage steam turbine. A single stage water driven (pelton wheel) turbine is the back-up drive utilizing either feed water, condensate, or fire water as the driving fluid. Developmental testing of the circulators was accomplished prior to installation into Fort St. Vrain. A combined machine operating history of approximately 250,000 hours has shown these machines to be of conservative design and proven mechanical integrity. However, many problems have been encountered in operating the complex auxiliaries which are necessary for successful circulator and plant operation. It has been 15 years since initial installation of the circulators occurred at Fort St. Vrain. During this time, a number of significant issues had to be resolved dealing specifically with machine performance. These events include cavitation damage of the pelton wheels during the initial plant hot functional testing, cracks in the water turbine buckets and cervic coupling, static shutdown seal bellows failure, and, most recently, degradation of components within the steam drive assembly. Unreliable operation particularly with the circulator auxiliaries has been a focus of attention by Public Service Company of Colorado. Actions to replace or significantly modify the existing circulators and their auxiliaries are currently awaiting decisions concerning the long-term future of the Fort St. Vrain plant. (author). 10 refs, 7 figs, 2 tabs

  13. Fort St. Vrain circulator operating experience

    Energy Technology Data Exchange (ETDEWEB)

    Brey, H. L.

    1988-08-15

    Fort St. Vrain, on the system of Public Service Company of Colorado, is the only high-temperature gas-cooled power reactor in the United States. Four helium circulators are utilized in this plant to transfer heat from the reactor to the steam generators. These unique machines have a single stage axial flow helium compressor driven by a single stage steam turbine. A single stage water driven (pelton wheel) turbine is the back-up drive utilizing either feed water, condensate, or fire water as the driving fluid. Developmental testing of the circulators was accomplished prior to installation into Fort St. Vrain. A combined machine operating history of approximately 250,000 hours has shown these machines to be of conservative design and proven mechanical integrity. However, many problems have been encountered in operating the complex auxiliaries which are necessary for successful circulator and plant operation. It has been 15 years since initial installation of the circulators occurred at Fort St. Vrain. During this time, a number of significant issues had to be resolved dealing specifically with machine performance. These events include cavitation damage of the pelton wheels during the initial plant hot functional testing, cracks in the water turbine buckets and cervic coupling, static shutdown seal bellows failure, and, most recently, degradation of components within the steam drive assembly. Unreliable operation particularly with the circulator auxiliaries has been a focus of attention by Public Service Company of Colorado. Actions to replace or significantly modify the existing circulators and their auxiliaries are currently awaiting decisions concerning the long-term future of the Fort St. Vrain plant. (author). 10 refs, 7 figs, 2 tabs.

  14. Analysis and evaluation of recent operational experience from the Fort St. Vrain HTGR

    International Nuclear Information System (INIS)

    Moses, D.L.; Lanning, W.D.

    1985-05-01

    The Fort St. Vrain operating experience to be discussed here includes notable safety-related events which have occurred since late 1981 when ORNL was first contracted to provide technical assistance to AEOD. Earlier Fort St. Vrain operating experience through the time of successful full-power testing in November 1981 has been summarized by the licensee and the reactor vendor, GA Technologies, Inc. (GA), in papers presented at several different forums during 1982. In addition, extensive and very useful detailed evaluations of preoperational and startup testing and of the rise-to-power operating experience through completion of the first refueling outage in August 1979 have been compiled into a series of reports under the sponsorship of the Electric Power Research Institute (EPRI). Finally, the US Department of Energy's Fort St. Vrain Improvement Plan provides a summary of the major operational limits which have affected the plant since start-up. The events discussed here are categorized based on the major systems affected, namely, (1) primary system and reactor vessel, (2) electrical systems, and (3) the reactor building. In all cases to be discussed, the lessons to be learned are vigilance and prevention. These lessons translate into the need for the recognition and control of unexpected situations and of their potential for branching effects. At Fort St. Vrain, these lessons are found in the effects of moisture ingress, in the challenges experienced to the supply of essential electrical power, and in controlling the environment of the reactor building. 13 refs

  15. Radiochemical analysis of the first plateout probe from the Fort St. Vrain high-temperature gas-cooled reactor

    International Nuclear Information System (INIS)

    Burnette, R.D.

    1982-06-01

    This report presents the analysis of radioactive elements on the first plateout probe from the Fort St. Vrain high-temperature gas-cooled reactor. The plateout probe is a device which samples the primary coolant for condensible fission products. Circuit inventories of individual radionuclides are estimated from the probe analysis. The analysis shows that the radioactive contamination in the primary circuit is remarkable low, with activation product concentrations much greater than that of fission products. The analysis demonstrates that the concentrations of the key fission products I-131 and Sr-90 are far below the limits allowed by the technical specification

  16. Leaktightness in HTGRs - experience at Fort St. Vrain

    International Nuclear Information System (INIS)

    Neylan, A.J.; Barker, R.A.; Deardorff, A.F.

    1976-01-01

    The Fort St. Vrain Prestressed Concrete Reactor Vessel is the first utilized to contain the helium coolant of a High Temperature Gas-Cooled Reactor. Because the helium coolant contains fission products, leakage from the vessel is limited to 15 percent of vessel inventory per year. This paper describes the fabrication methods and development tests used to assure this leaktightness and the leakage test conducted to verify it. (author)

  17. Calculations of the three-dimensional power distribution in the Fort St. Vrain reactor using UK methods and data

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, D W

    1973-04-15

    Assessments of the ability of UK methods and data developed primarily for the low enriched uranium cycle to simulate thorium cycle HTRs haye been extended to cover reactivity and power distributions in commercial size reactors. The Fort St. Vrain 330 MW(E) HTR being built in the United States by Gulf General Atomic has been chosen as a convenient object for such a study since detailed design information together with the results of GGA's own calculations have been published. The results obtained are in good agreement with those obtained by GGA and indicate that both thorium and low enriched cycle HTRs can be adequately modelled with UK data and methods.

  18. Construction experience on PCRV liners at Fort St. Vrain

    International Nuclear Information System (INIS)

    Cliff, J.O.; Wunderlich, R.G.

    1976-01-01

    The construction of the steel liners for the Fort St. Vrain prestressed concrete reactor vessel presented many unique problems for which techniques were developed to satisfy the rigid specification requirements. The PCRV cavity liner was fabricated from 1.9cm carbon steel plate. The liners were partially fabricated by Pittsburgh-Des Moines Steel Company at their Pittsburgh manufacturing facility. The liners were then shipped by rail to within approximately five miles of the jobsite and then trucked the remaining distance. The construction techniques, dimensional control, concrete support and testing utilized on the Fort St. Vrain project are presented in detail and demonstrate the flexibility of the PCRV for field construction. (author)

  19. Fortællingen

    DEFF Research Database (Denmark)

    Hejlsted, Annemette

    Fortællingen - teori og analyse introducerer til teorier om fortællingen og præsenterer et sæt af analytiske tilgange til fortællinger af enhver art. Bogen lægger vægt på læsersynsvinklen og retter opmærksomheden mod de vilkår for menings- og betydningsdannelse, der kendetegner fortællingen. Begr....... Begreber om plot, fortællingens verden, karakterer, fortæller, modus og genre behandles, og deres anvendelse demonstreres på dansk og nordisk litteratur - med inddragelse af eksempler fra film og tv-reklamer....

  20. Nondestructive evaluation of the oxidation and strength of the Fort Saint Vrain HTGR support block

    International Nuclear Information System (INIS)

    Tingey, G.L.; Posakony, G.J.; Morgan, W.C.; Prince, J.M.; Hill, R.W.; Lessor, D.L.

    1982-04-01

    Non-destructive detection of changes in the strength of graphite support structures in a HTGR appears to be feasible using sonic velocity measurements where access for through transmission is possible. Therefore, future HTGR designs should consider providing such access. Where access is not available, strength changes can be correlated with oxidation profiles in the support member. These oxidation profiles can be determined non-destructively by a combination of eddy current measurements to detect near surface oxidation and sonic backscattering measurements designed to determine oxidation in depth. The Fort Saint Vrain reactor provides an operating reactor to test the applicability of the eddy current and sonic backscattering techniques for determination of oxidation in a support block. Furthermore, such tests in Fort Saint Vrain will supply base line data which will be useful in assuring an adequate strength of the support structure for the lifetime of the reactor. Equipment is, therefore, being developed for tests to be conducted during the next major refueling of the reactor

  1. Characteristics of potential repository wastes: Volume 4, Appendix 4A, Nuclear reactors at educational institutions of the United States; Appendix 4B, Data sheets for nuclear reactors at educational institutions; Appendix 4C, Supplemental data for Fort St. Vrain spent fuel; Appendix 4D, Supplemental data for Peach Bottom 1 spent fuel; Appendix 4E, Supplemental data for Fast Flux Test Facility

    International Nuclear Information System (INIS)

    1992-07-01

    Volume 4 contains the following appendices: nuclear reactors at educational institutions in the United States; data sheets for nuclear reactors at educational institutions in the United States(operational reactors and shut-down reactors); supplemental data for Fort St. Vrain spent fuel; supplemental data for Peach Bottom 1 spent fuel; and supplemental data for Fast Flux Test Facility

  2. Fort St. Vrain decommissioning project

    International Nuclear Information System (INIS)

    Fisher, M.

    1998-01-01

    Public Service Company of Colorado (PSCo), owner of the Fort St. Vrain nuclear generating station, achieved its final decommissioning goal on August 5, 1997 when the Nuclear Regulatory Commission terminated the Part 50 reactor license. PSCo pioneered and completed the world's first successful decommissioning of a commercial nuclear power plant after many years of operation. In August 1989, PSCo decided to permanently shutdown the reactor and proceed with its decommissioning. The decision to proceed with early dismantlement as the appropriate decommissioning method proved wise for all stake holders - present and future - by mitigating potential environmental impacts and reducing financial risks to company shareholders, customers, employees, neighboring communities and regulators. We believe that PSCo's decommissioning process set an exemplary standard for the world's nuclear industry and provided leadership, innovation, advancement and distinguished contributions to other decommissioning efforts throughout the world. (author)

  3. Operational experience at Fort St. Vrain

    International Nuclear Information System (INIS)

    Bramblett, G.C.; Fisher, C.R.; Swart, F.E.

    1981-01-01

    The Fort St. Vrain (FSV) station, a 330-MW(e) single reheat steam cycle powered by a high-temperature gas-cooled reactor (HTGR), is the first HTGR to enter commercial operation. Designed and built by General Atomic Company (GA), the plant is owned and operated by Public Service Company of Colorado (PSC). Many unique design features have been incorporated into this reactor system, including high-pressure helium as the primary system coolant, a graphite-moderated prismatic block core design, fission-product-containing carbide coatings on both fissile and fertile fuel particles, steam-driven helium circulators turning on water bearings, and once-through steam generators. All of these systems are contained in a prestressed concrete reactor vessel (PCRV). Extensive testing has been conducted during the rise to power following first criticality early in 1974 to verify system design performance. During this period, the plant has operated at power levels up to 70% and produced over one billion kilowatt hours of electricity. In 1979, the first refueling was conducted in conjunction with an extensive in-core inspection, the addition of in-core instrumentation, and a planned removal of a circulator for inspection. Later in the year, a scheduled shutdown was undertaken for surveillance tests, insertion of core region constraint devices (RCDs), and other maintenance. Fort St. Vrain has encountered problems of the type that would be expected in a first-of-a-kind system. The plant is currently restricted to 70% of design power by the Nuclear Regulatory Commission (NRC) pending resolution of the core region gas outlet temperature fluctuation problem. Even so, the basic performance of the HTGR concept and all of the unique design features have been successfully demonstrated. The system has been characterized by low personnel radiation exposures, operational flexibility, and long time afforded for status evaluation and response. (author)

  4. A reactivity accidents simulation of the Fort Saint Vrain HTGR

    International Nuclear Information System (INIS)

    Fainer, Gerson

    1980-01-01

    A reactivity accidents analysis of the Fort Saint Vrain HTGR was made. The following accidents were analysed 1) A rod pair withdrawal accident during normal operation, 2) A rod pair ejection accident, 3) A rod pair withdrawal accident during startup operations at source levels and 4) Multiple rod pair withdrawal accident. All the simulations were performed by using the BLOOST-6 nuclear code The steady state reactor operation results obtained with the code were consistent with the design reactor data. The numerical analysis showed that all accidents - except the first one - cause particle failure. (author)

  5. Safety and licensing analyses for the Fort St. Vrain HTGR

    International Nuclear Information System (INIS)

    Ball, S.J.; Conklin, J.C.; Harrington, R.M.; Cleveland, J.C.; Clapp, N.E. Jr.

    1982-01-01

    The Oak Ridge National Laboratory (ORNL) safety analysis program for the HTGR includes development and verification of system response simulation codes, and applications of these codes to specific Fort St. Vrain reactor licensing problems. Licensing studies addressed the oscillation problems and the concerns about large thermal stresses in the core support blocks during a postulated accident

  6. Operational testing highlights of Fort St. Vrain

    International Nuclear Information System (INIS)

    Cadwell, J.J.; McEachern, D.W.; Read, J.W.; Simon, W.A.; Walker, R.F.

    1975-01-01

    The Fort St. Vrain program has progressed through construction, preoperational testing, fuel loading, initial criticality, and operational testing at power levels up to 2 percent related power. To date, all tests necessary before the rise to full power have been completed, and the rise-to-power program is expected to be resumed again in late 1975. Major plant systems, including the prestressed concrete reactor vessel and circulators, have demonstrated adequate performance. Extensive tests on the reactor core at zero power and up to 2 percent power have demonstrated the accuracy in the design predictions of such core characteristics as critical rod position, control system worths, neutron flux distributions, and temperature coefficients. Gaseous fission product release measurements to date have confirmed the extensive analytical estimates. 6 references

  7. Fort St. Vrain defueling ampersand decommissioning considerations

    International Nuclear Information System (INIS)

    Warembourg, D.

    1994-01-01

    Fort St. Vrain Nuclear Generating Station (FSV) is one of the first commercial reactors to be decommissioned under NRC's decommissioning rule. The defueling and decommissioning of this 330 MWe High Temperature Gas Cooled Reactor (HTGR) has involved many challenges for Public Service Company of Colorado (PSC) including defueling to an Independent Spent Fuel Storage Installation (ISFSI), establishing decommissioning funding, obtaining regulatory approvals, arranging for waste disposal, and managing a large fixed price decommissioning contract. In 1990, a team comprised of the Westinghouse Corporation and Morrison Knudsen Corporation, with the Scientific Ecology Group as a major subcontractor, was contracted by PSC to perform the decommissioning under a fixed price contract. Physical work activities began in August 1992. Currently, physical dismantlement activities are about 45% complete, the project is on schedule, and is within budget

  8. Fort St. Vrain improvement program plan. Draft final report

    International Nuclear Information System (INIS)

    1980-03-01

    The restraints are described which inhibit the Fort St. Vrain (FSV) Nuclear Power Station, a high temperature gas cooled reactor (HTGR) plant, from achieving full power operation with high availability. The actions necessary to overcome these restraints are outlined. The restraints originated from problems in both hardware related and institutional areas. The report summarizes what has been accomplished, what is currently being done, and what should be done to resolve the problems

  9. Test and evaluation of the Fort St. Vrain dew point moisture monitor system

    International Nuclear Information System (INIS)

    Block, G.A.; Del Bene, J.V. Jr.; Gitterman, M.; Hastings, G.A.; Hawkins, W.M.; Hinz, R.F.; McCue, D.E.; Swanson, L.L.; Vavrina, J.; Zwetzig, G.B.

    1975-01-01

    Descriptions are given of the Fort St. Vrain Dew Point Moisture Monitor (DPMM) System; the bases for the DPMM system response time requirements for safety related functions at the required reactor operating conditions; the results and evaluation of recent testing which measured the performance of the current system at simulated operating conditions; predicted response times for reactor power operation from 0 to 100 percent and a modification to provide improved response times for low-load and plant start-up conditions

  10. Operational experience at Fort St. Vrain

    Energy Technology Data Exchange (ETDEWEB)

    Bramblett, G. C.; Fisher, C. R.; Swart, F. E. [General Atomic Co., San Diego, CA (USA)

    1981-01-15

    The Fort St. Vrain (FSV) station, a 330-MW(e) single reheat steam cycle powered by a high-temperature gas-cooled reactor (HTGR), is the first HTGR to enter commercial operation. Designed and built by General Atomic Company (GA), the plant is owned and operated by Public Service Company of Colorado (PSC). Many unique design features have been incorporated into this reactor system, including high-pressure helium as the primary system coolant, a graphite-moderated prismatic block core design, fission-product-containing carbide coatings on both fissile and fertile fuel particles, steam-driven helium circulators turning on water bearings, and once-through steam generators. All of these systems are contained in a prestressed concrete reactor vessel (PCRV). Extensive testing has been conducted during the rise to power following first criticality early in 1974 to verify system design performance. During this period, the plant has operated at power levels up to 70% and produced over one billion kilowatt hours of electricity. In 1979, the first refueling was conducted in conjunction with an extensive in-core inspection, the addition of in-core instrumentation, and a planned removal of a circulator for inspection.

  11. Fission product behavior in the Peach Bottom and Fort St. Vrain HTGRs

    International Nuclear Information System (INIS)

    Hanson, D.L.; Baldwin, N.L.; Strong, D.E.

    1980-11-01

    Actual operating data from Peach Bottom and Fort St. Vrain were compared with code predictions to assess the validity of the methods used to predict the behavior of fission products in the primary coolant circuit. For both reactors the measured circuit activities were significantly below design values, and the observations generally verify the codes used for large HTGR design

  12. ORNL's NRC-sponsored HTGR safety and licensing analysis activities for Fort St. Vrain and advanced reactors

    International Nuclear Information System (INIS)

    Ball, S.J.; Cleveland, J.C.; Harrington, R.M.

    1985-01-01

    The ORNL safety analysis program for the HTGR was established in 1974 to provide technical assistance to the USNRC on licensing questions for both Fort St. Vrain and advanced plant concepts. The emphasis has been on development of major component and system dynamic simulation codes, and use of these codes to analyze specific licensing-related scenarios. The program has also emphasized code verification, using Fort St. Vrain data where applicable, and comparing results with industry-generated codes. By the use of model and parameter adjustment routines, safety-significant uncertainties have been identified. A major part of the analysis work has been done for the Fort St. Vrain HTGR, and has included analyses of FSAR accident scenario re-evaluations, the core block oscillation problem, core support thermal stress questions, technical specification upgrade review, and TMI action plan applicability studies. The large, 2240-MW(t) cogeneration lead plant design was analyzed in a multi-laboratory cooperative effort to estimate fission product source terms from postulated severe accidents

  13. Fortæller

    DEFF Research Database (Denmark)

    Larsen, Gorm

    2012-01-01

    Siden Gerard Genettes ”Discours du récit” (1972) er distinktionen mellem hvem, der taler, og hvem, der ser, blevet cementeret som et grundparadigme i narratologien og litteraturteorien. Genettes pointe var, at den etablerede narrative teori – som fx Wayne C. Booths The Rhetoric of Fiction (1961...... narratologi blevet forsøgt udfordret, enten fordi det hævdes, at en tekst ikke nødvendigvis er udstyret med en fortæller, eller fordi begrebet om fortæller antages at bero på en misvisende og reduktiv antropomorficering. Eller omvendt fordi der i Genettes begrebsdannelse ligger en forkastelse af...... forestillingen om en implicit forfatter (implied author) og dermed også en afvisning af en upålidelige fortæller. Kapitlet præsenterer begreberne fortæller og synsvinkel i narratologien med afsæt i Genettes bestemmelser og diskutere de problemer, der opstår i kølvandet herpå. Det være sig både de rent...

  14. Status of the Fort St. Vrain decommissioning

    International Nuclear Information System (INIS)

    Fisher, M.J.

    1990-01-01

    Fort St. Vrain is a high temperature gas cooled reactor. It has been shut down as a result of financial and technical difficulties. Fort St. Vrain has been planning for defueling and decommissioning for at least three years. The preliminary decommissioning plan, in accordance with the NRC's final rule, has been submitted and is being reviewed by the NRC. The basis of the preliminary decommissioning plan has been SAFSTOR. Public Service Company, who is the owner and operator of FSV, is scheduled to submit a proposed decommissioning plan to the NRC in the fourth quarter of 1990. PSC has gone out for bid on the decontamination and dismantlement of FSV. This paper includes the defueling schedule, the independent spent fuel storage installation status, the probability of shipping fuel to DOE, the status of the preliminary decommissioning plan submittal, the issuance of a possession only license and what are the results of obtaining this license amendment, preliminary decommissioning activities allowed prior to the approval of a proposed decommissioning plan, the preparation of a proposed decommissioning plan and the status of our decision to proceed with SAFSTOR or DECON as identified in the NRC's final decommissioning rule

  15. Water quality and hydrology in the Fort Belvoir area, Virginia, 1954-55

    Science.gov (United States)

    Durfor, Charles N.

    1961-01-01

    This report summarizes the results of an investigation of water quality and hydrology in the Fort Belvoir, Va., area for the period August 1954 to September 1955. It summarizes and evaluates information about the water resources of this area that are pertinent to the choice of location and operation of an Army nuclear power reactor. The quantity, quality, nature, and use of the local water that might be affected by the location and operation of a reactor in the area were subjects of investigation. Variations in the quality of the water caused by variation in streamflow, tidal effects, and pollution were important facets of the investigation. During extended periods of low streamflow in the Potomac River (usually in the late summer months), salty water moves upstream from Chesapeake Bay and increases the dissolved solids content of the surface waters adjacent to Fort Belvoir. When the streamflow is low the concentration of dissolved solids in the water near the river bottom exceeds that near the surface. The waters in Gunston Cove usually contain more dissolved oxygen than those in the Potomac River. During the summer, the content of dissolved oxygen in the cove waters frequently exceeds 100 percent of saturation. Surface floats that were released on a flood tide in Gunston Cove moved toward the inner portion of the cove in the same direction as the wind and the tide. The maximum average velocity of these floats was 0.65 feet per second. On an ebb tide, many surface floats that were released in Gunston Cove moved toward the inner portion of the cove in the direction of the wind, in opposition to the direction of the tidal movement. Floats released near the mouth of the cove on the same tide, moved with the tide out of the cove through a narrow pass at the end of a submerged sandbar extending from the Fort Belvoir shoreline. The maximum average velocity of the floats in the pass on this ebb tide was 0.85 feet per second. Measurements of subsurface flow direction

  16. СТЕЛІАН ГРУЯ – ДОСЛІДНИК ТВОРЧОСТІ ТАРАСА ШЕВЧЕНКА / STELIAN HRUYA AS A RESEARCHER OF TARAS SHEVCHENKO'S CREATIONS

    Directory of Open Access Journals (Sweden)

    Антоній МОЙСЕЙ

    2017-03-01

    Full Text Available Мойсей А., Каизер И. Стелиан Груя – исследователь творчества Тараса Шевченко. С 90-х годов ХІХ века положено начало румынского шевченковедения. Значительный вклад в развитие этой галузи сделали такие ученые, как Т. Носенко, М. Ласло-Куцюк, К. Барборике, И. Ребошапка, С. Груя и др. В статье пойдет речь о работах Стелиана Груи, посвященных творчеству Тараса Шевченко («Т. Шевченко – поет-романтик», «Молитва и проклятие: критическое исследование». Также проанализированы сочинения «Гайдамаки», «Псалмы Давидовы», «Великий лех», «Иван Подкова», их интерпретация румынским ученым. Ключевые слова: Т. Шевченко, шевченковедение, романтизм, историческая поэма, мистерия. Antoniy Moysey, Iryna Kaizer. Stelian Hruya as a researcher of Taras Shevchenko's creations. The process of assimilation of Shevchenko`s writings in Romania, and, accordingly, the appearing of the Shevchenko studies are divided into two periods – before and after World War II. For the first time the Kobzar`s name began to appear on the pages of periodicals in the 90's. XIX century, when the magazine «Contenporanul» reprinted the article about the Ukrainian poet from the French newspaper «Le Temps». The ballad «Prychynna» became the first translated work of the Ukrainian poet in Romania. The Romanian academic Shevchenko studies begin only after World War II. One of the most famous Romanian experts of the Ukrainian literature and culture can be

  17. Construction, testing, and initial operation of Fort St. Vrain PCRV

    International Nuclear Information System (INIS)

    Ople, F.S. Jr.; Neylan, A.J.

    1975-01-01

    The Fort St. Vrain (FSV) Nuclear Generating Station is the first station in the USA to use a prestressed concrete reactor vessel (PCRV). The PCRV was designed and constructed by General Atomic. Construction of the PCRV was completed in 1970; the pressure and leak tests were completed in 1971. The structural behavior of the PCRV has been monitored by installed instrumentation since start of construction. The highlights of the actual construction, testing, and initial operation of the PCRV, including a comparison of structural behavior, where possible, between observed data and analytical predictions. (U.S.)

  18. Plant maintenance and advanced reactors, 2006

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2006-09-15

    The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: Advanced plants to meet rising expectations, by John Cleveland, International Atomic Energy Agency, Vienna; A flexible and economic small reactor, by Mario D. Carelli and Bojan Petrovic, Westinghouse Electric Company; A simple and passively safe reactor, by Yury N. Kuznetsov, Research and Development Institute of Power Engineering (NIKIET), Russia; Gas-cooled reactors, by Jeffrey S. Merrifield, U.S. Nuclear Regulatory Commission; ISI project managment in the PRC, by Chen Chanbing, RINPO, China; and, Fort Calhoun refurbishment, by Sudesh Cambhir, Omaha Public Power District.

  19. Water-chemical regime of a fast reactor ower complex

    International Nuclear Information System (INIS)

    Musikhin, R.N.; Piskunov, E.M.; Samarkin, A.A.; Yurchenko, D.S.

    1983-01-01

    Some peculiarities of water-chemical regime of a power compleX in Shevchenko are considered. The complex comprises a desalination unit, a gas-masout heating-and-power plant and the BN-350 reactor. The compleX is used for the production of electric and thermal energy and fresh water. The power complex peculiarity is the utilization of disalinated seawater in a technological cycle along with highly mineralized seawater with a total salt content of 13.5 g/l (for cooling) in heat exchanges. A regime of ammoniacal correction of feed water was used as a basic water-chemical regime in the initial period of the BN-350 steam generator operation. Deposits composed mainly of iron oxide slime were observed on steam generator surfaces during the operation under these conditions. A conclusion is made that the regime with chelating agent providing steam generator safe operation without chemical cleaning is the most expedient one

  20. Equipment for nondestructive evaluation of the strength of the Fort St. Vrain core-support blocks

    International Nuclear Information System (INIS)

    Morgan, W.C.; Prince, J.M.; Posakony, G.J.

    1982-09-01

    A novel sweep-frequency eddy current instrument has been constructed for measuring density-depth profiles in oxidized graphite. Development work on additional parts of the instrumentation package, that was to be tested in the Fort St. Vrain High Temperature Gas-Cooled Reactor, has been temporarily halted. This report documents the work which has been accomplished to date and presents the current status of the equipment development effort

  1. Dynamic computer simulation of the Fort St. Vrain steam turbines

    International Nuclear Information System (INIS)

    Conklin, J.C.

    1983-01-01

    A computer simulation is described for the dynamic response of the Fort St. Vrain nuclear reactor regenerative intermediate- and low-pressure steam turbines. The fundamental computer-modeling assumptions for the turbines and feedwater heaters are developed. A turbine heat balance specifying steam and feedwater conditions at a given generator load and the volumes of the feedwater heaters are all that are necessary as descriptive input parameters. Actual plant data for a generator load reduction from 100 to 50% power (which occurred as part of a plant transient on November 9, 1981) are compared with computer-generated predictions, with reasonably good agreement

  2. Nondestructive examination of 51 fuel and reflector elements from Fort St. Vrain Core Segment 1

    International Nuclear Information System (INIS)

    Miller, C.M.; Saurwein, J.J.

    1980-12-01

    Fifty-one fuel and reflector elements irradiated in core segment 1 of the Fort St. Vrain High-Temperature Gas-Cooled Reactor (HTGR) were inspected dimensionally and visually in the Hot Service Facility at Fort St. Vrain in July 1979. Time- and volume-averaged graphite temperatures for the examined fuel elements ranged from approx. 400 0 to 750 0 C. Fast neutron fluences varied from approx. 0.3 x 10 25 n/m 2 to 1.0 x 10 25 n/m 2 (E > 29 fJ)/sub HTGR/. Nearly all of the examined elements shrank in both axial and radial dimensions. The measured data were compared with strain and bow predictions obtained from SURVEY/STRESS, a computer code that employs viscoelastic beam theory to calculate stresses and deformations in HTGR fuel elements

  3. ALARA and decommissioning: The Fort St. Vrain experience

    Energy Technology Data Exchange (ETDEWEB)

    Borst, T.; Niehoff, M. [Public Service Co. of Colorado, Platteville, CO (United States); Zachary, M. [Scientific Ecology Group, Platteville, CO (United States)

    1995-03-01

    The Fort St. Vrain Nuclear Generating Station, the first and only commercial High Temperature Gas Cooled Reactor to operate in the United States, completed initial fuel loading in late 1973 and initial startup in early 1974. Due to a series of non-nuclear technical problems, Fort St. Vrain never operated consistently, attaining a lifetime capacity factor of slightly less than 15%. In August of 1989, the decision was made to permanently shut down the plant due to control rod drive and steam generator ring header failures. Public Service Company of Colorado elected to proceed with early dismantlement (DECON) as opposed to SAFSTOR on the bases of perceived societal benefits, rad waste, and exposure considerations, regulatory uncertainties associated with SAFSTOR, and cost. The decommissioning of Fort St. Vrain began in August of 1992, and is scheduled to be completed in early 1996. Decommissioning is being conducted by a team consisting of Westinghouse, MK-Ferguson, and Scientific Ecology Group. Public Service Company of Colorado as the licensee provides contract management and oversight of contractor functions. An aggressive program to maintain project radiation exposures As Low As Reasonably Achievable (ALARA) has been established, with the following program elements: temporary and permanent shielding contamination control; mockup training; engineering controls; worker awareness; integrated work package reviews communication; special instrumentation; video camera usage; robotics application; and project committees. To date, worker exposures have been less than project estimates. from the start of the project through Februrary of 1994, total exposure has been 98.666 person-rem, compared to the project estimate of 433 person-rem and goal of 347 person-rem. The presentation will discuss the site characterization efforts, the radiological performance indicator program, and the final site release survey plans.

  4. Defense.gov Special Report: Fort Hood Shooting

    Science.gov (United States)

    identify possible insider threats, Army Secretary John M. McHugh told lawmakers. Story Obama: Soldiers ," Army Secretary John M. McHugh told lawmakers. Story President Praises Swift Response to Fort Hood Remarks on Fort Hood Shooting at White House McHugh, Odierno Address Fort Hood Shooting Before Congress

  5. Preplaced aggregate concrete application on Fort St. Vrain PCRV construction

    International Nuclear Information System (INIS)

    Ople, F.S. Jr.

    1976-01-01

    Two distinct concreting methods were employed in the construction of the prestressed concrete reactor vessel (PCRV) of the Fort St. Vrain (FSV) Nuclear Generating Station, a 330 MW(e) High Temperature Gas-Cooled Reactor installation near Denver, Colorado. Preplaced aggregate concrete (PAC) techniques were employed in the PCRV bottom head and the core support floor; conventional job-mixed concrete was used in the PCRV sidewall and top head regions. This paper describes the successful application of PAC techniques utilized primarily in solving construction difficulties associated with confined and heavily congested regions of the PCRV. The PAC technique consists of placing coarse aggregate inside the forms, followed by injection of grout under pressure through embedded pipes to fill the interstices in the aggregate mass. Details of the PAC construction method including grout mix development, grouting equipment, grout pipe layout, grouting sequence, grout level monitoring, concrete temperature control, and pre-construction mockups are described. (author)

  6. Assessment of effects of Fort St. Vrain HTGR primary coolant on Alloy 800. Final report

    International Nuclear Information System (INIS)

    Trester, P.W.; Johnson, W.R.; Simnad, M.T.; Burnette, R.D.; Roberts, D.I.

    1982-08-01

    A comprehensive review was conducted of primary helium coolant chemistry data, based on current and past operating histories of helium-cooled, high-temperature reactors (HTGRs), including the Fort St. Vrain (FSV) HTGR. A reference observed FSV reactor coolant environment was identified. Further, a slightly drier expected FSV coolant chemistry was predicted for reactor operation at 100% of full power. The expected environment was compared with helium test environments used in the US, United Kingdom, Germany, France, and Japan. Based on a comprehensive review and analysis of mechanical property data reported for Alloy 800 tested in controlled-impurity helium environments (and in air when appropriate for comparison), an assessment was made of the effect of FSV expected helium chemistry on material properties of alloy 800, with emphasis on design properties of the Alloy 800 material utilized in the FSV steam generators

  7. New Life for Astronomical Instruments of the Past at the Astronomical Observatory of Taras Shevchenko

    Science.gov (United States)

    Kazantseva, Liliya

    2012-09-01

    Astronomical instruments of the past are certainly valuable artifacts of the history of science and education. Like other collections of scientific equipment, they also demonstrate i) development of scientific and technical ideas, ii) technological features of the historical period, iii) professional features of artists or companies -- manufacturers, and iv) national and local specificity of production. However, astronomical instruments are also devices made for observations of rare phenomena -- solar eclipses, transits of planets of the solar disk, etc. Instruments used to study these rare events were very different for each event, since the science changed quickly between events. The Astronomical Observatory of Kyiv National Taras Shevchenko University has a collection of tools made by leading European and local shops from the early nineteenth century. These include tools for optically observing the first artificial Earth satellites, photography, chronometry, and meteorology. In addition, it has assembled a library of descriptions of astronomical instruments and makers'price-lists. Of particular interest are the large stationary tools that are still active in their pavilions. Almost every instrument has a long interesting history. Museification of astronomical instruments gives them a second life, expanding educational programs and tracing the development of astronomy in general and scientific institution and region in particular. It would be advisable to first create a regional database of these rare astronomical instruments (which is already being done in Ukraine), then a common global database. By combining all the historical information about astronomical instruments with the advantages of the Internet, you can show the full evolution of an astronomical instrument with all its features. Time is relentless, and much is destroyed, badly kept and thrown in the garbage. We need time to protect, capture, and tell about it.

  8. Renewable Energy Opportunities at Fort Hood, Texas

    Energy Technology Data Exchange (ETDEWEB)

    Solana, Amy E.; Warwick, William M.; Orrell, Alice C.; Russo, Bryan J.; Parker, Kyle R.; Weimar, Mark R.; Horner, Jacob A.; Manning, Anathea

    2011-11-14

    This report presents the results of Pacific Northwest National Laboratory's (PNNL) follow-on renewable energy (RE) assessment of Fort Hood. Fort Hood receives many solicitations from renewable energy vendors who are interested in doing projects on site. Based on specific requests from Fort Hood staff so they can better understand these proposals, and the results of PNNL's 2008 RE assessment of Fort Hood, the following resources were examined in this assessment: (1) Municipal solid waste (MSW) for waste-to-energy (WTE); (2) Wind; (3) Landfill gas; (4) Solar photovoltaics (PV); and (5) Shale gas. This report also examines the regulatory issues, development options, and environmental impacts for the promising RE resources, and includes a review of the RE market in Texas.

  9. Investigations of postulated accident sequences for the Fort St. Vrain HTGR

    International Nuclear Information System (INIS)

    Ball, S.J.; Cleveland, J.C.; Conklin, J.C.; Hatta, M.; Sanders, J.P.

    1978-01-01

    The systems analysis capability of the ORNL HTGR Safety analysis research program includes a family of computer codes: an overall plant NSSS simulation (ORTAP), and detailed component codes for investigating core neutronic accidents (CORTAP), shutdown emergency-cooling accidents via a 3-dimensional core model (ORECA), and once-through steam generator transients (BLAST). The component codes can either be run independently or in the overall NSSS code. Verification efforts have consisted primarily of using existing Fort St. Vrain reactor dynamics data to compare against code predictions. Comparisons of core thermal conditions made for reactor scrams from power levels between 30 and 50% showed good agreement. An optimization program was used to rationalize the difference between the predicted and measured refueling region outlet temperatures, and, in general, excellent agreement was attained by adjustment of models and parameters within their uncertainty ranges. However, more work is required to establish a unique and valid set of models

  10. Failure of Fort St. Vrain 347SS control rod drive cables

    International Nuclear Information System (INIS)

    Hellner, R.L.; Thurgood, B.E.

    1990-01-01

    This paper reports on Fort St. Vrain (FSV) which is a high temperature gas cooled reactor. During a scheduled surveillance exercise, one of the control rod drives failed to operate properly. It was found that one of the 347 austenitic stainless cables had failed at several locations and the other had a broken strand. Metallurgical examination determined that the cables failed due to chloride stress corrosion cracking. An investigation into the source of chlorides determined that materials within the core could release chlorides either by water leaching or heat up. To prevent future failures, all the stainless control cables were replaced with cables fabricated from inconel 625

  11. FOUR YEARS OF OPERATIONS AND RESULTS WITH FORTE

    International Nuclear Information System (INIS)

    D. ROUSSEL-DUPRE; P. KLINGNER; L. CARLSON; ET AL

    2001-01-01

    The FORTE (Fast Onboard Recording of Transient Events) satellite was launched on 29 August 1997 and has been in continuous operation since that time. FORTE was placed in a nearly circular, 825-km-altitude, 70 degrees inclination orbit by a Pegasus rocket funded by Air Force Space Test Program. The Department of Energy funded the FORTE satellite, which was designed and built at Los Alamos. FORTE's successful launch and engineered robustness were a result of several years of dedicated work by the joint Los Alamos National Laboratory/Sandia National Laboratory project team, led through mission definition, payload and satellite development, and launch by Dr. Stephen Knox. The project is now led by Dr. Abram Jacobson. FORTE carries a suite of instruments, an optical system and a rf system, for the study of lightning and anthropogenic signals. As a result of this effort, new understandings of lightning events have emerged as well as a more complete understanding of the relationship between optical and rf lightning events. This paper will provide an overview of the FORTE satellite and will discuss the on orbit performance of the subsystems

  12. International working group on gas-cooled reactors. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-15

    The purpose of the meeting was to provide a forum for exchange of information on safety and licensing aspects for gas-cooled reactors in order to provide comprehensive review of the present status and of directions for future applications and development. Contributions were made concerning the operating experience of the Fort St. Vrain (FSV) HTGR Power Plant in the United States of America, the experimental power station Arbeitsgemeinschaft Versuchsreaktor (AVR) in the Federal Republic of Germany, and the CO/sub 2/-cooled reactors in the United Kingdom such as Hunterson B and Hinkley Point B. The experience gained at each of these reactors has proved the high safety potential of Gas-cooled Reactor Power Plants.

  13. Developmental assessment of the Fort St. Vrain version of the Composite HTGR Analysis Program (CHAP-2)

    International Nuclear Information System (INIS)

    Stroh, K.R.

    1980-01-01

    The Composite HTGR Analysis Program (CHAP) consists of a model-independent systems analysis mainframe named LASAN and model-dependent linked code modules, each representing a component, subsystem, or phenomenon of an HTGR plant. The Fort St. Vrain (FSV) version (CHAP-2) includes 21 coded modules that model the neutron kinetics and thermal response of the core; the thermal-hydraulics of the reactor primary coolant system, secondary steam supply system, and balance-of-plant; the actions of the control system and plant protection system; the response of the reactor building; and the relative hazard resulting from fuel particle failure. FSV steady-state and transient plant data are being used to partially verify the component modeling and dynamic smulation techniques used to predict plant response to postulated accident sequences

  14. Gas-cooled reactors

    International Nuclear Information System (INIS)

    Schulten, R.; Trauger, D.B.

    1976-01-01

    Experience to date with operation of high-temperature gas-cooled reactors has been quite favorable. Despite problems in completion of construction and startup, three high-temperature gas-cooled reactor (HTGR) units have operated well. The Windscale Advanced Gas-Cooled Reactor (AGR) in the United Kingdom has had an excellent operating history, and initial operation of commercial AGRs shows them to be satisfactory. The latter reactors provide direct experience in scale-up from the Windscale experiment to fullscale commercial units. The Colorado Fort St. Vrain 330-MWe prototype helium-cooled HTGR is now in the approach-to-power phase while the 300-MWe Pebble Bed THTR prototype in the Federal Republic of Germany is scheduled for completion of construction by late 1978. THTR will be the first nuclear power plant which uses a dry cooling tower. Fuel reprocessing and refabrication have been developed in the laboratory and are now entering a pilot-plant scale development. Several commercial HTGR power station orders were placed in the U.S. prior to 1975 with similar plans for stations in the FRG. However, the combined effects of inflation, reduced electric power demand, regulatory uncertainties, and pricing problems led to cancellation of the 12 reactors which were in various stages of planning, design, and licensing

  15. Bent's Old Fort: Amphibians and Reptiles

    Science.gov (United States)

    Muths, E.

    2008-01-01

    Bent's Old Fort National Historic Site sits along the Arkansas River in the semi-desert prairie of southeastern Colorado. The USGS provided assistance in designing surveys to assess the variety of herpetofauna (amphibians and reptiles) resident at this site. This brochure is the results of those efforts and provides visitors with information on what frogs, toads, snakes and salamanders might be seen and heard at Bent's Old Fort.

  16. Nuclear Safeguards Considerations For The Pebble Bed Modular Reactor (PBMR)

    Energy Technology Data Exchange (ETDEWEB)

    Phillip Casey Durst; David Beddingfield; Brian Boyer; Robert Bean; Michael Collins; Michael Ehinger; David Hanks; David L. Moses; Lee Refalo

    2009-10-01

    High temperature reactors (HTRs) have been considered since the 1940s, and have been constructed and demonstrated in the United Kingdom (Dragon), United States (Peach Bottom and Fort Saint Vrain), Japan (HTTR), Germany (AVR and THTR-300), and have been the subject of conceptual studies in Russia (VGM). The attraction to these reactors is that they can use a variety of reactor fuels, including abundant thorium, which upon reprocessing of the spent fuel can produce fissile U-233. Hence, they could extend the stocks of available uranium, provided the fuel is reprocessed. Another attractive attribute is that HTRs typically operate at a much higher temperature than conventional light water reactors (LWRs), because of the use of pyrolytic carbon and silicon carbide coated (TRISO) fuel particles embedded in ceramic graphite. Rather than simply discharge most of the unused heat from the working fluid in the power plant to the environment, engineers have been designing reactors for 40 years to recover this heat and make it available for district heating or chemical conversion plants. Demonstrating high-temperature nuclear energy conversion was the purpose behind Fort Saint Vrain in the United States, THTR-300 in Germany, HTTR in Japan, and HTR-10 and HTR-PM, being built in China. This resulted in nuclear reactors at least 30% or more thermodynamically efficient than conventional LWRs, especially if the waste heat can be effectively utilized in chemical processing plants. A modern variant of high temperature reactors is the Pebble Bed Modular Reactor (PBMR). Originally developed in the United States and Germany, it is now being redesigned and marketed by the Republic of South Africa and China. The team examined historical high temperature and high temperature gas reactors (HTR and HTGR) and reviewed safeguards considerations for this reactor. The following is a preliminary report on this topic prepared under the ASA-100 Advanced Safeguards Project in support of the NNSA Next

  17. Fort Collins Science Center fiscal year 2010 science accomplishments

    Science.gov (United States)

    Wilson, Juliette T.

    2011-01-01

    The scientists and technical professionals at the U.S. Geological Survey (USGS), Fort Collins Science Center (FORT), apply their diverse ecological, socioeconomic, and technological expertise to investigate complicated ecological problems confronting managers of the Nation's biological resources. FORT works closely with U.S. Department of the Interior (DOI) agency scientists, the academic community, other USGS science centers, and many other partners to provide critical information needed to help answer complex natural-resource management questions. In Fiscal Year 2010 (FY10), FORT's scientific and technical professionals conducted ongoing, expanded, and new research vital to the science needs and management goals of DOI, other Federal and State agencies, and nongovernmental organizations in the areas of aquatic systems and fisheries, climate change, data and information integration and management, invasive species, science support, security and technology, status and trends of biological resources (including the socioeconomic aspects), terrestrial and freshwater ecosystems, and wildlife resources, including threatened and endangered species. This report presents selected FORT science accomplishments for FY10 by the specific USGS mission area or science program with which each task is most closely associated, though there is considerable overlap. The report also includes all FORT publications and other products published in FY10, as well as staff accomplishments, appointments, committee assignments, and invited presentations.

  18. NSU Art Museum Fort Lauderdale | Art Museum in Fort Lauderdale

    Science.gov (United States)

    NSU Art Museum Fort Lauderdale Visit Admissions Hours & Admission Policies & Accessibility Airports Shop & Dine About the Café & Store Store Café Menu Art Exhibitions Currently on View Thursday 2-for-1 specials on wine and craft beer in the Museum Café, and hands-on art projects for all

  19. Uranium and thorium loadings determined by chemical and nondestructive methods in HTGR fuel rods for the Fort St. Vrain Early Validation Irradiation Experiment

    International Nuclear Information System (INIS)

    Angelini, P.; Rushton, J.E.

    1979-01-01

    The Fort St. Vrain Early Validation Irradiation Experiment is an irradiation test of reference and of improved High-Temperature Gas-Cooled Reactor fuels in the Fort St. Vrain Reactor. The irradiation test includes fuel rods fabricated at ORNL on an engineering scale fuel rod molding machine. Fuel rods were nondestructively assayed for 235 U content by a technique based on the detection of prompt-fission neutrons induced by thermal-neutron interrogation and were later chemically assayed by using the modified Davies Gray potentiometric titration method. The chemical analysis of the thorium content was determined by a volumetric titration method. The chemical assay method for uranium was evaluated and the results from the as-molded fuel rods agree with those from: (1) large samples of Triso-coated fissile particles, (2) physical mixtures of the three particle types, and (3) standard solutions to within 0.05%. Standard fuel rods were fabricated in order to evaluate and calibrate the nondestructive assay device. The agreement of the results from calibration methods was within 0.6%. The precision of the nondestructive assay device was established as approximately 0.6% by repeated measurements of standard rods. The precision was comparable to that estimated by Poisson statistics. A relative difference of 0.77 to 1.5% was found between the nondestructive and chemical determinations on the reactor grade fuel rods

  20. FORTE spacecraft vibration mitigation. Final report

    International Nuclear Information System (INIS)

    Maly, J.R.

    1996-02-01

    This report documents work that was performed by CSA Engineering, Inc., for Los Alamos National Laboratory (LANL), to reduce vibrations of the FORTE spacecraft by retrofitting damped structural components into the spacecraft structure. The technical objective of the work was reduction of response at the location of payload components when the structure is subjected to the dynamic loading associated with launch and proto-qualification testing. FORTE is a small satellite that will be placed in orbit in 1996. The structure weighs approximately 425 lb, and is roughly 80 inches high and 40 inches in diameter. It was developed and built by LANL in conjunction with Sandia National Laboratories Albuquerque for the United States Department of Energy. The FORTE primary structure was fabricated primarily with graphite epoxy, using aluminum honeycomb core material for equipment decks and solar panel substrates. Equipment decks were bonded and bolted through aluminum mounting blocks to adjoining structure

  1. Fortælling og fortolkning i Jyske Bank

    DEFF Research Database (Denmark)

    Albrechtsen, Charlotte

    Afhandlingen præsenterer en undersøgelse af et konkret eksempel på storytelling brugt som strategisk ledelses- og kommunikationsredskab i en organisations interne kommunikation. Eksemplet er fortællingen "Slaget ved Vejle", som stammer fra Jyske Bank og udgør under afhandlingens case. De overordn......Afhandlingen præsenterer en undersøgelse af et konkret eksempel på storytelling brugt som strategisk ledelses- og kommunikationsredskab i en organisations interne kommunikation. Eksemplet er fortællingen "Slaget ved Vejle", som stammer fra Jyske Bank og udgør under afhandlingens case. De......, at medarbejderne forholder sig reflekteret, nuanceret og kritisk til den strategiske fortælling, og at der er stor diversitet i deres oplevelser, fortolkninger og vurderinger af fortællingen. Desuden ser afhandlingen nærmere på hvad begrebet "storytelling" dækker over, og hvordan der hidtil er forsket i...

  2. Cancer incidence in Fort Chipewyan, Alberta : 1995-2006

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Y. [Alberta Cancer Board, Edmonton, AB (Canada). Division of Population Health and Information Surveillance

    2009-02-15

    A high number of cases of cholangiocarcinoma, a rare form of bile duct cancer, as well as high rates of other cancers were reported by a physician working in Fort Chipewyan, Alberta in 2006. Concerns were raised by local residents, attributing cancers in their community to environmental contamination from a range of industrial development including the oil sands development, uranium mining and pulp mills. However, an initial review of the Alberta Cancer Registry did not confirm an increased incidence of cancer in Fort Chipewyan. In the summer/fall of 2007, a working group was formed to support the Alberta Cancer Board in doing a cluster investigation based on the guidelines of the United States Centre for Disease Control and Prevention. This report presented an investigation to determine if there was an elevated rate of cholangiocarcinoma in Fort Chipewyan and whether there was an elevated rate of cancers overall in Fort Chipewyan. The report provided background information on the Athabasca oil sands, uranium mining, and Fort Chipewyan as well as previous investigations of cancer incidence in Fort Chipewyan. Study methods were also presented with particular reference to study and comparison populations; cancer classification and inclusion criteria; active case ascertainment and verification; methods of analysis; and ethical approval. Results were also presented. The specific cancers that were discussed were cholangiocarcinoma, leukemia, colon cancer, and cancer in First Nations in Alberta. It was concluded that the observed number of cases of cholangiocarcinoma was within the expected range. 121 refs., 12 tabs., 3 figs., 5 appendices.

  3. Fort St. Vrain hot functional test results

    International Nuclear Information System (INIS)

    Phelps, R.D.

    1974-01-01

    A description is given of Fort St. Vrain hot functional tests performed to evaluate the initial nonnuclear performance of the primary coolant system and the associated effects on the various internal components of the reactor vessel and primary coolant system. The components included the twelve steam generator modules, the four helium circulators, the PCRV thermal barrier and liner coolant system, the helium purification system, and the primary and secondary closures at each of the PCRV penetrations. Additional objectives included analysis of the parallel operation of the four helium circulators and the performance of several circulator start/stop transients under various conditions of primary coolant temperature and pressure. Vibration and acoustical phenomena within the vessel were measured, recorded, and compared to theoretical analyses; a verification of reverse flow in the shutdown loop steam generator during one loop operation was performed; the PCRV was again observed for its structural response to internal pressure; and comparisons were made relative to data recorded during the initial pressure test completed in July 1971. (U.S.)

  4. Fort St. Vrain graphite site mechanical separation concept selection

    International Nuclear Information System (INIS)

    Berry, S.M.

    1993-09-01

    One of the alternatives to the disposal of the Fort St. Vrain (FSV) reactor spent nuclear fuel involves the separation of the fuel rods composed of compacts from the graphite fuel block assembly. After the separation of these two components, the empty graphite fuel blocks would be disposed of as a low level waste (provided the appropriate requirements are met) and the fuel compacts would be treated as high level waste material. This report deals with the mechanical separation aspects concerning physical disassembly of the FSV graphite fuel element into the empty graphite fuel blocks and fuel compacts. This report recommends that a drilling technique is the preferred choice for accessing the, fuel channel holes and that each hole is drilled separately. This report does not cover any techniques or methods to separate the triso fuel particles from the graphite matrix of the fuel compacts

  5. Fort Collins Science Center-Fiscal year 2009 science accomplishments

    Science.gov (United States)

    Wilson, Juliette T.

    2010-01-01

    Public land and natural resource managers in the United States are confronted with increasingly complex decisions that have important ramifications for both ecological and human systems. The scientists and technical professionals at the U.S. Geological Survey Fort Collins Science Center?many of whom are at the forefront of their fields?possess a unique blend of ecological, socioeconomic, and technological expertise. Because of this diverse talent, Fort Collins Science Center staff are able to apply a systems approach to investigating complicated ecological problems in a way that helps answer critical management questions. In addition, the Fort Collins Science Center has a long record of working closely with the academic community through cooperative agreements and other collaborations. The Fort Collins Science Center is deeply engaged with other U.S. Geological Survey science centers and partners throughout the Department of the Interior. As a regular practice, we incorporate the expertise of these partners in providing a full complement of ?the right people? to effectively tackle the multifaceted research problems of today's resource-management world. In Fiscal Year 2009, the Fort Collins Science Center's scientific and technical professionals continued research vital to Department of the Interior's science and management needs. Fort Collins Science Center work also supported the science needs of other Federal and State agencies as well as non-government organizations. Specifically, Fort Collins Science Center research and technical assistance focused on client and partner needs and goals in the areas of biological information management and delivery, enterprise information, fisheries and aquatic systems, invasive species, status and trends of biological resources (including human dimensions), terrestrial ecosystems, and wildlife resources. In the process, Fort Collins Science Center science addressed natural-science information needs identified in the U

  6. Undervisning mellem fortælling og feedback

    DEFF Research Database (Denmark)

    Andersen, Kirsten Margrethe

    2016-01-01

    Feedback gør det muligt for den enkelte at forstå, hvordan jeg kan blive bedre til det, jeg er ved at lære. Fortællinger gør det muligt for den enkelte at udvide horisonten og derved komme til en forståelse af, hvilke mulige perspektiver der er for at forholde sig til den verden, som fortællingen...

  7. ШЕВЧЕНКО В КОЛІ КЛАСИКІВ: НОВІ ПІДХОДИ ДО ВИВЧЕННЯ ТВОРЧОСТІ ВЕЛИКОГО УКРАЇНСЬКОГО ПОЕТА (НА ОСНОВІ ПУБЛІКАЦІЙ М. ЛАСЛО-КУЦЮК / SHEVCHENKO IN THE CIRCLE OF CLASSICS: NEW APPROACH TO THE STUDY OF GREAT UKRAINIAN POET’S WORKS (BASED ON PUBLICATIONS OF M. LASLO-KUTSYUK

    Directory of Open Access Journals (Sweden)

    Ірина КАІЗЕР

    2017-09-01

    Full Text Available Каизер И. Шевченко в кругу классиков: новые подходы к изучению творчества великого украинского поэта (основываясь на публикациях М. Ласло-Куцюк. В статье исследуются некоторые новые подходы к изучению творчества Т. Шевченко, основываясь на публикациях румынского литературоведа М. Ласло -Куцюк. В частности, сущность великого украинского поэта ученая раскрывает через его взаимоотношения с рядом украинских писателей и общественных деятелей, отношения к их творчеству и понимания их политической ориентации. Ключевые слова: психотип личности, соционика, Шевченко, Сковорода, Костомаров, Кулиш. Kaizer I. Shevchenko in the Circle of Slassics: New Approach to the Study of the Great Ukrainian Poet’s Works (Based on Publications of M. Laslo-Kutsyuk. The basis of the research were made by the literary critiqal articles of the Romanian Academic M. Laszlo-Kutsyuk about Shevchenko and other prominent Ukrainian writers and figures, and also the monograph "Shevchenko`s works on the background of his age", "Gods of light and gods of darkness," "The key to the belletristic". In the article "Scovoroda and Shevchenko" Romanian researcher discovers that Kobzar condemned the language the wandering philosopher used. However he shared Scovoroda`s philosophical views,especailly he was impressed by the criticism of Russian feudal system.We also can see the influence of Scovoroda`s works on Shevchenko`s works, "Vsyakomu gorodu nrav y prava" on the prologue to the poem "Dream". The

  8. Structural remains at the early mediaeval fort at Raibania, Orissa

    Directory of Open Access Journals (Sweden)

    Bratati Sen

    2013-11-01

    Full Text Available The fortifications of mediaeval India occupy an eminent position in the history of military architecture. The present paper deals with the preliminary study of the structural remains at the early mediaeval fort at Raibania in the district of Balasore in Orissa. The fort was built of stone very loosely kept together. The three-walled fortification interspersed by two consecutive moats, a feature evidenced at Raibania, which is unparallel in the history of ancient and mediaeval forts and fortifications in India. Several other structures like the Jay-Chandi Temple Complex, a huge well, numerous tanks and remains of an ancient bridge add to the uniqueness of the Fort in the entire eastern region.

  9. Le Fort I Maxillary Advancement Using Distraction Osteogenesis

    Science.gov (United States)

    Combs, Patrick D.; Harshbarger, Raymond J.

    2014-01-01

    Treatment of maxillary hypoplasia has traditionally involved conventional Le Fort I osteotomies and advancement. Advancements of greater than 10 mm risk significant relapse. This risk is greater in the cleft lip and palate population, whose anatomy and soft tissue scarring from prior procedures contributes to instability of conventional maxillary advancement. Le Fort I advancement with distraction osteogenesis has emerged as viable, stable treatment modality correction of severe maxillary hypoplasia in cleft, syndromic, and noncleft patients. In this article, the authors provide a review of current data and recommendations concerning Le Fort I advancement with distraction osteogenesis. In addition, they outline their technique for treating severe maxillary hypoplasia with distraction osteogenesis using internal devices. PMID:25383054

  10. Medium-size high-temperature gas-cooled reactor

    International Nuclear Information System (INIS)

    Peinado, C.O.; Koutz, S.L.

    1980-08-01

    This report summarizes high-temperature gas-cooled reactor (HTGR) experience for the 40-MW(e) Peach Bottom Nuclear Generating Station of Philadelphia Electric Company and the 330-MW(e) Fort St. Vrain Nuclear Generating Station of the Public Service Company of Colorado. Both reactors are graphite moderated and helium cooled, operating at approx. 760 0 C (1400 0 F) and using the uranium/thorium fuel cycle. The plants have demonstrated the inherent safety characteristics, the low activation of components, and the high efficiency associated with the HTGR concept. This experience has been translated into the conceptual design of a medium-sized 1170-MW(t) HTGR for generation of 450 MW of electric power. The concept incorporates inherent HTGR safety characteristics [a multiply redundant prestressed concrete reactor vessel (PCRV), a graphite core, and an inert single-phase coolant] and engineered safety features

  11. Case Study: Fort Mill High School--A Culture of Continuous Improvement

    Science.gov (United States)

    Southern Regional Education Board (SREB), 2014

    2014-01-01

    This is the latest in a series of case studies highlighting best practices High Schools That Work (HSTW) network schools and districts are implementing to prepare students better for further studies and careers. Fort Mill High School is in Fort Mill, South Carolina, an outlying suburb of Charlotte, North Carolina. Fort Mill links high quality…

  12. Hydrologic Analysis of Fort Leonard Wood, Missouri

    Science.gov (United States)

    2015-08-01

    drainage areas are different, hydrological analysis will be conducted on the two basins individually. The results of the two analyses will be combined to...ER D C TR -1 5- 4 Environmental Quality and Installations Hydrologic Analysis of Fort Leonard Wood, Missouri En gi ne er R es ea rc h...Environmental Quality and Installations ERDC TR-15-4 August 2015 Hydrologic Analysis of Fort Leonard Wood, Missouri Michael L. Follum, Darla C. McVan

  13. Fortællerfiktionen

    DEFF Research Database (Denmark)

    Reitan, Rolf

    Bogen er en kritisk nærlæsning af Gérard Genettes Discours du récit og viser, hvorden den franske teoretiker løser og forenkler en række centrale problemer i traditionel fortælleteori, idet han uudtalt forudsætter et fiktionsbegreb, som han eksplicit afviser som narratologisk relevant. Det...

  14. Fort Valley's early scientists: A legacy of distinction

    Science.gov (United States)

    Andrew J. Sanchez Meador; Susan D. Olberding

    2008-01-01

    When the Riordan brothers of Flagstaff, Arizona, asked Gifford Pinchot to determine why there was a deficit in ponderosa pine seedlings, neither party understood the historical significance of what they were setting in motion for the field of forest research. The direct result of that professional favor was the establishment of the Fort Valley Experiment Station (Fort...

  15. Neutron flux distribution measurement in the Fort St. Vrain initial core (results of Fort St. Vrain start-up test A-7)

    International Nuclear Information System (INIS)

    Marshall, A.C.; Brown, J.R.

    1975-01-01

    A description is given of a test to measure the axial flux distribution at several radial locations in the Fort St. Vrain core representing unrodded, rodded, and partially rodded regions. The measurements were intended to verify the calculational accuracy of the three-dimensional calculational model used to compute axial power distributions for the Fort St. Vrain core. (U.S.)

  16. Fuel-Cycle and Nuclear Material Disposition Issues Associated with High-Temperature Gas Reactors

    International Nuclear Information System (INIS)

    Shropshire, D.E.; Herring, J.S.

    2004-01-01

    The objective of this paper is to facilitate a better understanding of the fuel-cycle and nuclear material disposition issues associated with high-temperature gas reactors (HTGRs). This paper reviews the nuclear fuel cycles supporting early and present day gas reactors, and identifies challenges for the advanced fuel cycles and waste management systems supporting the next generation of HTGRs, including the Very High Temperature Reactor, which is under development in the Generation IV Program. The earliest gas-cooled reactors were the carbon dioxide (CO2)-cooled reactors. Historical experience is available from over 1,000 reactor-years of operation from 52 electricity-generating, CO2-cooled reactor plants that were placed in operation worldwide. Following the CO2 reactor development, seven HTGR plants were built and operated. The HTGR came about from the combination of helium coolant and graphite moderator. Helium was used instead of air or CO2 as the coolant. The helium gas has a significant technical base due to the experience gained in the United States from the 40-MWe Peach Bottom and 330-MWe Fort St. Vrain reactors designed by General Atomics. Germany also built and operated the 15-MWe Arbeitsgemeinschaft Versuchsreaktor (AVR) and the 300-MWe Thorium High-Temperature Reactor (THTR) power plants. The AVR, THTR, Peach Bottom and Fort St. Vrain all used fuel containing thorium in various forms (i.e., carbides, oxides, thorium particles) and mixtures with highly enriched uranium. The operational experience gained from these early gas reactors can be applied to the next generation of nuclear power systems. HTGR systems are being developed in South Africa, China, Japan, the United States, and Russia. Elements of the HTGR system evaluated included fuel demands on uranium ore mining and milling, conversion, enrichment services, and fuel fabrication; fuel management in-core; spent fuel characteristics affecting fuel recycling and refabrication, fuel handling, interim

  17. Anatomy of the Le Fort I segment: Are arterial variations a potential risk factor for avascular bone necrosis in Le Fort I osteotomies?

    Science.gov (United States)

    Bruneder, Simon; Wallner, Jürgen; Weiglein, Andreas; Kmečová, Ĺudmila; Egger, Jan; Pilsl, Ulrike; Zemann, Wolfgang

    2018-05-02

    Osteotomies of the Le Fort I segment are routine operations with low complication rates. Ischemic complications are rare, but can have severe consequences that may lead to avascular bone necrosis of the Le Fort I segment. Therefore the aim of this study was to investigate the blood supply and special arterial variants of the Le Fort I segment responsible for arterial hypoperfusion or ischemic avascular necrosis after surgery. The arterial anatomy of the Le Fort I segment's blood supply using 30 halved human cadaver head specimens was analyzed after complete dissection until the submicroscopic level. In all specimens the arterial variants of the Le Fort I segment and also the arterial diameters measured at two points were evaluated. The typical known vascularization pattern was apparent in 90% of all specimens, in which the ascending palatine (D1: 1,2 mm ± 0,34 mm; D2: 0,8 mm ± 0,34 mm) and ascending pharyngeal artery (D1: 1,3 mm ± 0,58 mm; D2: avascular segment necrosis after surgery. An individualized operation plan may prevent ischemic complications in at-risk patients. Copyright © 2018 European Association for Cranio-Maxillo-Facial Surgery. Published by Elsevier Ltd. All rights reserved.

  18. 78 FR 17087 - Special Local Regulation; New River Raft Race, New River; Fort Lauderdale, FL

    Science.gov (United States)

    2013-03-20

    ...-AA08 Special Local Regulation; New River Raft Race, New River; Fort Lauderdale, FL AGENCY: Coast Guard... on the New River in Fort Lauderdale, Florida during the Rotary Club of Fort Lauderdale New River Raft... States during the Rotary Club of Fort Lauderdale New River Raft Race. On March 23, 2013, Fort Lauderdale...

  19. 40 CFR 81.63 - Metropolitan Fort Smith Interstate Air Quality Control Region.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 17 2010-07-01 2010-07-01 false Metropolitan Fort Smith Interstate Air... Air Quality Control Regions § 81.63 Metropolitan Fort Smith Interstate Air Quality Control Region. The Metropolitan Fort Smith Interstate Air Quality Control Region (Arkansas-Oklahoma) has been revised to consist...

  20. How Do Le Fort-Type Fractures Present in a Pediatric Cohort?

    Science.gov (United States)

    Macmillan, Alexandra; Lopez, Joseph; Luck, J D; Faateh, Muhammad; Manson, Paul; Dorafshar, Amir H

    2018-05-01

    Le Fort-type fractures are very rare in children, and there is a paucity of literature presenting their frequency and characteristics. The purpose of this study was to determine the etiology, frequency, and fracture patterns of children with severe facial trauma associated with pterygoid plate fractures in a pediatric cohort. We performed a retrospective cohort study of all children aged younger than 16 years with pterygoid plate and facial fractures who presented to our institute between 1990 and 2010. Patient charts and radiologic records were reviewed for demographic and fracture characteristics. Patients were categorized into 2 groups as per facial fracture pattern: non-Le Fort-type fractures (group A) and Le Fort-type fractures (group B). Other variables including dentition age, frontal sinus development, mechanism of injury, injury severity, and concomitant injuries were recorded. Univariate methods were used to compare groups. We identified 24 children; 25% were girls, and 20.8% were of nonwhite race. Most presented with Le Fort-type fracture patterns (group B, 66.7%). Age was significantly different between group A and group B (mean, 5.9 years and 9.9 years, respectively; P = .009). No significant differences in Injury Severity Score, rate of operative repair, and length of stay were found between groups. Most children with severe facial fractures and pterygoid plate fractures presented with Le Fort-type fracture patterns in our cohort. The mean age of children with Le Fort-type fractures was greater than in those with non-Le Fort-type patterns. However, Le Fort-type fractures did occur in younger children with deciduous and mixed dentition. Copyright © 2017 American Association of Oral and Maxillofacial Surgeons. Published by Elsevier Inc. All rights reserved.

  1. Le Fort I Maxillary Advancement Using Distraction Osteogenesis

    OpenAIRE

    Combs, Patrick D.; Harshbarger, Raymond J.

    2014-01-01

    Treatment of maxillary hypoplasia has traditionally involved conventional Le Fort I osteotomies and advancement. Advancements of greater than 10 mm risk significant relapse. This risk is greater in the cleft lip and palate population, whose anatomy and soft tissue scarring from prior procedures contributes to instability of conventional maxillary advancement. Le Fort I advancement with distraction osteogenesis has emerged as viable, stable treatment modality correction of severe maxillary hyp...

  2. An aerial radiological survey of the Fort Calhoun Nuclear Power Plant and surrounding area, Fort Calhoun, Nebraska

    International Nuclear Information System (INIS)

    1994-05-01

    An aerial radiological survey was conducted over the Fort Calhoun Nuclear Power Plant in Fort Calhoun, Nebraska, during the period June 19 through June 28, 1993. The survey was conducted at an altitude of 150 feet (46 meters) over a 25-square-mile (65-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Fort Calhoun Nuclear Power Plant and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 12 microroentgens per hour and were attributed to naturally-occurring uranium, thorium, and potassium. The aerial data were compared to ground-based benchmark exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system. A previous survey was conducted on August 9 and 10, 1972, before the plant began operation. Exposure rates measured in both surveys were consistent with normal terrestrial background

  3. Fort Carson Wind Resource Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Robichaud, R.

    2012-10-01

    This report focuses on the wind resource assessment, the estimated energy production of wind turbines, and economic potential of a wind turbine project on a ridge in the southeastern portion of the Fort Carson Army base.

  4. Renewable Energy Opportunities at Fort Sill, Oklahoma

    Energy Technology Data Exchange (ETDEWEB)

    Boyd, Brian K.; Hand, James R.; Horner, Jacob A.; Orrell, Alice C.; Russo, Bryan J.; Weimar, Mark R.; Nesse, Ronald J.

    2011-03-31

    This document provides an overview of renewable resource potential at Fort Sill, based primarily upon analysis of secondary data sources supplemented with limited on-site evaluations. This effort focuses on grid-connected generation of electricity from renewable energy sources and on ground source heat pumps for heating and cooling buildings. The effort was funded by the U.S. Army Installation Management Command (IMCOM) as follow-on to the 2005 Department of Defense (DoD) Renewables Assessment. The site visit to Fort Sill took place on June 10, 2010.

  5. Renewable Energy Opportunities at Fort Polk, Louisiana

    Energy Technology Data Exchange (ETDEWEB)

    Solana, Amy E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Boyd, Brian K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Horner, Jacob A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gorrissen, Willy J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Orrell, Alice C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Weimar, Mark R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hand, James R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Russo, Bryan J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Williamson, Jennifer L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2010-11-17

    This document provides an overview of renewable resource potential at Fort Polk, based primarily upon analysis of secondary data sources supplemented with limited on-site evaluations. This effort focuses on grid-connected generation of electricity from renewable energy sources and also on ground source heat pumps for heating and cooling buildings. The effort was funded by the U.S. Army Installation Management Command (IMCOM) as follow-on to the 2005 Department of Defense (DoD) Renewables Assessment. The site visit to Fort Polk took place on February 16, 2010.

  6. Fort Independence: An Eighteenth-Century Frontier Homesite and Militia Post in South Carolina.

    Science.gov (United States)

    1982-12-01

    included in this instance as a condiment , but it could also indicate that the Fort Independence garrison was familiar with the strategy employed by the Fort...archeological investigation of Fort Charlotte, McCormick County, South Carolina. Notebook, Institute of Archeology and Anthropology, University of South

  7. ТАРАС ШЕВЧЕНКО: ІСТОРІЯ ХВОРОБИ, ПРИЧИНА СМЕРТІ / TARAS SHEVCHENKO: THE CASE HISTORY, THE CAUSE OF THE DEATH

    Directory of Open Access Journals (Sweden)

    Петро ЛЯШУК

    2016-09-01

    Full Text Available Ляшук П., Ляшук Р. Тарас Шевченко: история болезни, причина смерти. Представлена история болезни и версия об непосредственной причине смерти Т.Г. Шевченка (ревматический порок сердца с тотальной сердечной недостаточностью, основанные на его публикациях о состоянии здоровья, писем, воспоминаний современников, архивных материалов, а также аналитических медицинских исследований проблемы его ревматического процесса. Ключевые слова: ревматизм, порок сердца, отек легких, ссылка.Liashuk P., Liashuk R. Taras Shevchenko: The Case History, The Cause of The Death. The case history and the version of the immediate cause of the death of Taras Shevchenko (rheumatic heart disease with total heart failure, is based on his publications on health, letters, memoirs of contemporaries, archival materials, as well as on analytical medical researches of the problem of his rheumatic process. As a young Shevchenko was first seriously ill. By the time he was still a slave, assistant St. Petersburg artist. Described symptoms can be seen as scarlet fever, the pathogen which is relevant to the development of rheumatic fever that came over further confirmation of the disease with damage to the heart and joints. Being a poet in exile in Orenburg province was particularly difficult. The heavy life added rheumatism, skorbut, eye disease. Release from 10 years of exile did not end troubles Shevchenko. Along the way, he caught a cold. Peterburskyy climate hnityv his life remained unsettled. In autumn 1860 the disease has increased, the growth that is developed heart failure. We can

  8. Radiolytic reactions in the coolant of helium cooled reactors

    International Nuclear Information System (INIS)

    Tingey, G.L.; Morgan, W.C.

    1975-01-01

    The success of helium cooled reactors is dependent upon the ability to prevent significant reaction between the coolant and the other components in the reactor primary circuit. Since the thermal reaction of graphite with oxidizing gases is rapid at temperatures of interest, the thermal reactions are limited primarily by the concentration of impurity gases in the helium coolant. On the other hand, the rates of radiolytic reactions in helium are shown to be independent of reactive gas concentration until that concentration reaches a very low level. Calculated steady-state concentrations of reactive species in the reactor coolant and core burnoff rates are presented for current U. S. designed, helium cooled reactors. Since precise base data are not currently available for radiolytic rates of some reactions and thermal reaction rate data are often variable, the accuracy of the predicted gas composition is being compared with the actual gas compositions measured during startup tests of the Fort Saint Vrain high temperature gas-cooled reactor. The current status of these confirmatory tests is discussed. 12 references

  9. En fascinerende fortælling om det 20. århundredes musik

    DEFF Research Database (Denmark)

    Bonde, Lars Ole

    2011-01-01

    Anmeldelse af Karl Aage Rasmussen: Musik i det tyvende århundrede: En fortælling. Gyldendal 2011.......Anmeldelse af Karl Aage Rasmussen: Musik i det tyvende århundrede: En fortælling. Gyldendal 2011....

  10. Analysis of Delayed Sea Breeze Onset for Fort Ord Prescribed Burning Operations

    Science.gov (United States)

    2015-12-01

    DELAYED SEA BREEZE ONSET FOR FORT ORD PRESCRIBED BURNING OPERATIONS by Dustin D. Hocking December 2015 Thesis Advisor: Wendell Nuss Second...AND DATES COVERED Master’s thesis 4. TITLE AND SUBTITLE ANALYSIS OF DELAYED SEA BREEZE ONSET FOR FORT ORD PRESCRIBED BURNING OPERATIONS 5...release; distribution is unlimited 12b. DISTRIBUTION CODE 13. ABSTRACT (maximum 200 words) The U.S. Army conducts prescribed burns at Fort Ord

  11. Fort Peck-Wolf Point transmission line project, Montana

    International Nuclear Information System (INIS)

    1992-01-01

    The primary objective of the project is to replace the existing 36-mile Fort Peck-Wolf Point transmission line which has reached the end of its useful service life. Presently, the overall condition of this existing section of the 47-year-old line is poor. Frequent repairs have been required because of the absence of overhead ground wires. The continued maintenance of the line will become more expensive and customer interruptions will persist because of the damage due to lightning. The expense of replacing shell rotted poles, and the concern for the safety of the maintenance personnel because of hazards caused by severe shell rot are also of primary importance. The operational and maintenance problems coupled with power system simulation studies, demonstrate the need for improvements to the Wolf Point area to serve area loads. Western's Wolf Point Substation is an important point of interconnection for the power output from the Fort Peck Dam to area loads as far away as Williston, North Dakota. The proposed transmission line replacement would assure that there will continue to be reliable transmission capacity available to serve area electrical loads, as well as provide a reliable second high-voltage transmission path from the Fort Peck generation to back-up a loss of the Fort Peck-Wolf Point 115-kV Line No. 1

  12. Targeting Net Zero Energy at Fort Carson: Assessment and Recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, K.; Markel, T.; Simpson, M.; Leahey, J.; Rockenbaugh, C.; Lisell, L.; Burman, K.; Singer, M.

    2011-10-01

    The U.S. Army's Fort Carson installation was selected to serve as a prototype for net zero energy assessment and planning. NREL performed the comprehensive assessment to appraise the potential of Fort Carson to achieve net zero energy status through energy efficiency, renewable energy, and electric vehicle integration. This report summarizes the results of the assessment and provides energy recommendations. This study is part of a larger cross-laboratory effort that also includes an assessment of renewable opportunities at seven other DoD Front Range installations, a microgrid design for Fort Carson critical loads and an assessment of regulatory and market-based barriers to a regional secure smart grid.

  13. Morphological anomalies in two Lutzomyia (Psathyromyia) shannoni (Diptera: Psychodidae: Phlebotominae) specimens collected from Fort Rucker, Alabama, and Fort Campbell, Kentucky.

    Science.gov (United States)

    Florin, David A; Lawyer, Phillip; Rowton, Edgar; Schultz, George; Wilkerson, Richard; Davies, Stephen J; Lipnick, Robert; Keep, Lisa

    2010-09-01

    This report describes two male specimens of the sand fly species Lutzomyia shannoni (Dyar) (Diptera: Psychodidae: Phlebotominae) collected at Fort Rucker, AL, and Fort Campbell, KY, in dry ice-baited light traps during September 2005. The specimens were observed to have anomalies to the number of spines on the gonostyli. The taxonomic keys of Young and Perkins (Mosq. News 44: 263-285; 1984) use the number of spines on the gonostylus in the first couplet to differentiate two major groupings of North American sand flies. The two anomalous specimens were identified as L. shannoni based on the following criteria: (1) both specimens possess antennal ascoids with long, distinct proximal spurs (a near diagnostic character of L. shannoni in North America), (2) the sequences of the partial cytochrome c oxidase subunit 1 gene from both specimens indicated L. shannoni, and (3) the sequences of the internal transcribed spacer 2 molecular marker from both specimens indicated L. shannoni. The anomalous features are fundamentally different from each other as the Fort Rucker specimen possesses a fifth spine (basally located) on just one gonostylus, whereas the Fort Campbell specimen possesses five spines (extra spines subterminally located) on both gonostyli. Because the gonostyli are part of the external male genitalia, anomalies in the number of spines on the gonostyli may have serious biological consequences, such as reduced reproductive success, for the possessors. These anomalies are of taxonomic interest as the specimens could easily have been misidentified using available morphological keys.

  14. 76 FR 68625 - Establishment of the Fort Monroe National Monument

    Science.gov (United States)

    2011-11-07

    ... period of slavery in the colonies and, later, this Nation. Two hundred and forty-two years later, Fort... 1863. Thus, Old Point Comfort marks both the beginning and end of slavery in our Nation. The Fort... North Beach area lies the only undeveloped shoreline remaining on Old Point Comfort, providing modern...

  15. Requirements of, and operating experience with, gas analyses on high temperature reactors

    International Nuclear Information System (INIS)

    Nieder, R.

    1982-06-01

    Impurities in the helium coolant of the primary coolant circuit of HTGR's are mainly due to ingress of air or water, occasionally oil. Typical concentrations are given of H 2 O, H 2 , CO 2 , CO, N 2 , CH 4 and Ar in the AVR, Dragon, Peach Bottom and Fort St. Vrain reactors. A characteristic is presented of measuring devices for measuring non-active impurities in helium; measuring methods are described and a list is given of required and actual detection limits. Also given are concentrations of solid fission and activation products and tritium in the primary circuit of the AVR reactor

  16. State of development of high temperature gas-cooled reactors in foreign countries

    International Nuclear Information System (INIS)

    Sudo, Yukio

    1990-01-01

    Emphasis has been placed in the development of high temperature gas-cooled reactors on high thermal efficiency as power reactors and the reactor from which nuclear heat can be utilized. In U.K., as the international project 'Dragon Project', the experimental Dragon reactor for research use with 20 MWt output and exit coolant temperature 750 deg C was constructed, and operated till 1976. Coated fuel particles were developed. In West Germany, the experimental power reactor AVR with 46 MWt and 15 MWe output was operated till 1988. The prototype power reactor THTR-300 with 300 MWe output and 750 deg C exit temperature is in commercial operation. In USA, the experimental power reactor Peach Bottom reactor with 40 MWe output and 728 deg C exit temperature was operated till 1974. The prototype Fort Saint Vrain power reactor with 330 MWe output and 782 deg C exit temperature was operated till 1989. In USSR, the modular VGM with 200 MWh output is at the planning stage. Also in China, high temperature gas-cooled reactors are at the design stage. Switzerland has taken part in various international projects. (K.I.)

  17. Inventory of Forts in Indonesia

    Science.gov (United States)

    Rinandi, N.; Suryaningsih, F.

    2015-08-01

    The great archipelago in Indonesia with its wealthy and various nature, the products and commodities of tropic agriculture and the rich soil, was through the centuries a region of interest for other countries all over the world. For several reasons some of these countries came to Indonesia to establish their existence and tried to monopolize the trading. These countries such as the Portuguese, the Spanish, the Dutch and the British built strengthened trade stations which later became forts all over Indonesia to defend their interest. The archipelago of Indonesia possesses a great number of fortification-works as legacies of native rulers and those which were built by European trading companies and later became colonial powers in the 16th to the 19th centuries. These legacies include those specific structures built as a defence system during pre and within the period of World War II. These fortresses are nowadaysvaluable subjects, because they might be considered as shared heritage among these countries and Indonesia. It's important to develop a vision to preserve these particular subjects of heritage, because they are an interesting part of the Indonesian history and its cultural treasures. The Government of the Republic of Indonesia has national program to compile a comprehensive documentation of the existing condition of these various types of forts as cultural heritage. The result of the 3 years project was a comprehensive 442 forts database in Indonesia, which will be very valuable to the implementation of legal protection, preservation matters and adaptive re-use in the future.

  18. Cranial nerve injury after Le Fort I osteotomy.

    Science.gov (United States)

    Kim, J-W; Chin, B-R; Park, H-S; Lee, S-H; Kwon, T-G

    2011-03-01

    A Le Fort I osteotomy is widely used to correct dentofacial deformity because it is a safe and reliable surgical method. Although rare, various complications have been reported in relation to pterygomaxillary separation. Cranial nerve damage is one of the serious complications that can occur after Le Fort I osteotomy. In this report, a 19-year-old man with unilateral cleft lip and palate underwent surgery to correct maxillary hypoplasia, asymmetry and mandibular prognathism. After the Le Fort I maxillary osteotomy, the patient showed multiple cranial nerve damage; an impairment of outward movement of the eye (abducens nerve), decreased vision (optic nerve), and paraesthesia of the frontal and upper cheek area (ophthalmic and maxillary nerve). The damage to the cranial nerve was related to an unexpected sphenoid bone fracture and subsequent trauma in the cavernous sinus during the pterygomaxillary osteotomy. Copyright © 2010 International Association of Oral and Maxillofacial Surgeons. Published by Elsevier Ltd. All rights reserved.

  19. Fort Valley's early scientists: A legacy of distinction (P-53)

    Science.gov (United States)

    Andrew J. Sanchez Meador; Susan D. Olberding

    2008-01-01

    When the Riordan brothers of Flagstaff, Arizona asked Gifford Pinchot to determine why there was a deficit in ponderosa pine seedlings, neither party understood the historical significance of what they were setting in motion for the field of forest research. The direct result of that professional favor was the establishment of the Fort Valley Experiment Station (Fort...

  20. Renewable Energy Opportunities at Fort Campbell, Tennessee/Kentucky

    Energy Technology Data Exchange (ETDEWEB)

    Hand, James R.; Horner, Jacob A.; Kora, Angela R.; Orrell, Alice C.; Russo, Bryan J.; Weimar, Mark R.; Nesse, Ronald J.

    2011-03-31

    This document provides an overview of renewable resource potential at Fort Campbell, based primarily upon analysis of secondary data sources supplemented with limited on-site evaluations. This effort focuses on grid-connected generation of electricity from renewable energy sources and also on ground source heat pumps for heating and cooling buildings. The effort was funded by the U.S. Army Installation Management Command (IMCOM) as follow-on to the 2005 Department of Defense (DoD) Renewables Assessment. The site visit to Fort Campbell took place on June 10, 2010.

  1. Renewable Energy Opportunities at Fort Drum, New York

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Scott A.; Orrell, Alice C.; Solana, Amy E.; Williamson, Jennifer L.; Hand, James R.; Russo, Bryan J.; Weimar, Mark R.; Rowley, Steven; Nesse, Ronald J.

    2010-10-20

    This document provides an overview of renewable resource potential at Fort Drum, based primarily upon analysis of secondary data sources supplemented with limited on-site evaluations. This effort focuses on grid-connected generation of electricity from renewable energy sources and also on ground source heat pumps for heating and cooling buildings. The effort was funded by the U.S. Army Installation Management Command (IMCOM) as follow-on to the 2005 Department of Defense (DoD) Renewables Assessment. The site visit to Fort Drum took place on May 4 and 5, 2010.

  2. Potentialities of high temperature reactors (HTR)

    International Nuclear Information System (INIS)

    Hittner, D.

    2001-01-01

    This articles reviews the assets of high temperature reactors concerning the amount of radioactive wastes produced. 2 factors favors HTR-type reactors: high thermal efficiency and high burn-ups. The high thermal efficiency is due to the high temperature of the coolant, in the case of the GT-MHR project (a cooperation between General Atomic, Minatom, Framatome, and Fuji Electric) designed to burn Russian military plutonium, the expected yield will be 47% with an outlet helium temperature of 850 Celsius degrees. The high temperature of the coolant favors a lot of uses of the heat generated by the reactor: urban heating, chemical processes, or desalination of sea water.The use of a HTR-type reactor in a co-generating way can value up to 90% of the energy produced. The high burn-up is due to the technology of HTR-type fuel that is based on encapsulation of fuel balls with heat-resisting materials. The nuclear fuel of Fort-Saint-Vrain unit (Usa) has reached values of burn-ups from 100.000 to 120.000 MWj/t. It is shown that the quantity of unloaded spent fuel can be divided by 4 for the same amount of electricity produced, in the case of the GT-MHR project in comparison with a light water reactor. (A.C.)

  3. Developmental assessment of the Fort St. Vrain version of the composite HTGR analysis program (CHAP-2)

    International Nuclear Information System (INIS)

    Stroh, K.R.

    1981-01-01

    The Composite HTGR Analysis Program (CHAP) consists of a model-independent systems analysis mainframe named LASAN and model-dependent linked code modules, each representing a component, subsystem, or phenomenon of an HTGR plant. The Fort St. Vrain version (CHAP-2) includes 21 coded modules that model the neutron kinetics and thermal response of the core; the thermal-hydraulics of the reactor primary coolant system, secondary steam supply system, and balance-of-plant; the actions of the control system and plant protection system; the response of the reactor building; and the relative hazard resulting from fuel particle failure. FSV steady-state and transient plant data are being used to partially verify the component modeling and dynamic simulation techniques used to predict plant response to postulated accident sequences. Results of these preliminary validation efforts are presented showing good agreement between code output and plant data for the portions of the code that have been tested. Plans for further development and assessment as well as application of the validated code are discussed. (author)

  4. Microgrid Enabled Distributed Energy Solutions (MEDES) Fort Bliss Military Reservation

    Science.gov (United States)

    2014-02-01

    FINAL REPORT Microgrid Enabled Distributed Energy Solutions (MEDES) Fort Bliss Military Reservation ESTCP Project EW-201140 FEBRUARY...TITLE AND SUBTITLE Microgrid Enabled Distributed Energy Solutions (MEDES) 5a. CONTRACT NUMBER W912HQ-11-C-0082 Fort Bliss, Texas...Lockheed Martin’s Intelligent Microgrid Solution can provide more energy security while also lowering electric utility costs and greenhouse gas emissions

  5. Structural remains at the early mediaeval fort at Raibania, Orissa

    OpenAIRE

    Sen, Bratati

    2013-01-01

    The fortifications of mediaeval India occupy an eminent position in the history of military architecture. The present paper deals with the preliminary study of the structural remains at the early mediaeval fort at Raibania in the district of Balasore in Orissa. The fort was built of stone very loosely kept together. The three-walled fortification interspersed by two consecutive moats, a feature evidenced at Raibania, w...

  6. Black Swan Event Assessment for Fort Leonard Wood, Missouri

    Science.gov (United States)

    2016-03-01

    ER D C/ CE RL S R- 16 -1 Net Zero Planning for Fort Leonard Wood Black Swan Event Assessment for Fort Leonard Wood, Missouri Co ns...search for other technical reports published by ERDC, visit the ERDC online library at http://acwc.sdp.sirsi.net/client/default. Net Zero Planning for...1.8 degrees Celsius knots 0.5144444 meters per second miles (US statute) 1,609.347 meters miles per hour 0.44704 meters per second ERDC/CERL SR

  7. 75 FR 41922 - Notice of Intent To Rule on Request To Release Airport Property at Fort Smith Regional Airport...

    Science.gov (United States)

    2010-07-19

    ... To Release Airport Property at Fort Smith Regional Airport, Fort Smith, AR AGENCY: Federal Aviation... rule and invites public comment on the release of land at Fort Smith Regional Airport under the.... John Parker, Airport Director, Fort Smith Regional Airport, at the following address: Fort Smith...

  8. Liquid radwaste processing history at Fort Calhoun Nuclear Station

    International Nuclear Information System (INIS)

    Bilau, A.; Rutar, F.

    1989-01-01

    This report presents a historical perspective of liquid radwaste processing at the Fort Calhoun Unit 1 Nuclear Power Station, located in east central Nebraska. Of particular interest is the textual and graphical comparison of the operational implications of the various waste processing methods employed in the last ten years at the Fort Calhoun Station. Fort Calhoun's waste collection and processing systems are described in detail. These process systems include evaporation and solidification employing an in-plant drum solidification system. This solidification system was later replaced with vendor solidification services which solidified wastes in large liners. Ultimately, the plant converted its processing operation to ion exchange cleanup using ion selective media. The operational and economic impact of each of these process systems is discussed including overall costs, personnel exposure, capital expenditure requirements, burial volumes generated, maintenance and reliability assessments. Operational goals and performance criteria employed in the decision-making process for selection of the optimal technology are discussed, including the impact of various influent and effluent requirements

  9. Sundhedsprofessionelles begejstring for fortællinger fra levet erfaring

    DEFF Research Database (Denmark)

    Liveng, Anne; Larsen, Christine; Lange, Mads

    2018-01-01

    I 2013 etablerede psykiatrien i Region Hovedstaden, Danmark, et undervisningsprogram om recovery for sundhedsprofessionelle. Evalueringer af programmet viste et udtalt engagement i fortællingen fra underviseren med levet erfaring. Artiklen diskuterer hvordan dette kan forstås. Evalueringsmaterialet...... analyseres ud fra et læringsteoretisk perspektiv og fokuserer på: 1) Betydningen af fortællingens emotionelle indhold, 2) Rolle-bytningen mellem personen med levet erfaring og sundhedsprofessionelle, og 3) Workshoppene som et læringsrum, der aktiverer refleksioner over strukturer og organisering af...

  10. Den tabte fortælling

    DEFF Research Database (Denmark)

    Jørgensen, Kenneth Mølbjerg

    2008-01-01

    Ledelse er et af nøgleordene i fornyelsen af den offentlige sektor. Vi har imidlertid glemt et væsentligt aspekt af ledelse. Dette skyldes ikke mindst, at omgangsformen i dag er reguleret af information, mens den tidligere var reguleret af fortælleevnen. Evnen til dialog, indlevelse og nærvær er...

  11. Rumlige fortællinger fra mobilt og web-baseret GIS

    DEFF Research Database (Denmark)

    Møller-Jensen, Lasse

    2009-01-01

    Denne artikel handler om begrebet rumlige fortællinger med anvendelse af fortællingshenvisninger, og disses potentielle rolle ved implementation af fleksible og tematiske turistinformationssystemer. Artiklen fokuserer på brugen af mobile, positionsbekendte enheder, såsom visse PDA'er og smartphon......, samt på web-gis. Der præsenteres to anvendelseseksempler: et fra det centrale København og et fra et område nær Accra, Ghana....

  12. Comparison of predicted and measured fission product behaviour in the Fort St. Vrain HTGR during the first three cycles of operation

    International Nuclear Information System (INIS)

    Hanson, D.L.; Jovanovic, V.; Burnette, R.D.

    1985-01-01

    The 330 MW(e) Fort St. Vrain (M) High Temperature Gas-Cooled Reactor (HTGR) is fueled with (Th,U)C 2 /ThC 2 TRISO-coated fuel particles contained in prismatic graphite fuel elements. Fission product release from the reactor core has been monitored during the first three cycles of operation. In order to assess the validity of the design methods used to predict fission product source terms for HTGRs, fission product release from the reactor core has been predicted by the reference design methods and compared with reactor surveillance measurements and with the results of postirradiation examination (PIE) of spent FSV fuel elements. Overall, the predictive methods have been shown to be conservative: the predicted fission gas release at the end of Cycle 3 is about five times higher than observed. The dominant source of fission gas release is as-manufactured, heavy-metal contamination; in-service failure of the coated fuel particles appears to be negligible, which is consistent with the PIE of spent fuel elements removed during the first two refuelings. The predicted releases of fission metals are insignificant compared to the release and subsequent decay of their gaseous precursors, which is consistent with plateout probe measurements. (author)

  13. Options for treating high-temperature gas-cooled reactor fuel for repository disposal

    Energy Technology Data Exchange (ETDEWEB)

    Lotts, A.L.; Bond, W.D.; Forsberg, C.W.; Glass, R.W.; Harrington, F.E.; Micheals, G.E.; Notz, K.J.; Wymer, R.G.

    1992-02-01

    This report describes the options that can reasonably be considered for disposal of high-temperature gas-cooled reactor (HTGR) fuel in a repository. The options include whole-block disposal, disposal with removal of graphite (either mechanically or by burning), and reprocessing of spent fuel to separate the fuel and fission products. The report summarizes what is known about the options without extensively projecting or analyzing actual performance of waste forms in a repository. The report also summarizes the processes involved in convert spent HTGR fuel into the various waste forms and projects relative schedules and costs for deployment of the various options. Fort St. Vrain Reactor fuel, which utilizes highly-enriched {sup 235}U (plus thorium) and is contained in a prismatic graphite block geometry, was used as the baseline for evaluation, but the major conclusions would not be significantly different for low- or medium-enriched {sup 235}U (without thorium) or for the German pebble-bed fuel. Future US HTGRs will be based on the Fort St. Vrain (FSV) fuel form. The whole block appears to be a satisfactory waste form for disposal in a repository and may perform better than light-water reactor (LWR) spent fuel. From the standpoint of process cost and schedule (not considering repository cost or value of fuel that might be recycled), the options are ranked as follows in order of increased cost and longer schedule to perform the option: (1) whole block, (2a) physical separation, (2b) chemical separation, and (3) complete chemical processing.

  14. Options for treating high-temperature gas-cooled reactor fuel for repository disposal

    International Nuclear Information System (INIS)

    Lotts, A.L.; Bond, W.D.; Forsberg, C.W.; Glass, R.W.; Harrington, F.E.; Micheals, G.E.; Notz, K.J.; Wymer, R.G.

    1992-02-01

    This report describes the options that can reasonably be considered for disposal of high-temperature gas-cooled reactor (HTGR) fuel in a repository. The options include whole-block disposal, disposal with removal of graphite (either mechanically or by burning), and reprocessing of spent fuel to separate the fuel and fission products. The report summarizes what is known about the options without extensively projecting or analyzing actual performance of waste forms in a repository. The report also summarizes the processes involved in convert spent HTGR fuel into the various waste forms and projects relative schedules and costs for deployment of the various options. Fort St. Vrain Reactor fuel, which utilizes highly-enriched 235 U (plus thorium) and is contained in a prismatic graphite block geometry, was used as the baseline for evaluation, but the major conclusions would not be significantly different for low- or medium-enriched 235 U (without thorium) or for the German pebble-bed fuel. Future US HTGRs will be based on the Fort St. Vrain (FSV) fuel form. The whole block appears to be a satisfactory waste form for disposal in a repository and may perform better than light-water reactor (LWR) spent fuel. From the standpoint of process cost and schedule (not considering repository cost or value of fuel that might be recycled), the options are ranked as follows in order of increased cost and longer schedule to perform the option: (1) whole block, (2a) physical separation, (2b) chemical separation, and (3) complete chemical processing

  15. Fort Mason Center: Pier 2 Project

    Energy Technology Data Exchange (ETDEWEB)

    Nester, Patrick [Fort Mason Center, San Francisco, CA (United States)

    2014-08-30

    The rooftop Photovoltaic (PV) panels and radiant piping project was constructed by Fort Mason Center as part of its $21 million comprehensive rehabilitation of the Pier 2 shed which include the shed’s electrical, natural gas and water systems. Fort Mason Center improved performance while reducing energy and water usage and costs to demonstrate the efficiencies and opportunities available to large multi-function facilities. The scalable demand of these facilities required a layered approach to conservation, control and production. The project employed a comprehensive retrofit of electrical natural gas, and plumbing systems to maximize efficiency and lower carbon footprint specifically to demonstrate the effectiveness of these strategies in a public setting with varied and diverse use. The project was completed in July 2014 and met the expected outcomes regarding increased comfort and operational efficiency throughout the Pier 2 shed as well as on site electrical generation of current consumption. The entire Pier 2 shed project won a 2015 California Preservation Foundation design award for historic rehabilitation.

  16. BRAND EQUITY OF LAHORE FORT AS A TOURISM DESTINATION BRAND

    OpenAIRE

    KASHIF, MUHAMMAD; SAMSI, SITI ZAKIAH MELATU; SARIFUDDIN, SYAMSULANG

    2015-01-01

    ABSTRACTStudies that measure the brand equity of destination brands by using the Customer-Based Brand Equity (CBBE) model in a developing country context are scarce. The present study investigates the destination brand equity of the Lahore Fort by employing the CBBE model in a developing country context of Pakistan. Following the positivist tradition, we adopted a survey-based approach to collect data from 237 tourists visiting the Lahore Fort. Data were collected through a questionnaire deve...

  17. Comprehensive Inventory and Determinations of Eligibility for Fort Riley Buildings: 1857-1963

    Science.gov (United States)

    2009-09-01

    become fashionable . Stone residences built at Fort Riley after the 1850s all have rock-faced walls and most have contrasting smooth-faced lintels...507 is significant as a wood-framed Folk Victorian cottage. While Building 507 is one of four Folk Victorian buildings at Fort Riley, it possesses a

  18. The geology and mechanics of formation of the Fort Rock Dome, Yavapai County, Arizona

    Science.gov (United States)

    Fuis, Gary S.

    1996-01-01

    The Fort Rock Dome, a craterlike structure in northern Arizona, is the erosional product of a circular domal uplift associated with a Precambrian shear zone exposed within the crater and with Tertiary volcanism. A section of Precambrian to Quaternary rocks is described, and two Tertiary units, the Crater Pasture Formation and the Fort Rock Creek Rhyodacite, are named. A mathematical model of the doming process is developed that is consistent with the history of the Fort Rock Dome.

  19. Ecological Baseline, Fort Hood, Texas

    Science.gov (United States)

    1980-08-01

    cedar eTm (Uiimus crassifolia), Texas ash (Fraxinus texansis), and Texas persimmon ( Diospyros texana). Conversely, the two predominant tree species...Ilex decidua), Mex- ican buckeye (Ungnadia spjeciosa), and Texas persimmon ( Diospyros texana). Vines included greenbrier (Smilax bona-nox) and white...Hedgehey Cactus (Echinocereus sp.) has been observed on Fort Hood. Due to the brief period of flowering for this genus , the individual species were not

  20. Fort Davis National Historic Site : acoustical monitoring

    Science.gov (United States)

    2013-06-01

    During the summer of 2010 (September - October 2010), the Volpe Center collected baseline acoustical data at Fort Davis National Historic Site (FODA)at two sites deployed for approximately 30 days each. The baseline data collected during this period ...

  1. Nondestructive examination of 54 fuel and reflector elements from Fort St. Vrain core segment 2

    International Nuclear Information System (INIS)

    Saurwein, J.J.

    1982-10-01

    Fifty-four fuel and reflector elements irradiated in core segment 2 of the Fort St. Vrain high-temperature gas-cooled reactor (HTGR) were nondestructively examined. The time- and volume-averaged graphite irradiation temperatures for the elements ranged from approx. 350 0 to 750 0 C. The element-averaged fast neutron fluences ranged from approx. 0.2 to 1.6 x 10 25 n/m 2 (E > 29 fJ)/sub HTGR/. The elements, except for two fuel elements in which single localizeed cracks developed during irradiation, were in excellent condition. No evidence was observed of significant graphite oxidation or mechanical interaction beween elements. The cracks in the two elements did not affect their performance or handling. These elements were, otherwise, in excellent condition. Nearly all elements shrank in both the axial and radial directions, but the dimensional changes were relatively small

  2. Electricity Generation from Geothermal Resources on the Fort Peck Reservation in Northeast Montana

    Energy Technology Data Exchange (ETDEWEB)

    Carlson, Garry J. [Gradient Geophysics Inc., Missoula, MT (United States); Birkby, Jeff [Birkby Consulting LLC, Missoula, MT (United States)

    2015-05-12

    Tribal lands owned by Assiniboine and Sioux Tribes on the Fort Peck Indian Reservation, located in Northeastern Montana, overlie large volumes of deep, hot, saline water. Our study area included all the Fort Peck Reservation occupying roughly 1,456 sq miles. The geothermal water present in the Fort Peck Reservation is located in the western part of the Williston Basin in the Madison Group complex ranging in depths of 5500 to 7500 feet. Although no surface hot springs exist on the Reservation, water temperatures within oil wells that intercept these geothermal resources in the Madison Formation range from 150 to 278 degrees F.

  3. Technical evaluation report of the Fort St. Vrain final draft upgraded technical specifications

    International Nuclear Information System (INIS)

    Kimura, C.Y.

    1989-01-01

    This report is a technical evaluation of the final draft of the Fort St. Vrain (FSV) Upgraded Technical Specifications (UT/S) as issued by Public Service of Colorado (PSC) on May 27, 1988 with subsequent supplemental updates issued on June 15, 1988 and August 5, 1988. It has been compared for consistency, and safety conservatism with the Fort St. Vrain (FSV) Updated Final Safety Analysis Report (FSAR), the FSV Safety Evaluation Report (SER), the Facility Operating License, DPR-34, and all amendments to the Facility Operating License issued as of June 1, 1988, and Appendix A to the Operating License DPR-34, Technical Specifications. Because of the age of the plant, no supplements to the Fort St. Vrain SER have been issued since the original SER was not issued as a WASH or a NUREG report. This made it necessary to review all amendments to the Facility Operating License since they would contain the safety evaluations done to support changes to the Facility Operating License. The upgraded Fort St. Vrain Technical Specifications were also broadly compared with the latest Westinghouse Standard Technical Specifications (WSTS) to assure that what was proposed for Fort St. Vrain was consistent with the latest NRC staff practices for standard technical specifications

  4. Fortælleværksteder

    DEFF Research Database (Denmark)

    Krøjer, Jo; Hutters, Camilla

    2009-01-01

    Unges valg af videregående uddannelse er omgærdet af forventninger. Forventninger til hvad man skal vælge. Forventninger til hvor lang tid, man skal være om at tage en uddannelse. Og forventninger til, hvad uddannelsen skal føre til. Artiklen præsenterer fortælleværkstedet, en metode til kollekti...... refleksioner over egne og adres forventninger til og tanker om uddannelsesvalg....

  5. 77 FR 58354 - Bend-Fort Rock Ranger District; Oregon; Withdrawal of Notice for Preparation of an Environmental...

    Science.gov (United States)

    2012-09-20

    ...-Fort Rock Ranger District; Oregon; Withdrawal of Notice for Preparation of an Environmental Impact... Administration, USDOT. ACTION: Notice of withdrawal. SUMMARY: The Bend-Fort Rock Ranger District and FHWA are..., Project Leader, Bend- Fort Rock Ranger District, 63095 Deschutes Market Road, Bend, OR 97701, phone 541...

  6. Cannon Fire Soon to Accompany Bugle Call at Fort Detrick | Poster

    Science.gov (United States)

    Beginning June 14, the familiar bugle calls at Fort Detrick will be joined by a special percussion instrument: a cannon. A single cannon shot will be fired on the first note of “Reveille,” which signals the start of each day and is accompanied by the raising of the American flag. “Reveille” sounds at 6:30 a.m. At 5 p.m., Fort Detrick plays “Retreat,” which alerts the post that

  7. The Fort St. Vrain high temperature gas-cooled reactor. III

    International Nuclear Information System (INIS)

    Olson, H.G.; Brey, H.L.

    1979-01-01

    The helium circulator auxiliary system provides buffer helium and bearing water for the reactor's four circulators with two nearly identical auxiliary loops serving the two circulators of a primary coolant loop. A series of drains removes the water and helium for separation and recycle. Loss of buffer helium's function as a dynamic seal has resulted in inleakage of bearing water into the primary coolant and outleakage of primary coolant into the auxiliary system. Inleakage of water also has occurred due to inadvertent pressurization of the bearing cavity with the static shutdown seal set. Satisfactory performance of the normal, backup and emergency bearing water systems has been accomplished after numerous component additions and modifications. Frequent circulator trips have occurred. Most of these have involved the delicate sensors that measure buffer helium differential pressure. Transients in one loop have communicated to the other loop through common components. Total separation of the auxiliary loops will occur after the planned installation of those components that currently service both loops. (Auth.)

  8. Site-Based Budgeting in Fort Worth, Texas.

    Science.gov (United States)

    Peternick, Lauri; Sherman, Joel

    1998-01-01

    Examines the Fort Worth Independent School District's decentralized decision-making system through three lenses: a review of site-based decision-making procedures at several schools; an examination of who participates; and stakeholders' perceptions. Some schools operated democratically, significantly including teachers, parents, and community…

  9. Reactor G1: high power experiments; Experiences a forte puissance

    Energy Technology Data Exchange (ETDEWEB)

    Laage, F de; Teste du Baillet, A; Veyssiere, A; Wanner, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Retel, H [Societe Rateau, D.E.A. (France)

    1957-07-01

    The experiments carried out in the starting-up programme of the reactor G1 comprised a series of tests at high power, which allowed the following points to be studied: 1- Effect of poisoning by Xenon (absolute value, evolution). 2- Temperature coefficients of the uranium and graphite for a temperature distribution corresponding to heating by fission. 3- Effect of the pressure (due to the coiling system) on the reactivity. 4- Calibration of the security rods as a function of their position in the pile (1). 5- Temperature distribution of the graphite, the sheathing, the uranium and the air leaving the canals, in a pile running normally at high power. 6- Neutron flux distribution in a pile running normally at high power. 7- Determination of the power by nuclear and thermodynamic methods. These experiments have been carried out under two very different pile conditions. From the 1. to the 15. of August 1956, a series of power increases, followed by periods of stabilisation, were induced in a pile containing uranium only, in 457 canals, amounting to about 34 tons of fuel. A knowledge of the efficiency of the control rods in such a pile has made it possible to measure with good accuracy the principal effects at high temperatures, that is, to deal with points 1, 2, 3, 5. Flux charts giving information on the variations of the material Laplacian and extrapolation lengths in the reflector have been drawn up. Finally the thermodynamic power has been measured under good conditions, in spite of some installation difficulties. On September 16, the pile had its final charge of 100 tons. All the canals were loaded, 1,234 with uranium and 53 (i.e. exactly 4 per cent of the total number) with thorium uniformly distributed in a square lattice of 100 cm side. Since technical difficulties prevented the calibration of the control rods, the measurements were limited to the determination of the thermodynamic power and the temperature distributions (points 5 and 7). This report will

  10. 77 FR 9960 - Final Environmental Impact Statement for Extension of F-Line Streetcar Service to Fort Mason...

    Science.gov (United States)

    2012-02-21

    ... Environmental Impact Statement for Extension of F-Line Streetcar Service to Fort Mason Center, San Francisco, CA... Environmental Impact Statement for the Extension of F-Line Streetcar Service to Fort Mason Center, San Francisco... the extension of the historic streetcar F-line from Fisherman's Wharf to the Fort Mason Center, in San...

  11. BRAND EQUITY OF LAHORE FORT AS A TOURISM DESTINATION BRAND

    Directory of Open Access Journals (Sweden)

    Muhammad Kashif

    2015-06-01

    Full Text Available Studies that measure the brand equity of destination brands by using the Customer-Based Brand Equity (CBBE model in a developing country context are scarce. The present study investigates the destination brand equity of the Lahore Fort by employing the CBBE model in a developing country context of Pakistan. Following the positivist tradition, we adopted a survey-based approach to collect data from 237 tourists visiting the Lahore Fort. Data were collected through a questionnaire developed to explain the relationship of brand awareness, brand image, brand association, and brand loyalty with Lahore Fort’s overall brand equity. We used various robust statistical techniques such as correlation, regression and confirmatory factor analysis (using PLS method to reach meaningful conclusions and found that brand image and brand associations positively contribute to brand loyalty. Furthermore, brand loyalty significantly contributes towards overall brand equity. Pragmatically, this study measures the customer based brand equity of the Lahore Fort, a destination brand. The results are useful as they suggest a few strategies that can help policy makers to enhance Lahore Fort’s brand performance.

  12. National Training Center Fort Irwin expansion area aquatic resources survey

    Energy Technology Data Exchange (ETDEWEB)

    Cushing, C.E.; Mueller, R.P.

    1996-02-01

    Biologists from Pacific Northwest National Laboratory (PNNL) were requested by personnel from Fort Irwin to conduct a biological reconnaissance of the Avawatz Mountains northeast of Fort Irwin, an area for proposed expansion of the Fort. Surveys of vegetation, small mammals, birds, reptiles, amphibians, and aquatic resources were conducted during 1995 to characterize the populations and habitats present with emphasis on determining the presence of any species of special concern. This report presents a description of the sites sampled, a list of the organisms found and identified, and a discussion of relative abundance. Taxonomic identifications were done to the lowest level possible commensurate with determining the status of the taxa relative to its possible listing as a threatened, endangered, or candidate species. Consultation with taxonomic experts was undertaken for the Coleoptera ahd Hemiptera. In addition to listing the macroinvertebrates found, the authors also present a discussion related to the possible presence of any threatened or endangered species or species of concern found in Sheep Creek Springs, Tin Cabin Springs, and the Amargosa River.

  13. Comparison of maxillary stability after Le Fort I osteotomy for occlusal cant correction surgery and maxillary advanced surgery.

    Science.gov (United States)

    Ueki, Koichiro; Hashiba, Yukari; Marukawa, Kohei; Yoshida, Kan; Shimizu, Chika; Nakagawa, Kiyomasa; Yamamoto, Etsuhide

    2007-07-01

    To compare postoperative maxillary stability following Le Fort I osteotomy for the correction of occlusal cant as compared with conventional Le Fort I osteotomy for maxillary advancement. The subjects were 40 Japanese adults with jaw deformities. Of these, 20 underwent a Le Fort I osteotomy and intraoral vertical ramus osteotomy (IVRO) to correct asymmetric skeletal morphology and inclined occlusal cant. The other 20 patients underwent a Le Fort I osteotomy and sagittal split ramus osteotomy (SSRO) to advance the maxilla. Lateral and posteroanterior cephalograms were taken postoperatively and assessed statistically. Thereafter, the 2 groups were followed for time-course changes. There was no significant difference between the 2 groups with regard to time-course changes during the immediate postoperative period. This suggests that maxillary stability after Le Fort I osteotomy for cant correction does not differ from that after Le Fort I osteotomy for maxillary advancement.

  14. Feltarbejde i Thule. Sammenfiltringen af steder, folk og fortællinger

    Directory of Open Access Journals (Sweden)

    Kirsten Hastrup

    2016-07-01

    Full Text Available På baggrund af lang tids arbejde i Thuleregionen i det nordvestligste Grønland vil jeg diskutere, hvordan steder, folk og fortællinger gensidigt former hinanden. ’Felten’ er således formateret af mange forhold, historiske og nutidige, naturlige og kulturelle, og man må besinde sig på feltens flydende form, selv når den ser mest solid ud. Steder er i sig selv flygtige; de opstår i mødet med mennesker, som tillægger dem betydning. Folk kan se nok så traditionelle ud, men de lever i samme verden som antropologen, der kommer for at lære af dem. Endelig er fortællingerne ikke stivnede vidnesbyrd om tidligere tider; de er tværtimod et vigtigt redskab i håndteringen af højst nutidige udfordringer, som kommer til syne i det endnu ufortalte. Bag fortællingen om Thule ligger en større diskussion af enhver felts plasticitet.

  15. Smithsonian Marine Station (SMS) at Fort Pierce

    Science.gov (United States)

    share current Smithsonian research on the plants and animals of the Indian River Lagoon and marine Smithsonian Marine Station at Fort Pierce Website Search Box Search Field: SMS Website Search Twitter SMS Home › Welcome to the Smithsonian Marine Station Homepage slideshow Who We Are... The

  16. RadNet Air Data From Fort Smith, AR

    Science.gov (United States)

    This page presents radiation air monitoring and air filter analysis data for Fort Smith, AR from EPA's RadNet system. RadNet is a nationwide network of monitoring stations that measure radiation in air, drinking water and precipitation.

  17. Fission product behaviour in the Peach Bottom and Fort St. Vrain HTGRs

    International Nuclear Information System (INIS)

    Hanson, D.L.; Baldwin, N.L.; Strong, D.E.

    1981-01-01

    Actual operating data from the Peach Bottom (PB) and Fort St. Vrain (FSV) High-Temperature Gas-Cooled Reactors (HTGRs) have been compared with code predictions to assess the validity of the methods used to predict the behaviour of fission products in the primary coolant circuit. For both reactors the measured circuit activities were significantly below design values, and the observations generally verify the codes used for large HTGR design. The PB primary circuit after seven years of operation was exceptionally clean. A fuel element purge system virtually eliminated the release of fission gases into the primary coolant circuit. Extensive examinations at end-of-life revealed that only Cs and trace amounts of Sr had plated out in the circuit. Their plateout distributions were in excellent agreement with PAD code predictions. Most of the deposited activity was associated with carbonaceous surface films which resulted from occasional small inleakages of lubricating oil. Primary circuit activities in FSV during the first cycle were also very low. Noble gas activity was about 1% of the design limit; and the circulating iodines were at least one order of magnitude below the limit, although the measurement uncertainties are significant. The plateout per pass of the iodine isotopes increased with decreasing half-life (the value for I-131 is about 1% per pass) as predicted with the PADLOC code. Gamma scanning of two helium circulators indicated very low plateout activities. Iodine-131 was the principal fission product observed, along with small amounts of Cs-134, Cs-137, and Ba/La-140. (author)

  18. Slaget ved Vejle og andre fortællinger fra Jyske Bank

    DEFF Research Database (Denmark)

    Albrechtsen, Charlotte

    Storytelling som ledelsesværktøj er en form for retorik idet formålet med at bruge fortællinger i kommunikationen fra ledelse til medarbejdere er at påvirke modtagerne/medarbejderne. Imidlertid er refleksioner over modtagerinstansen så godt som fraværende både i den populære debat om storytelling...... og i den eksisterende forskning i emnet. Foruden at introducere til forskningen i storytelling præsenterer artiklens forfatter, som er ph.d.-studerende, en modtagerorienteret analyse af en fortælling fra Jyske Bank....

  19. Low footwall accelerations and variable surface rupture behavior on the Fort Sage Mountains fault, northeast California

    Science.gov (United States)

    Briggs, Richard W.; Wesnousky, Steven G.; Brune, James N.; Purvance, Matthew D.; Mahan, Shannon

    2013-01-01

    The Fort Sage Mountains fault zone is a normal fault in the Walker Lane of the western Basin and Range that produced a small surface rupture (L 5.6 earthquake in 1950. We investigate the paleoseismic history of the Fort Sage fault and find evidence for two paleoearthquakes with surface displacements much larger than those observed in 1950. Rupture of the Fort Sage fault ∼5.6  ka resulted in surface displacements of at least 0.8–1.5 m, implying earthquake moment magnitudes (Mw) of 6.7–7.1. An older rupture at ∼20.5  ka displaced the ground at least 1.5 m, implying an earthquake of Mw 6.8–7.1. A field of precariously balanced rocks (PBRs) is located less than 1 km from the surface‐rupture trace of this Holocene‐active normal fault. Ground‐motion prediction equations (GMPEs) predict peak ground accelerations (PGAs) of 0.2–0.3g for the 1950 rupture and 0.3–0.5g for the ∼5.6  ka paleoearthquake one kilometer from the fault‐surface trace, yet field tests indicate that the Fort Sage PBRs will be toppled by PGAs between 0.1–0.3g. We discuss the paleoseismic history of the Fort Sage fault in the context of the nearby PBRs, GMPEs, and probabilistic seismic hazard maps for extensional regimes. If the Fort Sage PBRs are older than the mid‐Holocene rupture on the Fort Sage fault zone, this implies that current GMPEs may overestimate near‐fault footwall ground motions at this site.

  20. FORT NAMUTONI: FROM MILITARY STRONGHOLD TO TOURIST ...

    African Journals Online (AJOL)

    STRONGHOLD TO TOURIST CAMP. Col Dr Jan Ploeger*. "... this fortress was not just a white elephant, it was actually occupied and played a major role in the settlement of Germans in the far North." (own translation) - D.W. Krynauw Die Verhaal van. Namutoni, p 3. Introduction. Fort Namutoni, the last White outpost east of ...

  1. 78 FR 28622 - Notice of Approval of Record of Decision for Extending F-Line Streetcar Service to Fort Mason...

    Science.gov (United States)

    2013-05-15

    ...] Notice of Approval of Record of Decision for Extending F-Line Streetcar Service to Fort Mason Center... Environmental Impact Statement (Final EIS) for extending the F-Line historic streetcar service to Fort Mason... turnaround terminus at the Fort Mason Center; and installing appurtenant features such as signals, crossings...

  2. 77 FR 71636 - Huntington Foam LLC, Fort Smith, AR; Notice of Revised Determination on Reconsideration

    Science.gov (United States)

    2012-12-03

    ... Smith, AR; Notice of Revised Determination on Reconsideration On August 8, 2012, the Department of Labor... workers and former workers of Huntington Foam LLC, Fort Smith, Arkansas (subject firm). The workers are... reconsideration investigation, I determine that workers of Huntington Foam LLC, Fort Smith, Arkansas, who were...

  3. Maxillary distraction osteogenesis at Le Fort-I level induces bone apposition at infraorbital rim.

    Science.gov (United States)

    Rattan, Vidya; Jena, Ashok Kumar; Singh, Satinder Pal; Utreja, Ashok Kumar

    2014-09-01

    The aim of this study is to evaluate whether there is any remodeling of bone at infraorbital rim following maxillary distraction osteogenesis (DO) at Le Fort-I level. Twelve adult subjects in the age range of 17-21 years with complete unilateral cleft lip and palate underwent advancement of the maxilla by DO. The effect of maxillary DO on the infraorbital rim remodeling was evaluated from lateral cephalograms recorded prior to the DO (T0), at the end of DO (T1), and at least 2-years after the DO (T2) by Walker's analysis. The ANOVA and two-tailed t test were used and probability value (P value) 0.05 was considered as statistically significant level. There was anterior movement of maxilla by 9.22 ± 3.27 mm and 7.67 ± 3.99 mm at the end of immediate (T1) and long-term (T2) follow-up of maxillary DO, respectively. The Walker's analysis showed 1.49 ± 1.22 mm and 2.31 ± 1.81 mm anterior movement of the infraorbital margin (Orbitale point) at the end of T1 and T2, respectively (P distraction osteogenesis at Le Fort-I level induced significant bone apposition at infraorbital rim. Patients with mild midface hypoplasia who would otherwise may be candidates for osteotomy at Le Fort-II or Le Fort-III level may benefit from maxillary distraction at Le Fort-I level.

  4. Wood-Fired Boiler System Evaluation at Fort Stewart, GA

    National Research Council Canada - National Science Library

    Potts, Noel

    2002-01-01

    Part of the plan to modernize the central energy plant (CEP) at Fort Stewart, GA is focused on the installations wood-fired boiler, which provides steam for heating, cooling, and domestic hot water. The U.S...

  5. Von Braun Rocket Team at Fort Bliss, Texas

    Science.gov (United States)

    1940-01-01

    The German Rocket Team, also known as the Von Braun Rocket Team, poses for a group photograph at Fort Bliss, Texas. After World War II ended in 1945, Dr. Wernher von Braun led some 120 of his Peenemuende Colleagues, who developed the V-2 rocket for the German military during the War, to the United Sttes under a contract to the U.S. Army Corps as part of Operation Paperclip. During the following five years the team worked on high altitude firings of the captured V-2 rockets at the White Sands Missile Range in New Mexico, and a guided missile development unit at Fort Bliss, Texas. In April 1950, the group was transferred to the Army Ballistic Missile Agency (ABMA) at Redstone Arsenal in Huntsville, Alabama, and continued to work on the development of the guided missiles for the U.S. Army until transferring to a newly established field center of the National Aeronautic and Space Administration (NASA), George C. Marshall Space Flight Center (MSFC).

  6. Ægtefællen skal også trives her

    DEFF Research Database (Denmark)

    Elle, Morten; Shevchenko, Yana

    2014-01-01

    Kort oplæg baseret på Yana Shevchenko's Master Thesis - om problemerne i at fastholde expats og kommunernes rolle i en globaliseret verden.......Kort oplæg baseret på Yana Shevchenko's Master Thesis - om problemerne i at fastholde expats og kommunernes rolle i en globaliseret verden....

  7. Development of a detailed core flow analysis code for prismatic fuel reactors

    International Nuclear Information System (INIS)

    Bennett, R.G.

    1990-01-01

    The detailed analysis of the core flow distribution in prismatic fuel reactors is of interest for modular high-temperature gas-cooled reactor (MHTGR) design and safety analyses. Such analyses involve the steady-state flow of helium through highly cross-connected flow paths in and around the prismatic fuel elements. Several computer codes have been developed for this purpose. However, since they are proprietary codes, they are not generally available for independent MHTGR design confirmation. The previously developed codes do not consider the exchange or diversion of flow between individual bypass gaps with much detail. Such a capability could be important in the analysis of potential fuel block motion, such as occurred in the Fort St. Vrain reactor, or for the analysis of the conditions around a flow blockage or misloaded fuel block. This work develops a computer code with fairly general-purpose capabilities for modeling the flow in regions of prismatic fuel cores. The code, called BYPASS solves a finite difference control volume formulation of the compressible, steady-state fluid flow in highly cross-connected flow paths typical of the MHTGR

  8. Wind resource assessment and wind energy system cost analysis: Fort Huachuca, Arizona

    Energy Technology Data Exchange (ETDEWEB)

    Olsen, T.L. [Tim Olsen Consulting, Denver, CO (United States); McKenna, E. [National Renewable Energy Lab., Golden, CO (United States)

    1997-12-01

    The objective of this joint DOE and National Renewable Energy Laboratory (NREL) Strategic Environmental Research and Development Program (SERDP) project is to determine whether wind turbines can reduce costs by providing power to US military facilities in high wind areas. In support of this objective, one year of data on the wind resources at several Fort Huachuca sites was collected. The wind resource data were analyzed and used as input to an economic study for a wind energy installation at Fort Huachuca. The results of this wind energy feasibility study are presented in the report.

  9. Surgical risk factors and maxillary nerve function after le fort I osteotomy

    DEFF Research Database (Denmark)

    Thygesen, Torben Henrik; Jensen, Allan Bardow; Norholt, SE

    2009-01-01

    PURPOSE: Data on intraoperative risk factors for long-term postoperative complications after Le Fort I osteotomy (LFO) are limited. The aim of this study was to describe prospectively the overall postoperative changes in maxillary nerve function after LFO, and to correlate these changes with a nu......PURPOSE: Data on intraoperative risk factors for long-term postoperative complications after Le Fort I osteotomy (LFO) are limited. The aim of this study was to describe prospectively the overall postoperative changes in maxillary nerve function after LFO, and to correlate these changes...

  10. Strategic Analysis and Plan for Implementing Telemedicine at Fort Greely

    National Research Council Canada - National Science Library

    Bolton, Karl

    2003-01-01

    .... To best accomplish this, a strategic analysis and business case analysis was conducted. Introspective strategic analysis tools revealed an organization that is capable of supporting a telemedicine program at Fort Greely...

  11. The Fort Smith radioactive belt, Northwest Territories

    International Nuclear Information System (INIS)

    Charbonneau, B.W.

    1980-01-01

    The Fort Smith Belt is an elongate zone, about 200 km x 50 km, extending from the East Arm of Great Slave Lake southerly into northeastern Alberta. The major feature of the belt is that it is one of the most radioactive regions so far recognized in the Canadian Shield. Potassium, uranium, and thorium are all enriched but the greatest increase is in thorium. The dominant rock type underlying the area is a foliated porphyritic granite. This rock contains an average of about 80 ppm thorium (with areas of tens of square kilometres containing up to 200 ppm) and approximately 11 ppm uranium. In places, dark elongate zones rich in biotite, apatite, and opaque minerals within the porphyritic granite may contain an order of magnitude more uranium and thorium than the porphyry. Radioactive minerals within both the porphyry and the dark zones are principally monazite (containing up to 16% ThO 2 ) and isolated grains of uraninite. This foliated porphyritic granite is interpreted as being pre- or syntectonic with respect to the Hudsonian event because its foliation parallels that of the surrounding rocks. There has been subsequent deformation. The second characteristic feature of the Fort Smith Belt is the development of a peripheral zone where eU is enriched relative to eTh correlating mainly with granitoid rocks which surround the thorium-rich area and wherein ratios of eU/eTh exceed 1:2 (compared to the crustal average of 1:4). Uranium may have moved laterally into this marginal area from the thorium-rich porphyry, possibly in a vapour phase. There is a possibility that concentrations of uranium as well as other metals such as Cu, Mo, Zn, Sn, and W could exist in the porphyry and its margin in appropriate chemical and/or structural traps. The radioactive granite rocks of the Fort Smith Belt are adjacent to uranium-thorium occurrences in the nearby Proterozoic Nonacho sediments but whether or not a genetic relationship exists between the two situations is uncertain. (auth)

  12. The Fall of Fort Eben Emael: The Effects of Emerging Technologies on the Successful Completion of Military Objectives

    Science.gov (United States)

    2004-06-18

    of Sickle,” World War II Magazine, November 2003, 59. 11Ibid., 60. 12Abbeville is 100 miles north of Paris near the English Channel. 13T. N. Mout... catacombs of Fort Eben Emael. A further understanding of the dynamics of the fort and her defenders can be gained by the knowledge that that fort was...Green Devils German Paratroopers 1939-45 ( Paris , France: Histories & Collections, 1997), 27. Helmut Wenzl (Left in photo) Born - 10 March

  13. 75 FR 39051 - Desoto Mills LLC, Fort Payne, AL; Notice of Negative Determination Regarding Application for...

    Science.gov (United States)

    2010-07-07

    ... DEPARTMENT OF LABOR Employment and Training Administration [TA-W-73,416] Desoto Mills LLC, Fort... applicable to workers and former workers at Desoto Mills, LLC, a Subsidiary of Fruit of the Loom, Fort Payne... * * * locations outside the Desoto Mills Plant.'' The petitioner compares the situation at this location with...

  14. FIND: Fort Calhoun Station, Unit 2

    International Nuclear Information System (INIS)

    Williams, W.H.

    1976-07-01

    This index is presented for the microfiche material of Docket 50548 which concerns the application of Omaha Public Power District to build and operate Fort Calhoun Station, Unit 2. The information includes both application and review material dated from September 1975 through March 1976. There are five amendments to the PSAR and one supplement to the ER which have been incorporated by reference into the respective reports. Docket RESAR-3 is used as a reference for portions of the PSAR

  15. Opening remarks for the Fort Valley Centennial Celebration

    Science.gov (United States)

    G. Sam Foster

    2008-01-01

    The Rocky Mountain Research Station recognizes and values the contributions of our scientists and collaborators for their work over the past century at Fort Valley Experimental Forest. With the help of our partners and collaborators, Rocky Mountain Research Station is working to improve coordination across its research Program Areas and Experimental Forests and Ranges...

  16. A visual progression of the Fort Valley Restoration Project treatments using remotely sensed imagery (P-53)

    Science.gov (United States)

    Joseph E. Crouse; Peter Z. Fule

    2008-01-01

    The landscape surrounding the Fort Valley Experimental Forest in northern Arizona has changed dramatically in the past decade due to the Fort Valley Restoration Project, a collaboration between the Greater Flagstaff Forest Partnership, Coconino National Forest, and Rocky Mountain Research Station. Severe wildfires in 1996 sparked community concern to start restoration...

  17. Fortællinger om sorg og tab – når det personlige bliver socialt?

    DEFF Research Database (Denmark)

    Christensen, Dorthe Refslund; Sandvik, Kjetil

    2016-01-01

    Vi fortæller om døden, om det at miste og føle sorg. Kulturhistorisk er litteratur, teater og malerkunst scener for netop dette emne. Som socialt fænomen ser vi dog ikke i samme omfang fortællinger om død, tab og sorg, eftersom emnet typisk har været anskuet som et privat anliggende. Bestemte...

  18. The present state of development and the future of the high-temperature reactor in the United States of America

    International Nuclear Information System (INIS)

    Simon, W.A.; Chi, H.W.

    1982-01-01

    The American prototype high-temperature reactor at Fort St. Vrain has been operating successfully for years. To date it has produced more than 3.000.000.000 kilowatt hours of electricity and a short while ago was cleared for operation at full load. Operating experience justifies expectations that the combined cycle HTR plant of 2240 MW thermal output favoured by the US Government and industry will offer significant economic advantages. (orig.) [de

  19. Shevchenkian documents in the archive of Mykola Shudria (on the materials from the fonds of the Institute of Manuscript of V. Vernadsky National Library of Ukraine

    Directory of Open Access Journals (Sweden)

    Gerasimova T.

    2015-01-01

    Full Text Available In the paper the author analyzes Shevchenkian documents deposited in the personal archival fond of a Ukrainian journalist Mykola Shudria, which comprises the fond 299 of the Institute of Manuscript of VNLU. These documents represent both Mykola Shudria’s Shevchenko research heritage and his collection of Shevchenkian studies of other investigators. The article revealed that Mykola Shudria’s attention in Shevchenko Studies had mostly been centered on Kobzar’s biography and origin, Ukrainian areas associated with the personality of Taras Shevchenko, his poems and paintings. The most prominent works of Mykola Shudria reviewed in the article are a novel "The head of the pedunculate oak" revealing Taras Shevchenko’s genealogy and his Shevchenkian publicistic writings

  20. Third party testing : new pilot facility for mining processes opens in Fort McKay

    International Nuclear Information System (INIS)

    Jaremko, D.

    2007-01-01

    Fort McKay lies 65 kilometres north of Fort McMurray, Alberta and is the centre of operational oilsands mining activity. As such, it was chosen for a pilot testing facility created by the Geneva-based SGS Group. The reputable facility provides an opportunity for mining producers to advance their processes, including environmental performance, by allowing them to test different processes on their own oilsands. The Northern Lights partnership, led by Synenco Energy, was the first client at the facility. Due to outsourcing, clients are not obligated to make substantial capital investment into in-house research. The Northern Lights partnership will be using the facility to test extraction processes on bitumen from its leases. Although the Fort McKay facility is SGS's first venture into the oilsands industry, it operates in more than 140 companies globally, including the mineral industry, and specializes in inspection, verification, testing and certification. SGS took the experience from its minerals extraction business to identify what could be done to help the oilsands industry by using best practices developed from global operations. The facility lies on the Fort McKay industrial park owned by the Fort McKay First Nation. An existing testing facility called McMurray Resources Research and Testing was expanded by the SGS Group to include environmental analysis capabilities. The modular units that lie on 6 acres include refrigerated ore storage to maintain ore integrity; modular ore and materials handling systems; extraction equipment; and, zero discharge process water and waste disposal systems. Froth treatment will be added in the near future to cover the entire upstream side of the mining processing business. A micro-upgrader might be added in the future to manufacture synthetic crude. 3 figs

  1. Third party testing : new pilot facility for mining processes opens in Fort McKay

    Energy Technology Data Exchange (ETDEWEB)

    Jaremko, D.

    2007-12-15

    Fort McKay lies 65 kilometres north of Fort McMurray, Alberta and is the centre of operational oilsands mining activity. As such, it was chosen for a pilot testing facility created by the Geneva-based SGS Group. The reputable facility provides an opportunity for mining producers to advance their processes, including environmental performance, by allowing them to test different processes on their own oilsands. The Northern Lights partnership, led by Synenco Energy, was the first client at the facility. Due to outsourcing, clients are not obligated to make substantial capital investment into in-house research. The Northern Lights partnership will be using the facility to test extraction processes on bitumen from its leases. Although the Fort McKay facility is SGS's first venture into the oilsands industry, it operates in more than 140 companies globally, including the mineral industry, and specializes in inspection, verification, testing and certification. SGS took the experience from its minerals extraction business to identify what could be done to help the oilsands industry by using best practices developed from global operations. The facility lies on the Fort McKay industrial park owned by the Fort McKay First Nation. An existing testing facility called McMurray Resources Research and Testing was expanded by the SGS Group to include environmental analysis capabilities. The modular units that lie on 6 acres include refrigerated ore storage to maintain ore integrity; modular ore and materials handling systems; extraction equipment; and, zero discharge process water and waste disposal systems. Froth treatment will be added in the near future to cover the entire upstream side of the mining processing business. A micro-upgrader might be added in the future to manufacture synthetic crude. 3 figs.

  2. Rail Outloading Capability Study, Fort Polk, Louisiana,

    Science.gov (United States)

    1977-06-01

    regardless of experience, to avoid wasted man -hours. The main problem at Fort Polk is that no blocking and bracing material stockpile exists and no...ti1 hottul only thtrough the 0111crinost hole; to defect within 20 days after it is determined to -tuit Owt ttrtk in tuse. III thle caste of classes 3...wheels, slipping, or similar trak (meh causes. 1 -------------------- (12) " Shelly spots" means a condition 2 ------------------------ % where a thin

  3. 78 FR 78380 - Notice of Inventory Completion: U.S. Department of the Interior, National Park Service, Fort...

    Science.gov (United States)

    2013-12-26

    ... completion of an inventory of human remains under the control of Fort Bowie National Historic Site, Bowie, AZ....R50000] Notice of Inventory Completion: U.S. Department of the Interior, National Park Service, Fort... completed an inventory of human remains, in consultation with the appropriate Indian tribes or Native...

  4. A new small modular high-temperature gas-cooled reactor plant concept based on proven technology

    International Nuclear Information System (INIS)

    McDonald, C.F.; Goodjohn, A.J.

    1982-01-01

    Based on the established and proven high-temperature gas-cooled reactor (HTGR) technologies from the Peach Bottom 1 and Fort St. Vrain utility-operated units, a new small modular HTGR reactor is currently being evaluated. The basic nuclear reactor heat source, with a prismatic core, is being designed so that the decay heat can be removed by passive means (i.e., natural circulation). Although this concept is still in the preconceptual design stage, emphasis is being placed on establishing an inherently safe or benign concept which, when engineered, will have acceptable capital cost and power generation economics. The proposed new HTGR concept has a variety of applications, including electrical power generation, cogeneration, and high-temperature process heat. This paper discusses the simplest application, i.e., a steam Rankine cycle electrical power generating version. The gas-cooled modular reactor concepts presented are based on a graphite moderated prismatic core of low-power density (i.e., 4.1 W/cm 3 ) with a thermal rating of 250 MW(t). With the potential for inherently safe characteristics, a new small reactor could be sited close to industrial and urban areas to provide electrical power and thermal heating needs (i.e., district and space heating). Incorporating a multiplicity of small modular units to provide a larger power output is also discussed. The potential for a small, inherently safe HTGR reactor concept is highlighted

  5. Fra erfaringer til betydninger: Tolkning af fortællinger om eksamensgruppebegivenheder fra folkeskolelærerstuderende ved Aalborg Seminarium

    DEFF Research Database (Denmark)

    Silleborg, Ellen

    2004-01-01

    karakter. Denne situation giveruoverensstemmelser i de studerendes følelsesliv, og hovedparten af fortællingerne afspejler en i mange henseender konfliktfyldt eksamensgruppeproces. I fortællingernes betydninger ses en loyal men privatiseret etik, hvor ansvarlighed bliver til selvskyld. Alle implicerede...

  6. La fouille du fort Saint-Georges à Chinon (Indre-et-Loire. Premiers résultats The excavation of fort Saint-Georges at Chinon (Indre-et-Loire. First results

    Directory of Open Access Journals (Sweden)

    Bruno Dufaÿ

    2006-05-01

    Full Text Available Cette note présente les premiers résultats des fouilles menées en 2003 et 2004 sur la quasi-totalité du fort Saint-Georges à Chinon (Indre-et-Loire. Celui-ci est l’un des trois éléments de la forteresse médiévale qui domine la ville. La fouille a permis de préciser la fonction du fort, construit dans la deuxième moitié du XIIe s., à l’époque où Chinon est le centre administratif des possessions continentales des Plantagenêt, rois d’Angleterre. Du point de vue militaire, il formait une fortification avancée, protégeant le château principal, selon une structure que Richard Cœur de Lion appliquera au Château Gaillard. À l’intérieur, de vastes bâtiments constituaient des logis, conçus peut-être au départ pour héberger la chancellerie royale.This article presents the first results of the excavations undertaken in 2003 and 2004 over almost all of the Fort Saint-Georges at Chinon (Indre-et-Loire, one of three elements of the medieval fortress which dominates the town. The excavation enabled us to clarify the function of the fort, built in the 2nd half of the 12th century at a time when Chinon was the administrative centre of the continental possesions of the Plantagenet King of England. From a military point of view, it formed an advanced fortification protecting the main castle, within a structure that Richard the Lionheart would apply to the Chayeau Gaillard. Inside, some vast buildings made up the dwellings, designed perhaps initially to house the royal chanceller.

  7. Airborne electromagnetic data and processing within Leach Lake Basin, Fort Irwin, California: Chapter G in Geology and geophysics applied to groundwater hydrology at Fort Irwin, California

    Science.gov (United States)

    Bedrosian, Paul A.; Ball, Lyndsay B.; Bloss, Benjamin R.; Buesch, David C.

    2014-01-01

    From December 2010 to January 2011, the U.S. Geological Survey conducted airborne electromagnetic and magnetic surveys of Leach Lake Basin within the National Training Center, Fort Irwin, California. These data were collected to characterize the subsurface and provide information needed to understand and manage groundwater resources within Fort Irwin. A resistivity stratigraphy was developed using ground-based time-domain electromagnetic soundings together with laboratory resistivity measurements on hand samples and borehole geophysical logs from nearby basins. This report releases data associated with the airborne surveys, as well as resistivity cross-sections and depth slices derived from inversion of the airborne electromagnetic data. The resulting resistivity models confirm and add to the geologic framework, constrain the hydrostratigraphy and the depth to basement, and reveal the distribution of faults and folds within the basin.

  8. 77 FR 37318 - Eighth Coast Guard District Annual Safety Zones; Sound of Independence; Santa Rosa Sound; Fort...

    Science.gov (United States)

    2012-06-21

    ...-AA00 Eighth Coast Guard District Annual Safety Zones; Sound of Independence; Santa Rosa Sound; Fort... Coast Guard will enforce a Safety Zone for the Sound of Independence event in the Santa Rosa Sound, Fort... during the Sound of Independence. During the enforcement period, entry into, transiting or anchoring in...

  9. Forest pathology and entomology at Fort Valley Experimental Forest

    Science.gov (United States)

    Brian W. Geils

    2008-01-01

    Forest pathology and entomology have been researched at Fort Valley Experimental Forest throughout its history. The pathogens and insects of particular interest are mistletoes, decay and canker fungi, rusts, bark beetles, and various defoliators. Studies on life history, biotic interactions, impacts, and control have been published and incorporated into silvicultural...

  10. Evaluation of Codisposal Viability for TH/U Carbide (Fort Saint Vrain HTGR) DOE-Owned Fuel

    International Nuclear Information System (INIS)

    Radulescu, H.

    2001-01-01

    There are more than 250 forms of US Department of Energy (DOE)-owned spent nuclear fuel (SNF). Due to the variety of the spent nuclear fuel, the National Spent Nuclear Fuel Program has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. The Fort Saint Vrain reactor (FSVR) SNF has been designated as the representative fuel for the Th/U carbide fuel group. The FSVR SNF consists of small particles (spheres of the order of 0.5-mm diameter) of thorium carbide or thorium and high-enriched uranium carbide mixture, coated with multiple, thin layers of pyrolytic carbon and silicon carbide, which serve as miniature pressure vessels to contain fission products and the U/Th carbide matrix. The coated particles are bound in a carbonized matrix, which forms fuel rods or ''compacts'' that are loaded into large hexagonal graphite prisms. The graphite prisms (or blocks) are the physical forms that are handled in reactor loading and unloading operations, and which will be loaded into the DOE standardized SNF canisters. The results of the analyses performed will be used to develop waste acceptance criteria. The items that are important to criticality control are identified based on the analysis needs and result sensitivities. Prior to acceptance to fuel from the Th/U carbide fuel group for disposal, the important items for the fuel types that are being considered for disposal under the Th/U carbide fuel group must be demonstrated to satisfy the conditions determined in this report

  11. Evaluation of Codisposal Viability for TH/U Carbide (Fort Saint Vrain HTGR) DOE-Owned Fuel

    Energy Technology Data Exchange (ETDEWEB)

    H. radulescu

    2001-09-28

    There are more than 250 forms of US Department of Energy (DOE)-owned spent nuclear fuel (SNF). Due to the variety of the spent nuclear fuel, the National Spent Nuclear Fuel Program has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. The Fort Saint Vrain reactor (FSVR) SNF has been designated as the representative fuel for the Th/U carbide fuel group. The FSVR SNF consists of small particles (spheres of the order of 0.5-mm diameter) of thorium carbide or thorium and high-enriched uranium carbide mixture, coated with multiple, thin layers of pyrolytic carbon and silicon carbide, which serve as miniature pressure vessels to contain fission products and the U/Th carbide matrix. The coated particles are bound in a carbonized matrix, which forms fuel rods or ''compacts'' that are loaded into large hexagonal graphite prisms. The graphite prisms (or blocks) are the physical forms that are handled in reactor loading and unloading operations, and which will be loaded into the DOE standardized SNF canisters. The results of the analyses performed will be used to develop waste acceptance criteria. The items that are important to criticality control are identified based on the analysis needs and result sensitivities. Prior to acceptance to fuel from the Th/U carbide fuel group for disposal, the important items for the fuel types that are being considered for disposal under the Th/U carbide fuel group must be demonstrated to satisfy the conditions determined in this report.

  12. Bioequivalence of fixed-dose combination Myrin®-P Forte and reference drugs in loose combination.

    Science.gov (United States)

    Wang, H F; Wang, R; O'Gorman, M; Crownover, P; Naqvi, A; Jafri, I

    2013-12-01

    Myrin®-P Forte is a fixed-dose combination (FDC) tablet containing rifampicin (RMP, 150 mg), isoniazid (INH, 75 mg), ethambutol (EMB) hydrochloride (275 mg) and pyrazinamide (PZA, 400 mg) developed for the treatment of tuberculosis (TB). This study was conducted at a single centre--the Pfizer Clinical Research Unit in Singapore. To demonstrate the bioequivalence of each drug component of the Myrin-P Forte FDC and the individual product in loose combination. In a randomized, open-label, single-dose, two-way, crossover study, subjects received single doses of Myrin-P Forte or four individual products under fasting conditions in a crossover fashion with at least 7 days washout between doses. The primary measures for comparison were peak plasma concentration (C(max)) and the area under plasma concentration-time curve (AUC). Of 36 subjects enrolled, 35 completed the study. The adjusted geometric mean ratios and 90% confidence intervals for C(max) and AUC values were completely contained within bioequivalence limits (80%, 125%) for all four drugs in both formulations. Both treatments were generally well tolerated in the study. The Myrin-P Forte FDC tablet formulation is bioequivalent to the four single-drug references for RMP, INH, EMB hydrochloride and PZA at equivalent doses.

  13. Renewable Energy Opportunities at Fort Hood, Texas

    Energy Technology Data Exchange (ETDEWEB)

    Chvala, William D.; Warwick, William M.; Dixon, Douglas R.; Solana, Amy E.; Weimar, Mark R.; States, Jennifer C.; Reilly, Raymond W.

    2008-06-30

    The document provides an overview of renewable resource potential at Fort Hood based primarily upon analysis of secondary data sources supplemented with limited on-site evaluations. The effort was funded by the U.S. Army Installation Management Command (IMCOM) as follow-on to the 2005 DoD Renewables Assessment. This effort focuses on grid-connected generation of electricity from renewable energy sources and also ground source heat pumps for heating and cooling buildings, as directed by IMCOM.

  14. Calculation of Void in the Fort Saint Vrain Material

    Energy Technology Data Exchange (ETDEWEB)

    Potter, David Charles [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Taylor, Craig Michael [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Coons, James Elmer [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-05-11

    The percent void of the Fort Saint Vrain (FSV) material is estimated to be 21.1% based on the volume of the gap at the top of the drums, the volume of the coolant channels in the FSV fuel element, and the volume of the fuel handling channel in the FSV fuel element.

  15. Hydrogeochemical cycling and chemical denudation in the Fort River Watershed, central Massachusetts: An appraisal of mass-balance studies

    Science.gov (United States)

    Yuretich, Richard F.; Batchelder, Gail L.

    1988-01-01

    The Fort River watershed in central Massachusetts receives precipitation with a composition similar to that in Hubbard Brook (New Hampshire), yet the average stream water chemistry is substantially different, showing higher pH and TDS. This is largely a function of bedrock and surficial geology, and chemical differences among small streams within the Fort River watershed are apparently controlled by the composition and thickness of the prevailing surficial cover. The surficial deposits determine groundwater and surface water flow paths, thereby affecting the resultant contact time with mineral matter and the chemistry of the runoff. Despite the rural setting, over 95% of the annual sodium and chloride in the streams comes from road salt; after correcting for this factor, cation denudation rates are about equal to those at Hubbard Brook. However, silica removal is occurring at a rate more than 30% greater in the Fort River. When climatic conditions in Hubbard Brook and Fort River are normalized, weathering rates appear consistently higher in the Fort River, reflecting differences in weathering processes (i.e., cation exchange and silicate breakdown) and hydrogeology. Because of uncertainties in mechanisms of cation removal from watersheds, the silica denudation rate may be a better index of weathering intensity.

  16. Sustainability Analysis of the Water Resources and Supply of the Vieux Fort Region of Saint Lucia

    Science.gov (United States)

    Coles, D.; Johnson, B.; Morgan, F.

    2005-05-01

    In the Vieux Fort region of the Caribbean island of St. Lucia, water needs are becoming acute. The water supply shortfalls during the dry season will continue to grow as population and development increase, unless action is taken. Actions to address the problem should include measures to optimize the present water delivery system and the development of a new supply, through new intakes, groundwater, or reservoir construction. An investigation into the potential for groundwater resources using electrical resistivity soundings indicated a likely pervasive, shallow aquitard of clay materials below the water table; the shallowness of this aquitard virtually precludes the existence of productive perched aquifers. Consequently, a model of Grande Riviere du Vieux Fort (Big Vieux Fort River) seasonal surface-water flow was developed, based on a digital elevation model and rainfall data, allowing us to analyze the possible productivity of any new intakes placed along the river. A specific site downstream of the present intake was recommended for potential development. Recommendations were given for short, medium and long-term development of the resources and supply of the Vieux Fort region of southern St. Lucia.

  17. Energy efficiency campaign for residential housing at the Fort Lewis army installation

    Energy Technology Data Exchange (ETDEWEB)

    AH McMakin; RE Lundgren; EL Malone

    2000-02-23

    In FY1999, Pacific Northwest National Laboratory conducted an energy efficiency campaign for residential housing at the Fort Lewis Army Installation near Tacoma, Washington. Preliminary weather-corrected calculations show energy savings of 10{percent} from FY98 for energy use in family housing. This exceeded the project's goal of 3{percent}. The work was funded by the U.S. DOEs Federal Energy Management Program (FEMP), Office of Energy Efficiency and Renewable Energy. The project adapted FEMP's national ``You Have the Power Campaign'' at the local level, tailoring it to the military culture. The applied research project was designed to demonstrate the feasibility of tailored, research-based strategies to promote energy conservation in military family housing. In contrast to many energy efficiency efforts, the campaign focused entirely on actions residents could take in their own homes, as opposed to technology or housing upgrades. Behavioral change was targeted because residents do not pay their own utility bills; thus other motivations must drive personal energy conservation. This campaign augments ongoing energy savings from housing upgrades carried out by Fort Lewis. The campaign ran from September 1998 through August 1999. The campaign strategy was developed based on findings from previous research and on input from residents and officials at Fort Lewis. Energy use, corrected to account for weather differences, was compared with the previous year's use. Survey responses from 377 of Fort Lewis residents of occupied housing showed that the campaign was moderately effective in promoting behavior change. Of those who were aware of the campaign, almost all said they were now doing one or more energy-efficient things that they had not done before. Most people were motivated by the desire to do the right thing and to set a good example for their children. They were less motivated by other factors.

  18. Master Environmental Plan: Fort Wingate Depot Activity, Gallup, New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Biang, C.A.; Yuen, C.R.; Biang, R.P.; Antonopoulos, A.A.; Ditmars, J.D.

    1990-12-01

    The master environmental plan is based on an environmental assessment of the areas requiring environmental evaluation (AREEs) at Fort Wingate Depot Activity near Gallup, New Mexico. The Fort Wingate Depot Activity is slated for closure under the Base Closure and Realignment Act, Public Law 100--526. The MEP assesses the current status, describes additional data requirements, recommends actions for the sites, and establishes a priority order for actions. The plan was developed so that actions comply with hazardous waste and water quality regulations of the State of New Mexico and applicable federal regulations. It contains a brief history of the site, relevant geological and hydrological information, and a description of the current status for each AREE along with a discussion of the available site-specific data that pertain to existing or potential contamination and the impact on the environment. 35 refs., 27 figs., 23 tabs.

  19. Assessment of DOD Wounded Warrior Matters -- Fort Drum

    Science.gov (United States)

    2011-09-30

    their relation to military duties. The six factors that are evaluated are: physical capacity or stamina , upper extremities, lower extremities...Health Net Federal Services contractor. The Fort Drum MEDDAC Referral Management Office created a “Reports Cell ” which was responsible for obtaining...Care Division had created a CLR/Reports Cell group that focused specifically on obtaining CLRs, inputting them into patients’ AHLTA records and

  20. Thunderstorm and Lightning Studies using the FORTE Optical Lightning System (FORTE/OLS)

    International Nuclear Information System (INIS)

    Argo, P.; Franz, R.; Green, J.; Guillen, J.L.; Jacobson, A.R.; Kirkland, M.; Knox, S.; Spalding, R.; Suszcynsky, D.M.

    1999-01-01

    Preliminary observations of simultaneous RF and optical emissions from lightning as seen by the FORTE spacecraft are presented. RF/optical pairs of waveforms are routinely collected both as individual lightning events and as sequences of events associated with cloud-to-ground (CG) and intra-cloud (IC) flashes. CG pulses can be distinguished from IC pulses based on the properties of the RF and optical waveforms, but mostly based on the associated RF spectrograms. The RF spectrograms are very similar to previous ground-based VHF observations of lightning and show signatures associated with return strokes, stepped and dart leaders, and attachment processes,. RF emissions are observed to precede the arrival of optical emissions at the satellite by a mean value of 280 microseconds. The dual phenomenology nature of these observations are discussed in terms of their ability to contribute to a satellite-based lightning monitoring mission

  1. Thunderstorm and Lightning Studies using the FORTE Optical Lightning System (FORTE/OLS)

    Energy Technology Data Exchange (ETDEWEB)

    Argo, P.; Franz, R.; Green, J.; Guillen, J.L.; Jacobson, A.R.; Kirkland, M.; Knox, S.; Spalding, R.; Suszcynsky, D.M.

    1999-02-01

    Preliminary observations of simultaneous RF and optical emissions from lightning as seen by the FORTE spacecraft are presented. RF/optical pairs of waveforms are routinely collected both as individual lightning events and as sequences of events associated with cloud-to-ground (CG) and intra-cloud (IC) flashes. CG pulses can be distinguished from IC pulses based on the properties of the RF and optical waveforms, but mostly based on the associated RF spectrograms. The RF spectrograms are very similar to previous ground-based VHF observations of lightning and show signatures associated with return strokes, stepped and dart leaders, and attachment processes,. RF emissions are observed to precede the arrival of optical emissions at the satellite by a mean value of 280 microseconds. The dual phenomenology nature of these observations are discussed in terms of their ability to contribute to a satellite-based lightning monitoring mission.

  2. Final Sampling and Analysis Plan for Background Sampling, Fort Sheridan, Illinois

    National Research Council Canada - National Science Library

    1995-01-01

    .... This Background Sampling and Analysis Plan (BSAP) is designed to address this issue through the collection of additional background samples at Fort Sheridan to support the statistical analysis and the Baseline Risk Assessment (BRA...

  3. Strategic Energy Management Plan For Fort Buchanan, Puerto Rico

    Energy Technology Data Exchange (ETDEWEB)

    Parker, Steven A.; Hunt, W. D.

    2001-10-31

    This document reports findings and recommendations as a result of a design assistance project with Fort Buchanan with the goals of developing a Strategic Energy Management Plan for the Site. A strategy has been developed with three major elements in mind: 1) development of a strong foundation from which to build, 2) understanding technologies that are available, and 3) exploring financing options to fund the implementation of improvements. The objective of this report is to outline a strategy that can be used by Fort Buchanan to further establish an effective energy management program. Once a strategy is accepted, the next step is to take action. Some of the strategies defined in this Plan may be implemented directly. Other strategies may require the development of a more sophisticated tactical, or operational, plan to detail a roadmap that will lead to successful realization of the goal. Similarly, some strategies are not single events. Rather, some strategies will require continuous efforts to maintain diligence or to change the culture of the Base occupants and their efforts to conserve energy resources.

  4. Site Investigations with the Site Characterization and Analysis Penetrator System at Fort Dix, New Jersey

    Science.gov (United States)

    1993-07-01

    rod system or through a tremie tube ; both procedures were used interchangeably at Fort Dix to demon- strate the efficiency and effectiveness of each...allows delivery through either a l/4-in.-diam grout tube or a 3/8-in.-diam rout tube . The grout used at Fort Dix consisted of a mixture of water and... microfine , blended Portland cement (Lehigh Geocem’, Leeds, Alabama). The grout is a suspension of a uniformly produced cement clinker interground with

  5. Thermal protection system for the concrete core support floor at Fort St. Vrain

    International Nuclear Information System (INIS)

    Jones, H.; Hedgecock, P.D.

    1976-01-01

    A unique feature of the Fort St. Vrain HTGR is its steel jacketed concrete core support floor. The construction of this floor generally resembles that of the prestressed concrete reactor vessel, but its location immediately below the core hot gas outlets generates some particularly severe thermal protection requirements. A thermal barrier is used over the entire outer surface of the floor and in the twelve hot gas ducts which convey the primary coolant through the floor to the steam generators. A cooling water system of square tubes welded to the inside of the steel jacket is used to remove that heat which does pass through the thermal barrier and to maintain the concrete at acceptable temperatures. The design approach to the floor itself and to the thermal barriers and cooling system will be described, but the main emphasis of the paper will be on the total experience gained during construction and pre-operational testing. A particular problem experienced during construction was leakage from some cooling tubes, after their embedment in concrete. The solution to that problem was to develop a method for injecting catalyzed epoxy into the leaking tube. This method, which has general usefulness for in-service repairs, will be described. (author)

  6. Fort Lewis natural gas and fuel oil energy baseline and efficiency resource assessment

    International Nuclear Information System (INIS)

    Brodrick, J.R.; Daellenbach, K.K.; Parker, G.B.; Richman, E.E.; Secrest, T.J.; Shankle, S.A.

    1993-02-01

    The mission of the US Department of Energy (DOE) Federal Energy Management Program (FEMP) is to lead the improvement of energy efficiency and fuel flexibility within the federal sector. Through the Pacific Northwest Laboratory (PNL), FEMP is developing a fuel-neutral approach for identifying, evaluating, and acquiring all cost-effective energy projects at federal installations; this procedure is entitled the Federal Energy Decision Screening (FEDS) system. Through a cooperative program between FEMP and the Army Forces Command (FORSCOM) for providing technical assistance to FORSCOM installations, PNL has been working with the Fort Lewis Army installation to develop the FEDS procedure. The natural gas and fuel oil assessment contained in this report was preceded with an assessment of electric energy usage that was used to implement a cofunded program between Fort Lewis and Tacoma Public Utilities to improve the efficiency of the Fort's electric-energy-using systems. This report extends the assessment procedure to the systems using natural gas and fuel oil to provide a baseline of consumption and an estimate of the energy-efficiency potential that exists for these two fuel types at Fort Lewis. The baseline is essential to segment the end uses that are targets for broad-based efficiency improvement programs. The estimated fossil-fuel efficiency resources are estimates of the available quantities of conservation for natural gas, fuel oils number-sign 2 and number-sign 6, and fuel-switching opportunities by level of cost-effectiveness. The intent of the baseline and efficiency resource estimates is to identify the major efficiency resource opportunities and not to identify all possible opportunities; however, areas of additional opportunity are noted to encourage further effort

  7. Inpatient Behavioral Health Recapture A Busiess Case Analysis at Evans Army Community Hospital Fort Carson, Colorado

    Science.gov (United States)

    2009-07-20

    and Obstetrics /Gynecology. Inpatient care includes Obstetrics , Intensive Care, and Post Anesthesia Care/Same Day Surgery. EACH Mission: Delivering...charged with murder in Iraq shooting deaths, 2009). EACH Inpt Psych 13 Fort Carson has not been immune to the increase in suicides and violence among...to identify Soldiers with PTSD symptoms. In 2008, however, attention returned to Fort Carson as a number of local homicides and other violence tied

  8. The health of loblolly pine stands at Fort Benning, GA

    Science.gov (United States)

    Soung-Ryoul Ryu; G. Geoff Wang; Joan L. Walker

    2013-01-01

    Approximately two-thirds of the red-cockaded woodpecker (Picoides borealis) (RCW) groups at Fort Benning, GA, depend on loblolly pine (Pinus taeda) stands for nesting or foraging. However, loblolly pine stands are suspected to decline. Forest managers want to replace loblolly pine with longleaf pine (P. palustris...

  9. 77 FR 57112 - Notice of Inventory Completion: U.S. Department of Defense, Army, Fort Sill Museum, Lawton, OK

    Science.gov (United States)

    2012-09-17

    ... Landmark and Museum, U.S. Army Fires Center of Excellence, Fort Sill, OK 73503, telephone (580) 442-6570... trapping, 3 metal rings, 2 metal rivets, 17 metal nails, 53 metal bracelets, 1 metal pail, 1,500 glass... A. Neel, Director, Fort Sill National Historic Landmark and Museum, U.S. Army Fires Center of...

  10. Informal report on measurements of slant TEC by FORTE

    International Nuclear Information System (INIS)

    Massey, R.S.

    1997-01-01

    Los Alamos National Laboratory's Space and Atmospheric Sciences group is now operating the FORTE satellite, which has two sets of instruments: optical detectors and radio detectors. In this report the author describes work with one set of radio detectors that allow measurements of the total electron content (TEC) traversed by VHF radiation originating at an electromagnetic pulse (EMP) generator located at Los Alamos

  11. Assessment of DoD Wounded Warrior Matters -- Fort Riley

    Science.gov (United States)

    2013-08-06

    acceptable excuses included At Remote Care, Regular Leave, Maternity and Paternity Leave, Terminal Leave, Permanent Change of Station, and Transferred to...risk of negative medication interactions and reactions for Soldiers assigned to the Fort Riley WTB. B.2. Background The Joint Commission, an...reconciliation is to minimize medication errors such as omissions, duplications, dosing errors, and drug interactions . Medical reconciliation should

  12. Tile forts of the Liesbeeck Frontier | Sleigh | Scientia Militaria: South ...

    African Journals Online (AJOL)

    Scientia Militaria: South African Journal of Military Studies. Journal Home · ABOUT THIS JOURNAL · Advanced Search · Current Issue · Archives · Journal Home > Vol 27 (1997) >. Log in or Register to get access to full text downloads. Username, Password, Remember me, or Register. Tile forts of the Liesbeeck Frontier.

  13. 77 FR 24579 - Establishment of the Fort Ord National Monument

    Science.gov (United States)

    2012-04-25

    ... 1775-1776, Anza established the first overland route from ``New Spain,'' as Mexico was then known, to..., approximately 6 miles of which pass through the Fort Ord area. Although much of the historic route currently... tourists and recreationalists from near and far, and enhance its unique natural resources, for the...

  14. The Forte Kreis : an Attempt to Spiritual Leadership over Europe

    NARCIS (Netherlands)

    Poorthuis, Marcel

    2017-01-01

    Just before the outbreak of World War 1, a group of writers, artists and philosophers decided to establish a spiritual rule over Europe, the Forte Kreis. The group aimed at a reconciliation in Europe, by establishing pacifism, but also between East and West by creating a new language. Their thoughts

  15. 22nd Spring Research Festival Showcases Fort Detrick Science | Poster

    Science.gov (United States)

    Rainy weather couldn’t dampen the spirits of visitors to the 2018 Spring Research Festival, which brought together scientists from the Frederick National Laboratory (FNL), NCI at Frederick, and the U.S. Army Medical Research and Materiel Command (USAMRMC) and showcased the important research that takes place every day at Fort Detrick.

  16. Fort Valley studies: A natural laboratory for research and education

    Science.gov (United States)

    Brian W. Geils

    2008-01-01

    Drought, wildfire, extinction, and invasive species are considered serious threats to the health of our forests. Although these issues have global connections, we most readily see their consequences locally and attempt to respond with management based on science. For 100 years, the Fort Valley Experimental Forest (FVEF) has provided educational and experimental support...

  17. How confident is Fort McKay that industry can reclaim oil sand development

    Energy Technology Data Exchange (ETDEWEB)

    Fitzpatrick, C. [Fort McKay First Nations, AB (Canada)

    2004-02-05

    This presentation described how traditional environmental knowledge (TEK) can provide valuable information for both the reclamation design and assessment of oil sand development in Fort McKay. Conservation is valued by the Fort McKay First Nations communities who claim that current reclamation methods are too slow, and that the land is not being brought back to its original use with the uniqueness of the boreal landscape. Elders have noted that each year the water level in the Athabasca River is lower. The blowing tailings and coke dust are causing trees to dye and driving animals away. There is concern that the animals that remain may not be safe to eat. The Fort McKay First Nation community has stated that it will view reclamation as a success only when it functions with proof over many generations. The major concerns include: salt in the water draining from reclaimed areas; salt in the soils of reclaimed area; muskeg cannot be recreated; and, the issue of whether cranberry, blueberry and streambank forest areas can be recreated, along with traditional medicinal plants. Other concerns include the loss of rivers such as the Beaver Creek and Tar River, and that the water in reclaimed areas may not be suitable for animals to live in or to drink. tabs., figs.

  18. How confident is Fort McKay that industry can reclaim oil sand development

    International Nuclear Information System (INIS)

    Fitzpatrick, C.

    2004-01-01

    This presentation described how traditional environmental knowledge (TEK) can provide valuable information for both the reclamation design and assessment of oil sand development in Fort McKay. Conservation is valued by the Fort McKay First Nations communities who claim that current reclamation methods are too slow, and that the land is not being brought back to its original use with the uniqueness of the boreal landscape. Elders have noted that each year the water level in the Athabasca River is lower. The blowing tailings and coke dust are causing trees to dye and driving animals away. There is concern that the animals that remain may not be safe to eat. The Fort McKay First Nation community has stated that it will view reclamation as a success only when it functions with proof over many generations. The major concerns include: salt in the water draining from reclaimed areas; salt in the soils of reclaimed area; muskeg cannot be recreated; and, the issue of whether cranberry, blueberry and streambank forest areas can be recreated, along with traditional medicinal plants. Other concerns include the loss of rivers such as the Beaver Creek and Tar River, and that the water in reclaimed areas may not be suitable for animals to live in or to drink. tabs., figs

  19. The Fort McMurray Demonstration Project in Social Marketing: theory, design, and evaluation.

    Science.gov (United States)

    Guidotti, T L; Ford, L; Wheeler, M

    2000-02-01

    The Fort McMurray Demonstration Project in Social Marketing is a multifaceted program that applies the techniques of social marketing to health and safety. This paper describes the origins of the project and the principles on which it was based. VENUE: Fort McMurray, in the province of Alberta, Canada, was selected because the community had several community initiatives already underway and the project had the opportunity to demonstrate "value added." The project is distinguished from others by a model that attempts to achieve mutually reinforcing effects from social marketing in the community as a whole and from workplace safety promotion in particular. Specific interventions sponsored by the project include a media campaign on cable television, public activities in local schools, a community safety audit, and media appearance by a mascot that provides visual identity to the project, a dinosaur named "Safetysaurus." The project integrated its activities with other community initiatives. The evaluation component emphasizes outcome measures. A final evaluation based on injury rates and attitudinal surveys is underway. Baseline data from the first round of surveys have been compiled and published. In 1995, Fort McMurray became the first city in North America to be given membership in the World Health Organization's Safe Community Network.

  20. 2009 Federal Emergency Management Agency (FEMA) Topographic LiDAR: Fort Kent, Maine

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Camp Dresser McKee Inc. contracted with Sanborn Map Company to provide LiDAR mapping services for Fort Kent, Maine. Utilizing multi-return systems, Light Detection...

  1. Bastion on the Border: Fort Bliss, 1854-1943

    Science.gov (United States)

    1993-01-01

    Journals , Record Group (RG) 165, Records of the War Department General and Special Staffs, National Archives, Washington, D.C. "’Richard Estrada, Border...it was the Fort Bliss garrison and the other troops deployed by Steever in the El Paso Patrol District that would have to provide the figurative glue ...little military value. For example, on March 30 three carloads of oats, flour , corn, and hay were dispatched; on April 7 fourteen carloads of hay, gasoline

  2. 76 FR 77684 - Establishment of the Fort Ross-Seaview Viticultural Area

    Science.gov (United States)

    2011-12-14

    ...; Treasury decision. SUMMARY: This Treasury decision establishes the 27,500-acre ``Fort Ross-Seaview... may purchase. DATES: Effective Date: January 13, 2012. FOR FURTHER INFORMATION CONTACT: Elisabeth C... may purchase. Establishment of a viticultural area is neither an approval nor an endorsement by TTB of...

  3. Dimensions of Velopharyngeal Space following Maxillary Advancement with Le Fort I Osteotomy Compared to Zisser Segmental Osteotomy: A Cephalometric Study

    Directory of Open Access Journals (Sweden)

    Furkan Erol Karabekmez

    2015-01-01

    Full Text Available The objectives of this study are to assess the velopharyngeal dimensions using cephalometric variables of the nasopharynx and oropharynx as well as to compare the Le Fort I osteotomy technique to Zisser’s anterior maxillary osteotomy technique based on patients’ outcomes within early and late postoperative follow-ups. 15 patients with severe maxillary deficiency treated with Le Fort I osteotomy and maxillary segmental osteotomy were assessed. Preoperative, early postoperative, and late postoperative follow-up lateral cephalograms, patient histories, and operative reports are reviewed with a focus on defined cephalometric landmarks for assessing velopharyngeal space dimension and maxillary movement (measured for three different tracing points. A significant change was found between preoperative and postoperative lateral cephalometric measurements regarding the distance between the posterior nasal spine and the posterior pharyngeal wall in Le Fort I osteotomy cases. However, no significant difference was found between preoperative and postoperative measurements in maxillary segmental osteotomy cases regarding the same measurements. The velopharyngeal area calculated for the Le Fort I osteotomy group showed a significant difference between the preoperative and postoperative measurements. Le Fort I osteotomy for advancement of upper jaw increases velopharyngeal space. On the other hand, Zisser’s anterior maxillary segmental osteotomy does not alter the dimension of the velopharyngeal space significantly.

  4. Opening remarks for the Fort Valley Centennial Celebration (P-53)

    Science.gov (United States)

    G. Sam Foster

    2008-01-01

    The Rocky Mountain Research Station recognizes and values the contributions of our scientists and collaborators for their work over the past century at Fort Valley Experimental Forest. With the help of our partners and collaborators, Rocky Mountain Research Station is working to improve coordination across its research Program Areas and Experimental Forests and Ranges...

  5. Field Demonstration of Aviation Turbine Fuel MIL-T-83133C, Grade JP-8 (NATO Code F-34), at Fort Bliss, TX

    Science.gov (United States)

    1992-09-01

    APO NY 09052 CDR US ARMY NATICK RD&E CTR DOD PROJ MGR, MOBILE ELECTRIC POWER ATTN: SATNC-US US ARMY TROOP SUPPORT COMMAND NATICK MA 01760-5020 ATUN ...US ARMY QUARTERMASTER SCHOOL ATUN : LOEA-PL (MR LeVAN) I ATTN: ATSM-CDM 1 NEW CUMBERLAND PA 17070 ATSM-PWD I FORT LEE VA 23801 PETROLEUM FIELD OFFICE...ARTILLERY CENTER US ARMY INFANTRY SCHOOL & FORT BLISS ATTN: ATSH-CD-MIS-M I ATUN : ATZC-ISL-PP 3 ATSH-CD-TSM-T 1 ATZC-ISL-MM 3 FORT BENNING GA 31905-5400

  6. Automated Environmental Data Collection at Fort Benning, Georgia, from May 1999 to July 2001

    National Research Council Canada - National Science Library

    Hahn, Charles

    2002-01-01

    The Department of Defense, Strategic Environmental Research and Development Program, Ecosystem Management Project, Ecosystem Characterization and Monitoring initiative Program at Fort Benning, Georgia...

  7. Archaeological Surveys and Evaluations of Four Construction Areas in the Vicinity of Fort Jackson, Plaquemines Parish, Louisiana

    Science.gov (United States)

    1992-04-01

    the officers’ quarters, a hospital, and an inspector’s quarters (Greene 1982:128-129). The fort itself was a regular pentagon with bastions at each...Outside of the moat another brick wall was constructed, facing a second ditch. A bridge over the second ditch led southward to a water battery whose...Archaeological Swrveys and Evaluations at Fort Jackson du Pratz, Le Page 1975 The History of Louisiana. Louisiana American Revolution Bicentennial Commission

  8. DIGITAL PRESERVATION OF THE QUON SANG LUNG LAUNDRY BUILDING, FORT MACLEOD, ALBERTA

    Directory of Open Access Journals (Sweden)

    P. Dawson

    2017-08-01

    Full Text Available This paper describes the results of an emergency recording and archiving of a historic structure in Southern Alberta and explores the lessons learned. Digital recording of the Quon Sang Lung Laundry building in Fort Macleod, Alberta, was a joint initiative between Alberta Culture and Tourism and the University of Calgary. The Quon Sang Lung Laundry was a boomtown-style wood structure situated in the Fort Macleod Provincial Historic Area, Alberta. Built in the mid-1800s, the structure was one of the four buildings comprising Fort Macleod’s Chinatown. Its association with Chinese immigration, settlement, and emergence of Chinese-owned businesses in early twentieth-century Alberta, made the Quon Sang Lung Laundry a unique and very significant historic resource. In recent years, a condition assessment of the structure indicated that the building was not safe and that the extent of the instability could lead to a sudden collapse. In response, Alberta Culture and Tourism engaged the Departments of Anthropology and Archaeology and Geomatics Engineering from the University of Calgary, to digitally preserve the laundry building. A complete survey including the laser scanning of all the remaining elements of the original structure, was undertaken. Through digital modeling, the work guarantees that a three-dimensional representation of the building is available for future use. This includes accurate 3D renders of the exterior and interior spaces and a collection of architectural drawings comprising floor plans, sections, and elevations.

  9. Le Fort III Distraction With Internal vs External Distractors: A Cephalometric Analysis.

    Science.gov (United States)

    Robertson, Kevin J; Mendez, Bernardino M; Bruce, William J; McDonnell, Brendan D; Chiodo, Michael V; Patel, Parit A

    2018-05-01

    This study compares the change in midface position following Le Fort III advancement using either rigid external distraction (group 1) or internal distraction (group 2). We hypothesized that, with reference to right-facing cephalometry, internal distraction would result in increased clockwise rotation and inferior displacement of the midface. Le Fort III osteotomies and standardized distraction protocols were performed on 10 cadaveric specimens per group. Right-facing lateral cephalograms were traced and compared across time points to determine change in position at points orbitale, anterior nasal spine (ANS), A-point, and angle ANB. Institutional. Twenty cadaveric head specimens. Standard subcranial Le Fort III osteotomies were performed from a coronal approach and adequately mobilized. The specified distraction mechanism was applied and advanced by 15 mm. Changes of position were calculated at various skeletal landmarks: orbitale, ANS, A-point, and ANB. Group 1 demonstrated relatively uniform x-axis advancement with minimal inferior repositioning at the A-point, ANS, and orbitale. Group 2 demonstrated marked variation in x-axis advancement among the 3 points, along with a significant inferior repositioning and clockwise rotation of the midface ( P External distraction resulted in more uniform advancement of the midface, whereas internal distraction resulted in greater clockwise rotation and inferior displacement. External distraction appears to provide increased vector control of the midface, which is important in creating a customized distraction plan based on the patient's individual occlusal and skeletal needs.

  10. Digital Preservation of the Quon Sang Lung Laundry Building, Fort Macleod, Alberta

    Science.gov (United States)

    Dawson, P.; Baradaran, F.; Jahraus, A.; Rubalcava, E.; Farrokhi, A.; Robinson, C.

    2017-08-01

    This paper describes the results of an emergency recording and archiving of a historic structure in Southern Alberta and explores the lessons learned. Digital recording of the Quon Sang Lung Laundry building in Fort Macleod, Alberta, was a joint initiative between Alberta Culture and Tourism and the University of Calgary. The Quon Sang Lung Laundry was a boomtown-style wood structure situated in the Fort Macleod Provincial Historic Area, Alberta. Built in the mid-1800s, the structure was one of the four buildings comprising Fort Macleod's Chinatown. Its association with Chinese immigration, settlement, and emergence of Chinese-owned businesses in early twentieth-century Alberta, made the Quon Sang Lung Laundry a unique and very significant historic resource. In recent years, a condition assessment of the structure indicated that the building was not safe and that the extent of the instability could lead to a sudden collapse. In response, Alberta Culture and Tourism engaged the Departments of Anthropology and Archaeology and Geomatics Engineering from the University of Calgary, to digitally preserve the laundry building. A complete survey including the laser scanning of all the remaining elements of the original structure, was undertaken. Through digital modeling, the work guarantees that a three-dimensional representation of the building is available for future use. This includes accurate 3D renders of the exterior and interior spaces and a collection of architectural drawings comprising floor plans, sections, and elevations.

  11. Early thinning experiments established by the Fort Valley Experimental Forest

    Science.gov (United States)

    Benjamin P. De Blois; Alex. J. Finkral; Andrew J. Sanchez Meador; Margaret M. Moore

    2008-01-01

    Between 1925 and 1936, the Fort Valley Experimental Forest (FVEF) scientists initiated a study to examine a series of forest thinning experiments in second growth ponderosa pine stands in Arizona and New Mexico. These early thinning plots furnished much of the early background for the development of methods used in forest management in the Southwest. The plots ranged...

  12. 78 FR 32699 - Notice of Intent To Rule on Request to Release Airport Property at the Fort Worth Spinks Airport...

    Science.gov (United States)

    2013-05-31

    ... to Release Airport Property at the Fort Worth Spinks Airport, Fort Worth, Texas AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of request to release airport property. SUMMARY: The FAA... the provisions of Section 125 of the Wendell H. Ford Aviation Investment Reform Act for the 21st...

  13. Feasibility Study for an Off-Post, Primary Care Clinic at Fort Campbell, Kentucky

    National Research Council Canada - National Science Library

    Kvalevog, Kristen J

    2005-01-01

    .... Over 90,679 beneficiaries currently live in -the-Fort Campbell-catchment area and receive primary care at Blanchfield Army Community Hospital through the Red, White, Blue, Gold, and Young Eagle Clinics...

  14. Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.

    Energy Technology Data Exchange (ETDEWEB)

    Natesan, K.; Majumdar, S.; Shankar, P. S.; Shah, V. N.; Nuclear Engineering Division

    2007-03-21

    In the coming decades, the United States and the entire world will need energy supplies to meet the growing demands due to population increase and increase in consumption due to global industrialization. One of the reactor system concepts, the Very High Temperature Reactor (VHTR), with helium as the coolant, has been identified as uniquely suited for producing hydrogen without consumption of fossil fuels or the emission of greenhouse gases [Generation IV 2002]. The U.S. Department of Energy (DOE) has selected this system for the Next Generation Nuclear Plant (NGNP) Project, to demonstrate emissions-free nuclear-assisted electricity and hydrogen production within the next 15 years. The NGNP reference concepts are helium-cooled, graphite-moderated, thermal neutron spectrum reactors with a design goal outlet helium temperature of {approx}1000 C [MacDonald et al. 2004]. The reactor core could be either a prismatic graphite block type core or a pebble bed core. The use of molten salt coolant, especially for the transfer of heat to hydrogen production, is also being considered. The NGNP is expected to produce both electricity and hydrogen. The process heat for hydrogen production will be transferred to the hydrogen plant through an intermediate heat exchanger (IHX). The basic technology for the NGNP has been established in the former high temperature gas reactor (HTGR) and demonstration plants (DRAGON, Peach Bottom, AVR, Fort St. Vrain, and THTR). In addition, the technologies for the NGNP are being advanced in the Gas Turbine-Modular Helium Reactor (GT-MHR) project, and the South African state utility ESKOM-sponsored project to develop the Pebble Bed Modular Reactor (PBMR). Furthermore, the Japanese HTTR and Chinese HTR-10 test reactors are demonstrating the feasibility of some of the planned components and materials. The proposed high operating temperatures in the VHTR place significant constraints on the choice of material selected for the reactor pressure vessel for

  15. 78 FR 3479 - Notice of Public Meeting of Fort Scott Council

    Science.gov (United States)

    2013-01-16

    ... submitted on cards that will be provided at the meeting, via mail to Laurie Fox, Presidio Trust, 103... stated prominently at the beginning of the comments. The Trust will make available for public inspection... PRESIDIO TRUST Notice of Public Meeting of Fort Scott Council AGENCY: The Presidio Trust. ACTION...

  16. Fort Hills Oil Sands Project No Net Loss Lake earthfill structure

    Energy Technology Data Exchange (ETDEWEB)

    Blakely, D.; Sawatsky, L. [Golder Associates Ltd., Calgary, AB (Canada); Wog, K.; Paz, S. [Alberta Environment, Edmonton, AB (Canada). Water Management Operations; Chernys, S. [Petro-Canada, Calgary, AB (Canada)

    2007-07-01

    The Fort Hills Oil Sands Project (FHOSP) is located north of Fort McMurray, Alberta. The Fort Hills Energy Corporation (FHEC) must compensate for fish habitat lost as a result of mine development that would disturb natural streams and lakes. FHEC planned to construct a fisheries compensation lake on the north end of its leased property, contained in part by an earthfill structure. Unlike most dam structures, the FHOSP No Net Loss Lake (NNLL) earthfill structure was planned solely for the creation of fisheries compensation habitat. Therefore, the NNLL earthfill structure must be designed with robust features that can handle any foreseeable environmental condition without failure, so that it may be accepted as a sustainable feature of the mine closure landscape. This paper discussed the design features of the NNLL earthfill structure. The paper presented information on the background of the project including regulatory criteria for the fisheries compensation habitat; fisheries compensation habitat location; and design criteria for the NNLL. The features of the NNLL earthfill structure were also discussed. In addition, the paper outlined the dam safety classification for earthfill structure and anticipated system performance. The proposed monitoring program and permanent closure plans were also discussed. It was concluded that the earthfill structure was designed with several features that would allow it to become a part of the closure landscape. These included a high width to height ratio, significant erosion protection, and an aggressive reclamation plan. These features will provide a sound basis for FHEC to apply for a reclamation certificate at the end of mine life. 3 refs., 3 tabs., 8 figs.

  17. Fort Hood Building and Landscape Inventory with WWII and Cold War Context

    Science.gov (United States)

    2007-03-01

    barracks, 1970s (NARA)........................................................... 112 Figure 37. Palmer Movie Theater (NARA...revised 1953) showing layout of Hood Village and trailer park (Fort Hood...arms ammunition storage building #92012 (ERDC-CERL, 2004). ......... 260 Figure 163: Radio reception building #92063 (ERDC-CERL, 2004

  18. Vendor Payments-Operation Mongoose, Fort Belvoir Defense Accounting Office and Rome Operating Location

    National Research Council Canada - National Science Library

    Lane, F

    1996-01-01

    .... Due to the impending closure of the Defense Accounting Office at Fort Belvoir and the anticipated consolidation to the Rome Operating Location, New York, we did not perform a review of the management...

  19. Revised Geologic Map of the Fort Garland Quadrangle, Costilla County, Colorado

    Science.gov (United States)

    Wallace, Alan R.; Machette, Michael N.

    2008-01-01

    The map area includes Fort Garland, Colo., and the surrounding area, which is primarily rural. Fort Garland was established in 1858 to protect settlers in the San Luis Valley, then part of the Territory of New Mexico. East of the town are the Garland mesas (basalt-covered tablelands), which are uplifted as horsts with the Central Sangre de Cristo fault zone. The map also includes the northern part of the Culebra graben, a deep structural basin that extends from south of San Luis (as the Sanchez graben) to near Blanca, about 8 km west of Fort Garland. The oldest rocks exposed in the map area are early Proterozic basement rocks (granites in Ikes Creek block) that occupy an intermediate structural position between the strongly uplifted Blanca Peak block and the Culebra graben. The basement rocks are overlain by Oligocene volcanic and volcaniclastic rocks of unknown origin. The volcanic rocks were buried by a thick sequence of basin-fill deposits of the Santa Fe Group as the Rio Grande rift formed about 25 million years ago. The Servilleta Basalt, a regional series of 3.7?4.8 Ma old flood basalts, was deposited within sediment, and locally provides a basis for dividing the group into upper and lower parts. Landslide deposits and colluvium that rest on sediments of the Santa Fe Group cover the steep margins of the mesas. Exposures of the sediment beneath the basalt and within the low foothills east of the Central Sangre de Cristo fault zone are comprised of siltstones, sandstones, and minor fluvial conglomerates. Most of the low ground surrounding the mesas and in the graben is covered by surficial deposits of Quaternary age. The alluvial deposits are subdivided into three Pleistocene-age units and three Holocene-age units. The oldest Pleistocene gravel (unit Qao) is preserved as isolated remnants that cap high surfaces north and east of Fort Garland. The primary geologic hazards in the map area are from earthquakes, landslides, and localized flooding. The Central

  20. Fort Carson Building 1860 Biomass Heating Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    Hunsberger, Randolph [National Renewable Energy Lab. (NREL), Golden, CO (United States); Tomberlin, Gregg [National Renewable Energy Lab. (NREL), Golden, CO (United States); Gaul, Chris [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2015-09-01

    As part of the Army Net-Zero Energy Installation program, the Fort Carson Army Base requested that NREL evaluate the feasibility of adding a biomass boiler to the district heating system served by Building 1860. We have also developed an Excel-spreadsheet-based decision support tool--specific to the historic loads served by Building 1860--with which users can perform what-if analysis on gas costs, biomass costs, and other parameters. For economic reasons, we do not recommend adding a biomass system at this time.

  1. Basewide Energy Study, Fort Wainwright Alaska: Volume 1-Executive Summary

    Science.gov (United States)

    1982-04-01

    more accurate condensate wiett?Ing. 2.2 ENERGY OSAGE ANALISIS 4 top~down anay2ts was mad" of FY’•0 ener;’ uxage’ t Fort wrtsvrigFnt. The spporiIonments...vice, at each receptacle cluster . It should be thermally sensitlve. rtdtcing through-put from 600 watts at -SOOT to0soer power at 100? outside air

  2. Flood-inundation maps for the St. Marys River at Fort Wayne, Indiana

    Science.gov (United States)

    Menke, Chad D.; Kim, Moon H.; Fowler, Kathleen K.

    2012-01-01

    Digital flood-inundation maps for a 9-mile reach of the St. Marys River that extends from South Anthony Boulevard to Main Street at Fort Wayne, Indiana, were created by the U.S. Geological Survey (USGS) in cooperation with the City of Fort Wayne. The inundation maps, which can be accessed through the USGS Flood Inundation Mapping Science Web site, depict estimates of the areal extent of flooding corresponding to selected water levels (stages) at the USGS streamgage 04182000 St. Marys River near Fort Wayne, Ind. Current conditions at the USGS streamgages in Indiana may be obtained from the National Water Information System: Web Interface. In addition, the information has been provided to the National Weather Service (NWS) for incorporation into their Advanced Hydrologic Prediction Service (AHPS) flood warning system. The NWS forecasts flood hydrographs at many places that are often collocated at USGS streamgages. That forecasted peak-stage information, also available on the Internet, may be used in conjunction with the maps developed in this study to show predicted areas of flood inundation. In this study, water-surface profiles were simulated for the stream reach by means of a hydraulic one-dimensional step-backwater model. The model was calibrated using the most current stage-discharge relation at the USGS streamgage 04182000 St. Marys River near Fort Wayne, Ind. The hydraulic model was then used to simulate 11 water-surface profiles for flood stages at 1-ft intervals referenced to the streamgage datum and ranging from bankfull to approximately the highest recorded water level at the streamgage. The simulated water-surface profiles were then combined with a geographic information system digital elevation model (derived from Light Detection and Ranging (LiDAR) data) in order to delineate the area flooded at each water level. A flood inundation map was generated for each water-surface profile stage (11 maps in all) so that for any given flood stage users will be

  3. Management of Groin Abcess with Flaminal Forte and KerraMax Care

    Directory of Open Access Journals (Sweden)

    Maggie Pugh

    2016-04-01

    Full Text Available The patient’s dressing plan using Flaminal Forte and KerraMax Care successfully managed the complexities of his wound, absorbing exudate, reducing pain on dressing, malodour and wound bioburden. Moreover, the plan encouraged patient concordance, reduced nursing consultation time and subsequently altered treatment plans for our patients with abscesses

  4. Gynecologic Malignancies Post-LeFort Colpocleisis

    Directory of Open Access Journals (Sweden)

    Rayan Elkattah

    2014-01-01

    Full Text Available Introduction. LeFort colpocleisis (LFC is a safe and effective obliterative surgical option for older women with advanced pelvic organ prolapse who no longer desire coital activity. A major disadvantage is the limited ability to evaluate for post-LFC gynecologic malignancies. Methods. We present the first case of endometrioid ovarian cancer diagnosed after LFC and review all reported gynecologic malignancies post-LFC in the English medical literature. Results. This is the second reported ovarian cancer post-LFC and the first of the endometrioid subtype. A total of nine other gynecologic malignancies post-LFC have been reported in the English medical literature. Conclusions. Gynecologic malignancies post-LFC are rare. We propose a simple 3-step strategy in evaluating post-LFC malignancies.

  5. A Case Analysis of Energy Savings Performance Contract Projects and Photovoltaic Energy at Fort Bliss, El Paso, Texas

    Science.gov (United States)

    2006-06-01

    PHOTOVOLTAIC ENERGY AND FORT BLISS CASE BACKGROUND A. PHOTOVOLTAIC ENERGY The use of photovoltaic power systems is nothing new in the Department...against the Outback MPPT charge controller . This test will be done over a one month timeframe. The Arizona Power ISG test plan is contained in...cost-benefit analysis of conventional power versus emerging photovoltaic energy for the Army’s Fort Bliss in El Paso, TX. The project will also analyze

  6. Neurosensory changes of palatal mucousa following Le Fort I osteotomy

    Directory of Open Access Journals (Sweden)

    Bijan Movahedian Attar

    2009-09-01

    Full Text Available

    • BACKGROUND: This study evaluated the sensation of palatal ucosa before and after Le Fort I osteotomy and compared it based on whether greater palatine nerve has been dissected or not.
    • METHODS: Sixteen patients were studied within one week before  urgery and then one week, 6 weeks, 3 months and 6 months after surgery. Four tests including sharp-blunt discrimination, cold perception, pin prick sensation and electrical stimulation were performed.
    • RESULTS: Mean values of electrical stimulation were significantly higher 6 months after surgery (p < 0.05, on the other hand mean values of pin-prick sensation were significantly lower (p < 0.05. All patients regardless of the condition of greater palatine nerve were responsive to cold perception and sharp-blunt discrimination 6 months after surgery.
    • CONCLUSIONS: Following Le Fort I osteotomy, palatal  esponsiveness to electrical stimulation decreases and mechanical hyper sensitization occurs. Dissection of greater palatine nerve was shown to have no effect on the results.
    • KEYWORDS: Lefort I Osteotomy, Palatal Mocousa, Nerve Recovery.

  7. Freight Advanced Traveler Information System (FRATIS) - Dallas-Fort Worth (DFW) prototype : final report.

    Science.gov (United States)

    This is the Final Report for the FRATIS Dallas-Fort Worth DFW prototype system. The FRATIS prototype in : DFW consisted of the following components: optimization algorithm, terminal wait time, route specific : navigation/traffic/weather, and advanced...

  8. Scaling analysis of the coupled heat transfer process in the high-temperature gas-cooled reactor core

    International Nuclear Information System (INIS)

    Conklin, J.C.

    1986-08-01

    The differential equations representing the coupled heat transfer from the solid nuclear core components to the helium in the coolant channels are scaled in terms of representative quantities. This scaling process identifies the relative importance of the various terms of the coupled differential equations. The relative importance of these terms is then used to simplify the numerical solution of the coupled heat transfer for two bounding cases of full-power operation and depressurization from full-system operating pressure for the Fort St. Vrain High-Temperature Gas-Cooled Reactor. This analysis rigorously justifies the simplified system of equations used in the nuclear safety analysis effort at Oak Ridge National Laboratory

  9. 76 FR 22338 - Proposed Fort Ross-Seaview Viticultural Area; Comment Period Reopening

    Science.gov (United States)

    2011-04-21

    ... May 9, 2005, from all interested persons. In response to a request from a local wine industry member... the Fort Ross-Seaview viticultural area. Two local wine industry members supported the petition without qualification; a third industry member supported the viticultural area's establishment while...

  10. Archeological Testing Fort Hood: 1994-1995. Volume 2

    Science.gov (United States)

    1996-10-01

    ASSOCI TES, INC. (662-22) Archeological Testing at Fort Hood. 1994-199.5 569 -48-1941.1080-134 1935 -058 Figure 7.17 Selected Perforator Types: Awl and...Department of Anthropology, University of Arkansas. Huskey, V. 1935 An Archeological Survey of the Nueces Canyon of Texas, Bulletin of the Texas... epr 064lL.Tan I lms expected 08-FH1 Yellow 4 expected expedctd cd .9 15.Q W n• I less M 0 ~ *~Tax~on Total Total Inmr 53 nac na Vertebra.es 1. FcAuifnm

  11. Assessment of pterygomaxillary separation in Le Fort I Osteotomy in class III patients.

    Science.gov (United States)

    Ueki, Koichiro; Hashiba, Yukari; Marukawa, Kohei; Okabe, Katsuhiko; Alam, Shamiul; Nakagawa, Kiyomasa; Yamamoto, Etsuhide

    2009-04-01

    To examine the separation of the pterygomaxillary region at the posterior nasal spine level after Le Fort I osteotomy in Class III patients. The study group consisted of 37 Japanese patients with mandibular prognathism and asymmetry, with maxillary retrognathism or asymmetry. A total of 74 sides were examined. Le Fort I osteotomy was performed without a pterygoid osteotome, with an ultrasonic curette used to remove interference at the pterygomaxillary region. Postoperative computed tomography (CT) was analyzed for all patients. The separation of the pterygomaxillary region and the location of the descending palatine artery were assessed. Although acceptable separation between the maxilla and pterygoid plates was achieved in all patients, an exact separation of the pterygomaxillary junction at the posterior nasal spine level was found in only 18 of 74 sides (24%). In 29 of 74 sides (39.2%), the separation occurred anterior to the descending palatine artery. In 29 of 74 sides (39.2%), complete separation between the maxilla and lateral and/or medial pterygoid plate was not achieved, but lower level separation of the maxilla and pterygoid plate was always complete. The maxillary segments could be moved to the postoperative ideal position in all cases. Le Fort I osteotomy without an osteotome does not always induce an exact separation at the pterygomaxillary junction at the posterior nasal spine level, but the ultrasonic bone curette can remove the interference between maxillary segment and pterygoid plates more safely.

  12. Research, Development and Demonstration of Peak Load Reduction on Distribution Feeders Using Distributed Energy Resources for the City of Fort Collins

    Energy Technology Data Exchange (ETDEWEB)

    Sumner, Dennis [City of Fort Collins Utilities, CO (United States); Vosburg, Tom [City of Fort Collins Utilities, CO (United States); Brunner, Steve [Brendle Group, Fort Collins, CO (United States); Gates, Judy [Woodward, Inc., Fort Collins, CO (United States); Howard, Nathan [Spirae, Inc., Fort Collins, CO (United States); Merton, Andrew [Spirae, Inc., Fort Collins, CO (United States); Wright, Don [Spirae, Inc., Fort Collins, CO (United States); Birlingmair, Doug [Spirae, Inc., Fort Collins, CO (United States)

    2015-10-01

    This project titled “Research, Development and Demonstration of Peak Load Reduction on Distribution Feeders Using Distributed Energy Resources for the City of Fort Collins” evolved in response to the Department of Energy’s (DOE) Funding Opportunity Announcement (FOA) Number DE-PS26-07NT43119. Also referred to as the Fort Collins Renewable and Distributed System Integration (RDSI) Project, the effort was undertaken by a diverse group of local government, higher education and business organizations; and was driven by three overarching goals: I. Fulfill the requirements of the DOE FOA’s Area of Interest 2: Renewable and Distributed System Integration; most notably, to demonstrate the ability to reduce electric system distribution feeder peak load by 15% or more through the coordinated use of Distributed Energy Resources (DER). II. Advance the expertise, technologies and infrastructure necessary to support the long term vision of the Fort Collins Zero Energy District (FortZED) and move towards creating a zero energy district in the Fort Collins “Old Town” area. III. Further the goals of the City of Fort Collins Energy Policy, including the development of a Smart Grid-enabled distribution system in Fort Collins, expanded use of renewable energy, increased energy conservation, and peak load reduction. Through the collaborative efforts of the partner organizations, the Fort Collins RDSI project was successful in achieving all three of these goals. This report is organized into two distinct sections corresponding to the two phases of the project: • Part 1: Feeder Peak Load Reduction and the FortZED Initiative. • Part 2: Forming and Operating Utility Microgrids and Managing Load and Production Variability The original project scope addressed the Part 1 feeder peak load reduction. That work took place from 2009 through 2011 and was largely complete when the project scope was amended to include a demonstration of microgrid operations. While leveraging the

  13. A non-conventional procedure for the 3D modeling of WWI forts

    Science.gov (United States)

    Nocerino, E.; Fiorillo, F.; Minto, S.; Menna, F.; Remondino, F.

    2014-06-01

    2014 is the hundredth anniversary of the outbreak of the First World War (WWI) - or Great War - in Europe and a number of initiatives have been planned to commemorate the tragic event. Until 1918, the Italian Trentino - Alto Adige region was under the Austro - Hungarian Empire and represented one of the most crucial and bloody war front between the Austrian and Italian territories. The region borders were constellated of military fortresses, theatre of battles between the two opposite troops. Unfortunately, most of these military buildings are now ruined and their architectures can be hardly appreciated. The paper presents the initial results of the VAST project (VAlorizzazione Storia e Territorio - Valorization of History and Landscape), that aims to digitally reconstruct the forts located on the plateaus of Luserna, Lavarone and Folgaria. An integrated methodology has been adopted to collect and employ all possible source of information in order to derive precise and photo-realistic 3D digital representations of WWI forts.

  14. High Temperature Gas-Cooled Reactors Lessons Learned Applicable to the Next Generation Nuclear Plant

    Energy Technology Data Exchange (ETDEWEB)

    J. M. Beck; L. F. Pincock

    2011-04-01

    The purpose of this report is to identify possible issues highlighted by these lessons learned that could apply to the NGNP in reducing technical risks commensurate with the current phase of design. Some of the lessons learned have been applied to the NGNP and documented in the Preconceptual Design Report. These are addressed in the background section of this document and include, for example, the decision to use TRISO fuel rather than BISO fuel used in the Peach Bottom reactor; the use of a reactor pressure vessel rather than prestressed concrete found in Fort St. Vrain; and the use of helium as a primary coolant rather than CO2. Other lessons learned, 68 in total, are documented in Sections 2 through 6 and will be applied, as appropriate, in advancing phases of design. The lessons learned are derived from both negative and positive outcomes from prior HTGR experiences. Lessons learned are grouped according to the plant, areas, systems, subsystems, and components defined in the NGNP Preconceptual Design Report, and subsequent NGNP project documents.

  15. CORTAP: a coupled neutron kinetics-heat transfer digital computer program for the dynamic simulation of the high temperature gas cooled reactor core

    International Nuclear Information System (INIS)

    Cleveland, J.C.

    1977-01-01

    CORTAP (Core Transient Analysis Program) was developed to predict the dynamic behavior of the High Temperature Gas Cooled Reactor (HTGR) core under normal operational transients and postulated accident conditions. CORTAP is used both as a stand-alone component simulation and as part of the HTGR nuclear steam supply (NSS) system simulation code ORTAP. The core thermal neutronic response is determined by solving the heat transfer equations for the fuel, moderator and coolant in an average powered region of the reactor core. The space independent neutron kinetics equations are coupled to the heat transfer equations through a rapidly converging iterative technique. The code has the capability to determine conservative fuel, moderator, and coolant temperatures in the ''hot'' fuel region. For transients involving a reactor trip, the core heat generation rate is determined from an expression for decay heat following a scram. Nonlinear effects introduced by temperature dependent fuel, moderator, and coolant properties are included in the model. CORTAP predictions will be compared with dynamic test results obtained from the Fort St. Vrain reactor owned by Public Service of Colorado, and, based on these comparisons, appropriate improvements will be made in CORTAP

  16. Die opleiding van bedryfsielkundiges aan die universiteit van Fort Hare

    Directory of Open Access Journals (Sweden)

    W. Botha

    1977-11-01

    Full Text Available Die Departement Bedryfsielkunde aan die Universiteit van Fort Hare is 'n relatiewe jong departement en het eers in 1965 tot stand gekom. Voor hierdie datum is Bedryfsielkunde as 'n kort kursus deur die departement van suiwer Sielkunde aangebied en een van die destydse dosente, Dr. W. Backer, het die inisiatief geneem om 'n selfstandige departement van Bedryfsielkunde in die Fakulteit van Ekonomiese Wetenskappe op die been te bring.

  17. Reactor technology. Progress report, July-September 1980

    International Nuclear Information System (INIS)

    Breslow, M.

    1980-12-01

    Progress in the Space Power Advanced Reactor (SPAR) Program includes indications that revision of the BeO reflector configuration can reduce system weight. Observed boiling limit restrictions on the performance of the annular-wick core heat pipe have accelerated transition to the development of the target-design arterial heat pipe. Successful bends of core heat pipes have been made with sodium as the mandrel material. With the phasing out of the GCFR Program, work on the Low Power Safety Experiments Program is now concentrated on completion of the third 37-rod Full Length Subgroup test. In the Reactor Safety/Structural Analysis area, effort on the Category I Structures Program is toward developing an experimental test plan focusing on a specific structural design. Buckling experiments on thin-walled cylindrical shells with circular cutouts are reported. Results of a three-dimensional analysis of thermal stresses in the Fort St. Vrain core support block are presented. Materials investigations and operation of a molybdenum-core SiC heat pipe are reported. Entrainment limits for gravity-assisted heat pipes and heat pipe configurations for application to energy conservation are being investigated. The new solution critical assembly, SHEBA, was completed. Godiva IV was temporarily relocated at TA-15. Influence of scattered radiations in the test vault on InRad measurements was determined from detector scans of the vault produced by 252 Cf neutron and 137 Cs gamma sources

  18. Latest developments in prestressed concrete vessels for gas-cooled reactors

    International Nuclear Information System (INIS)

    Ople, F.S. Jr.

    1979-01-01

    This paper is an update of the design development of prestressed concrete vessels, commonly referred to as 'PCRVs' starting with the first single-cavity PCRV for the Fort St. Vrain Nuclear Generating Station to the latest multi-cavity PCRV configurations being utilized as the primary reactor vessels for both the High Temperature Gas-Cooled Reactor (HTGR) and the Gas-Cooled Fast Breeder Reactor (GCFR) in the U.S.A. The complexity of PCRV design varies not only due to the type of vessel configuration (single versus multi-cavity) but also on the application to the specific type of reactor concept. PCRV technology as applied to the Steam Cycle HTGR is fairly well established; however, some significant technical complexities are associated with PCRV design for the Gas Turbine HTGR and the GCFR. For the Gas Turbine HTGR, for instance, the fluid dynamics of the turbo-machinery cause multi-pressure conditions to exist in various portions of the power conversion loops during operation. This condition complicates the design approach and the proof test specification for the PCRV. The geometric configuration of the multi-cavity PCRV is also more complex due to the introduction of large horizontal cylindrical cavities (housing the turbo/machines for the Gas Turbine HTGR and circulators for the GCFR) in addition to the vertical cylindrical cavities for the core and heat exchangers. Because of this complex geometry, it becomes difficult to achieve an optimum prestressing arrangement for the PCRV. Other novel features of the multi-cavity PCRV resulting from the continuing design optimization effort are the incorporation of an asymmetric (offset core) configuration and the use of large vessel cavity/penetration concrete closures directly held down by prestressing tendons for both economic and safety reasons. (orig.)

  19. Edutainment, cultural innovation and social inclusion. Fort360, a project for cultural heritage enhancement

    Directory of Open Access Journals (Sweden)

    Paolo Di Pietro Martinelli

    2016-12-01

    Full Text Available   Fort360 project is a cultural initiative that receives the main directives of edutainment processes, trying to provide an answer to the necessity of a capillary system of information and awareness about the dismissing cultural heritage. The proposed study – carried out in the Fort Bravetta, Rome – presents a video where the educational aspect, related to the historical and architectural site contents, is strictly connected with the playful and emotional quality, resulted from a VR interaction with a panoramic video. This first case study focuses on the use of low-cost digital instrumentation and tries to improve the value of culture from the bottom, proposing an alternative way of cultural heritage enjoyment, based on participation and on interdisciplinarity of the proposed contents.

  20. 76 FR 71611 - Notice of Establishment of the Fort Winfield Scott Advisory Committee

    Science.gov (United States)

    2011-11-18

    ... (``Committee''). The Committee will advise the Executive Director of the Presidio Trust on matters pertaining... of once every three months. Nominations: The Presidio Trust will consider nominations of all... PRESIDIO TRUST Notice of Establishment of the Fort Winfield Scott Advisory Committee AGENCY: The...

  1. An ecological response model for the Cache la Poudre River through Fort Collins

    Science.gov (United States)

    Shanahan, Jennifer; Baker, Daniel; Bledsoe, Brian P.; Poff, LeRoy; Merritt, David M.; Bestgen, Kevin R.; Auble, Gregor T.; Kondratieff, Boris C.; Stokes, John; Lorie, Mark; Sanderson, John

    2014-01-01

    The Poudre River Ecological Response Model (ERM) is a collaborative effort initiated by the City of Fort Collins and a team of nine river scientists to provide the City with a tool to improve its understanding of the past, present, and likely future conditions of the Cache la Poudre River ecosystem. The overall ecosystem condition is described through the measurement of key ecological indicators such as shape and character of the stream channel and banks, streamside plant communities and floodplain wetlands, aquatic vegetation and insects, and fishes, both coolwater trout and warmwater native species. The 13- mile-long study area of the Poudre River flows through Fort Collins, Colorado, and is located in an ecological transition zone between the upstream, cold-water, steep-gradient system in the Front Range of the Southern Rocky Mountains and the downstream, warm-water, low-gradient reach in the Colorado high plains.

  2. A safety assessment of the use of graphite in nuclear reactors licensed by the US NRC

    International Nuclear Information System (INIS)

    Schweitzer, D.G.; Gurinsky, D.H.; Kaplan, E.; Sastre, C.

    1987-09-01

    This report reviews existing literature and knowledge on graphite burning and on stored energy accumulation and releases in order to assess what role, if any, a stored energy release can have in initiating or contributing to hypothetical graphite burning scenarios in research reactors. It also addresses the question of graphite ignition and self-sustained combustion in the event of a loss-of-coolant accident (LOCA). The conditions necessary to initiate and maintain graphite burning are summarized and discussed. From analyses of existing information it is concluded that only stored energy accumulations and releases below the burning temperature (650 0 C) are pertinent. After reviewing the existing knowledge on stored energy it is possible to show that stored energy releases do not occur spontaneously, and that the maximum stored energy that can be released from any reactor containing graphite is a very small fraction of the energy produced during the first few minutes of a burning incident. The conclusions from these analyses are that the potential to initiate or maintain a graphite burning incident is essentially independent of the stored energy in the graphite, and depends on other factors that are unique for these reactors, research reactors, and for Fort St. Vrain. In order to have self-sustained rapid graphite oxidation in any of these reactors, certain necessary conditions of geometry, temperature, oxygen supply, reaction product removal, and a favorable heat balance must be maintained. There is no new evidence associated with either the Windscale Accident or the Chernobyl Accident that indicates a credible potential for a graphite burning accident in any of the reactors considered in this review

  3. Establishment of ambient air quality trends using historical monitoring data from Edmonton and Fort McKay, Alberta

    International Nuclear Information System (INIS)

    Faisal, K.; Gamal El-Din, M.

    2006-01-01

    Ambient air trends were assessed using data collected over an 8 year period from monitoring stations in Edmonton and Fort McKay, Alberta. In particular, the study evaluated the short term trends in the concentration of carbon monoxide (CO), nitrogen dioxide (NO 2 ), ozone (O 3 ), and particulate matter (PM 2.5 ) in Edmonton, as well as the NO 2 , O 3 , PM 2.5 , and total hydrocarbons in Fort McKay. In order to evaluate the ambient air trends, this study examined the changes in concentrations of these pollutants between the 50 - 90 percentiles of concentration distributions for a calendar year. These statistics were assumed to be linear over the period of study and fitted using simple linear regression. Hypothesis tests were performed to determine if the slopes of the best-fit lines were greater or less than zero. There was no indication of a statistically significant short-term trend for NO 2 and O 3 for the city of Edmonton. However, statistically pronounced decreasing trends were noted for CO and PM 2.5 . There was no indication of statistically significant trend for any of the pollutants examined at Fort McKay over the study period. It was cautioned that since the period of study over which trends were examined was short, the changes or lack of changes observed do not necessarily indicate long term trends. However, the results suggest that air quality has remained unchanged during the last 6 to 8 years, despite increased economic development in Edmonton and continued oil sands development in Fort McKay

  4. Cultural keystone species in oil sands mine reclamation, Fort McKay, Alberta, Canada

    Energy Technology Data Exchange (ETDEWEB)

    Garibaldi, A.; Straker, J. [Stantec Ltd., Sidney, BC (Canada)

    2009-07-01

    Cultural keystone species (CKS) shape the cultural identify of people through the roles they have in diet, material and spiritual practices. The use of the CKS concept is regarded as a method of addressing linked social and ecological issues. This paper presented the results of using the CKS model in the indigenous community of Fort McKay, Alberta to address, social, ecological and spiritual values in regional mine-land reclamation. Fort McKay is at the epicenter of the existing mine developments. Its residents regard human and environmental health to be be linked and therefore experience the effects of development and subsequent reclamation on both cultural and ecological levels. The community is actively engaged in working with the local mining companies on issues of mine reclamation design. In order to hold meaning to the local people, oil sand operators used the CKS concept in their reclamation efforts to take into account ecological functionality and also address the linked social factors. Five CKS were identified through a literature review and extensive community interviews. The list includes moose, cranberry, blueberry, ratroot and beaver. These 5 CKS were used to focus discussions and make recommendations for relevant land reclamation within Fort McKay traditional territory. The project has influenced the way both the community and oil sands operators engage with reclamation. Lessons learned from this process will help direct reclamation activities on other portions of traditional territory, while offering guidance to other regional developers for addressing cultural values in reclamation on their leases. 15 refs., 1 fig.

  5. Drilling and Testing the DOI041A Coalbed Methane Well, Fort Yukon, Alaska

    Science.gov (United States)

    Clark, Arthur; Barker, Charles E.; Weeks, Edwin P.

    2009-01-01

    The need for affordable energy sources is acute in rural communities of Alaska where costly diesel fuel must be delivered by barge or plane for power generation. Additionally, the transport, transfer, and storage of fuel pose great difficulty in these regions. Although small-scale energy development in remote Arctic locations presents unique challenges, identifying and developing economic, local sources of energy remains a high priority for state and local government. Many areas in rural Alaska contain widespread coal resources that may contain significant amounts of coalbed methane (CBM) that, when extracted, could be used for power generation. However, in many of these areas, little is known concerning the properties that control CBM occurrence and production, including coal bed geometry, coalbed gas content and saturation, reservoir permeability and pressure, and water chemistry. Therefore, drilling and testing to collect these data are required to accurately assess the viability of CBM as a potential energy source in most locations. In 2004, the U.S. Geological Survey (USGS) and Bureau of Land Management (BLM), in cooperation with the U.S. Department of Energy (DOE), the Alaska Department of Geological and Geophysical Surveys (DGGS), the University of Alaska Fairbanks (UAF), the Doyon Native Corporation, and the village of Fort Yukon, organized and funded the drilling of a well at Fort Yukon, Alaska to test coal beds for CBM developmental potential. Fort Yukon is a town of about 600 people and is composed mostly of Gwich'in Athabascan Native Americans. It is located near the center of the Yukon Flats Basin, approximately 145 mi northeast of Fairbanks.

  6. 78 FR 60929 - Notice of Public Meeting of the Fort Scott Council

    Science.gov (United States)

    2013-10-02

    .... Such requests must be stated prominently at the beginning of the comments. The Trust will make... PRESIDIO TRUST Notice of Public Meeting of the Fort Scott Council AGENCY: The Presidio Trust... Scott Council (Council) will be held from 10 a.m. to 12:30 p.m. on Thursday, October 17, 2013. The...

  7. The Fort Logan Lodge: Intentional Community for Chronic Mental Patients. Final Report.

    Science.gov (United States)

    Fort Logan Mental Health Center, Denver, CO.

    This report attempts to identify important variables affecting the success of the Lodge Program, affiliated with the Fort Logan Mental Health Center. The Lodge Program is a community based, group oriented, social and work program for the rehabilitation of the refractory, long stay mental patient. Findings reported include the following: (1) the…

  8. Possible Location of Gaspar Dias Fort in Relation to the Present River Bank

    Digital Repository Service at National Institute of Oceanography (India)

    Mascarenhas, A.; Tripati, S.; ManiMurali, R.

    , it would be worthwhile to delineate the past river bank with respect to the present one, and to check whether any morphological changes occurred since then. Although the fort is marked by the river side in historical maps, the exact position of the shore...

  9. Design Schematics for a Sustainable Parking Lot: Building 2-2332, ENRD Classroom, Fort Bragg, NC

    National Research Council Canada - National Science Library

    Stumpf, Annette

    2003-01-01

    ...) was tasked with planning a sustainable design "charrette" to explore and develop alternative parking lot designs that would meet Fort Bragg's parking needs, as well as its need to meet sustainable...

  10. Efficacy and Safety Evaluation of Myostaal Forte, a Polyherbal Formulation, in Treatment of Knee Osteoarthritis: A Randomised Controlled Pilot Study

    Directory of Open Access Journals (Sweden)

    Raakhi K Tripathi

    2017-10-01

    Full Text Available Introduction: Myostaal Forte, a proprietary poly-herbal formulation, is mixture of nine herbal plant extracts which possess analgesic, anti-inflammatory and chondroprotective properties. Aim: A prospective, randomised, active controlled, 2-arm, parallel group, assessor blind study was planned to evaluate clinical efficacy and safety of Myostaal Forte in patients of knee osteoarthritis. Materials and Methods: Idiopathic knee osteoarthritis cases as per American College of Rheumatology (ACR clinical criteria were screened and recruited. A total of sixty patients were assigned to receive Myostaal Forte TDS (n=30 or Paracetamol 650 mg TDS (n=30 for six weeks. Naproxen was rescue analgesia. Modified Western Ontario and McMaster Universities Arthritis Index (WOMAC, Visual Analogue Scale (VAS, global assessment scores determined by orthopaedic physician at baseline, two, four, six weeks and telephonically at eight weeks. Safety was assessed through laboratory investigations at baseline and six weeks, adverse events and tolerability. Data were expressed as Mean±SD and analysed by Chi-square and unpaired t-test. p0.05. No significant adverse events, changes in the laboratory parameters and excellent compliance to treatment were seen in both the groups. Conclusion: Earlier onset analgesic effect with sustained chondroprotection after treatment cessation makes Myostaal Forte, a safe and effective alternative for treatment of knee osteoarthritis.

  11. Fort Stewart integrated resource assessment. Volume 3: Resource assessment

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, G.P.; Keller, J.M.; Stucky, D.J.; Wahlstrom, R.R.; Larson, L.L.

    1993-10-01

    The US Army Forces Command (FORSCOM) has tasked the US Department of Energy (DOE) Federal Energy Management Program (FEMP), supported by the Pacific Northwest Laboratory, to identify, evaluate, and assist in acquiring all cost-effective energy projects at Fort Stewart. This is part of a model program that PNL is designing to support energy-use decisions in the federal sector. This report provides the results of the fossil fuel and electric energy resource opportunity (ERO) assessments performed by PNL at the FORSCOM Fort Stewart facility located approximately 25 miles southwest of Savannah, Georgia. It is a companion report to Volume 1, Executive Summary, and Volume 2, Baseline Detail. The results of the analyses of EROs are presented in 11 common energy end-use categories (e.g., boilers and furnaces, service hot water, and building lighting). A narrative description of each ERO is provided, along with a table detailing information on the installed cost, energy and dollar savings; impacts on operations and maintenance (O&M); and, when applicable, a discussion of energy supply and demand, energy security, and environmental issues. A description of the evaluation methodologies and technical and cost assumptions is also provided for each ERO. Summary tables present the cost-effectiveness of energy end-use equipment before and after the implementation of each ERO. The tables also present the results of the life-cycle cost (LCC) analysis indicating the net present value (NPV) and savings to investment ratio (SIR) of each ERO.

  12. Notification: Hotline Complaint – Drinking Water Treatment Plant at the Fort Belknap Indian Community

    Science.gov (United States)

    Project #OA-FY13-0076, November 13, 2012. On March 22, 2012, the Office of Inspector General (OIG) received a hotline complaint on the construction of the Drinking Water Treatment Plant (DWTP) at the Fort Belknap Indian Community.

  13. Biomechanical testing of zirconium dioxide osteosynthesis system for Le Fort I advancement osteotomy fixation.

    Science.gov (United States)

    Hingsammer, Lukas; Grillenberger, Markus; Schagerl, Martin; Malek, Michael; Hunger, Stefan

    2018-01-01

    The following work is the first evaluating the applicability of 3D printed zirconium dioxide ceramic miniplates and screws to stabilize maxillary segments following a Le-Fort I advancement surgery. Conventionally used titanium and individual fabricated zirconium dioxide miniplates were biomechanically tested and compared under an occlusal load of 120N and 500N using 3D finite element analysis. The overall model consisted of 295,477 elements. Under an occlusal load of 500N a safety factor before plastic deformation respectively crack of 2.13 for zirconium dioxide and 4.51 for titanium miniplates has been calculated. From a biomechanical point of view 3D printed ZrO 2 mini-plates and screws are suggested to constitute an appropriate patient specific and metal-free solution for maxillary stabilization after Le Fort I osteotomy. Copyright © 2017 Elsevier Ltd. All rights reserved.

  14. A non-conventional procedure for the 3D modeling of WWI forts

    Directory of Open Access Journals (Sweden)

    E. Nocerino

    2014-06-01

    Full Text Available 2014 is the hundredth anniversary of the outbreak of the First World War (WWI – or Great War – in Europe and a number of initiatives have been planned to commemorate the tragic event. Until 1918, the Italian Trentino – Alto Adige region was under the Austro – Hungarian Empire and represented one of the most crucial and bloody war front between the Austrian and Italian territories. The region borders were constellated of military fortresses, theatre of battles between the two opposite troops. Unfortunately, most of these military buildings are now ruined and their architectures can be hardly appreciated. The paper presents the initial results of the VAST project (VAlorizzazione Storia e Territorio – Valorization of History and Landscape, that aims to digitally reconstruct the forts located on the plateaus of Luserna, Lavarone and Folgaria. An integrated methodology has been adopted to collect and employ all possible source of information in order to derive precise and photo-realistic 3D digital representations of WWI forts.

  15. A Study to Evaluate the Organization and the Operating Procedures of the Patient Assistance Function at Brooke Army Medical Center, Fort Sam Houston, Texas

    Science.gov (United States)

    1979-08-01

    15 March 1979. 59Interview with Wendy L. Farace , Head Nurse, Obstetrics/Gynecology Clinic, Brooke Army Medical Center, Fort Sam Houston, Texas, 8...6 February 1979. Farace , Wendy L. Head Nurse, Obstetrica/Gynecology Clinic, Brooke Army Medical Center, Fort Sam Houston, Texas. Interview, 8 January

  16. 75 FR 24930 - Fort Bliss (Texas) Army Growth and Force Structure Realignment Final Environmental Impact...

    Science.gov (United States)

    2010-05-06

    ...-PWE, Building 624, Taylor Road, Fort Bliss, TX 79916-6812; e- mail: [email protected] . FOR... Regional Branch Library, 551 Redd Road. In Las Cruces (NM), the New Mexico State University Zuhl Library...

  17. Fort St. Vrain high temperature gas-cooled reactor. Pt. 12. The dew point moisture monitor testing program

    Energy Technology Data Exchange (ETDEWEB)

    Olson, H.G. (Colorado State Univ., Fort Collins (USA). Dept. of Mechanical Engineering); Brey, H.L. (Public Service Co. of Colorado, Denver (USA)); Swart, F.E. (Gas-Cooled Reactor Associates, La Jolla, CA (USA)); Forbis, J.M. (Storage Technology Corp., Louisville, CO (USA))

    1982-09-01

    Moisture ingress into the core volume could cause damaging reactions with the moderator-reflector graphite and burnable poison, therefore a dew point moisture monitoring system has been developed with the basic design criteria that a plant protective system trip is signaled after the system detects high primary coolant helium moisture levels and that the system is able to correctly identify which of two steam generator loops is leaking. Modifications to the sample supplies to the monitors were necessary to reduce the system's unsatisfactory response time at lower reactor power levels.

  18. 77 FR 21448 - Security Zone; 2012 Fleet Week, Port Everglades, Fort Lauderdale, FL

    Science.gov (United States)

    2012-04-10

    ... Environmental Health Risks and Safety Risks. This rule is not an economically significant rule and does not create an environmental risk to health or risk to safety that may disproportionately affect children...-AA87 Security Zone; 2012 Fleet Week, Port Everglades, Fort Lauderdale, FL AGENCY: Coast Guard, DHS...

  19. Military vehicle trafficking impacts vegetation and soil bulk density at Fort Benning, Georgia

    Science.gov (United States)

    Potential increases in wind erosion that might be brought about by military vehicles travelling off-road during training are of concern to the United States military. Field studies were conducted in the summer of 2012 at Fort Benning, Georgia. The objective of the experiment was to assess the traffi...

  20. Warm Dry Weather Conditions Cause of 2016 Fort McMurray Wild Forest Fire and Associated Air Quality

    Science.gov (United States)

    de Azevedo, S. C.; Singh, R. P.; da Silva, E. A., Sr.

    2016-12-01

    The climate change is evident from the increasing temperature around the world, day to day life and increasing frequency of natural hazards. The warm and dry conditions are the cause of frequent forest fires around the globe. Forest fires severely affect the air quality and human health. Multi sensor satellites and dense network of ground stations provide information about vegetation health, meteorological, air quality and atmospheric parameters. We have carried out detailed analysis of satellite and ground data of wild forest fire that occurred in May 2016 in Fort McMurray, Alberta, Canada. This wild forest fire destroyed 10 per cent of Fort McMurray's housing and forced more than 90,000 people to evacuate the surrounding areas. Our results show that the warm and dry conditions with low rainfall were the cause of Fort McMurray wild fire. The air quality parameters (particulate matter, CO, ozone, NO2, methane) and greenhouse gases measured from Atmospheric Infrared Sounder (AIRS) satellite show enhanced levels soon after the forest fire. The emissions from the forest fire affected health of population living in surrounding areas up to 300 km radius.

  1. ORTURB, HTGR Steam Turbine Dynamic for FSV Reactor

    International Nuclear Information System (INIS)

    Conklin, J.C.

    2001-01-01

    1 - Description of program or function: ORTURB was written specifically to calculate the dynamic behavior of the Fort St. Vrain (FSV) High- Temperature Gas-Cooled Reactor (HTGR) steam turbines. The program is divided into three main parts: the driver subroutine; turbine subroutines to calculate the pressure-flow balance of the high-, intermediate-, and low-pressure turbines; and feedwater heater subroutines. 2 - Method of solution: The program uses a relationship derived for ideal gas flow in an iterative fashion that minimizes computational time to determine the pressure and flow in the FSV steam turbines as a function of plant transient operating conditions. An important computer modeling characteristic, unique to FSV, is that the high-pressure turbine exhaust steam is used to drive the reactor core coolant circulators prior to entering the reheater. A feedwater heater dynamic simulation model utilizing seven state variables for each of the five heaters is included in the ORTURB computer simulation of the regenerative Rankine cycle steam turbines. The seven temperature differential equations are solved at each time- step using a matrix exponential method. 3 - Restrictions on the complexity of the problem: The turbine shaft is assumed to rotate at a constant (rated) speed of 3600 rpm. Energy and mass storage of steam in the high-, intermediate-, and low-pressure turbines is assumed to be negligible. These limitations exclude the use of ORTURB during a turbine transient such as startup from zero power or very low turbine flows

  2. [Russian experience with Vitaprost Forte suppositories in patients with lower urinary tract symptoms and benign prostatic hyperplasia: comparative analysis of studies].

    Science.gov (United States)

    Korneev, I A

    2017-07-01

    The article reviews the domestic studies showing the efficacy and safety of suppositories containing prostate extract (Samprost substance) Vitaprost Forte in treating men with lower urinary tract symptoms secondary to benign prostatic hyperplasia. The data obtained by Russian specialists confirm the effectiveness of Vitaprost Forte suppositories in managing patients with moderate LUTS and infravesical obstruction caused by BPH to reduce dysuria, improve the quality of life and normalize urodynamic parameters.

  3. The hill forts and castle mounds in Lithuania: interaction between geodiversity and human-shaped landscape

    Science.gov (United States)

    Skridlaite, Grazina; Guobyte, Rimante; Satkunas, Jonas

    2015-04-01

    Lithuania is famous for its abundant, picturesque hill forts and castle mounds of natural origin. In Lithuania as well as in whole Europe the fortified hills were used as the society dwelling place since the beginning of the Late Bronze Age. Their importance increased when Livonian and Teutonic Orders directed a series of military campaigns against Lithuania with the aim of expansion of Christianity in the region at the end of 1st millennium AD, and they were intensively used till the beginning of the 15th c. when most of them were burned down during fights with the Orders or just abandoned due to the changing political and economical situation. What types of the geodiversity were used for fortified dwellings? The choice in a particular area depended on a variety of geomorphology left behind the retreating ice sheets. High spots dominating their surroundings were of prime interest. In E and SE Lithuania, the Baltic Upland hills marking the eastern margin of the last Weichselian glacier hosted numerous fortified settlements from the end of 2nd millennium BC to the Medieval Ages (Narkunai, Velikuskes etc). In W Lithuania, plateau-like hills of the insular Samogitian Upland had been repeatedly fortified from the beginning of 1st millennium AD to the 14th century (Satrija, Medvegalis etc). Chains of hill forts and castle mounds feature the slopes of glaciofluvial valleys of Nemunas, Neris and other rivers where the slopes were dissected by affluent rivulets and ravines and transformed into isolated, well protected hills (Kernave, Punia, Veliuona etc). Peninsulas and headlands formed by the erosion of fluvial and lacustrine deposits were used in the lowlands, e.g. in central and N Lithuania (Paberze, Mezotne etc). How much the landscape was modified for defense purposes? Long-term erosion and overgrowing vegetation damaged the former fortified sites, however some remains and the archeological excavations allowed their reconstruction. The fortified Bronze Age settlements

  4. Sustainable Materials Replacement for Prevention of Corrosion at Fort Lewis, WA

    Science.gov (United States)

    2009-08-01

    documents a building reclamation project at Fort Lewis, WA, in which significant portions of the work were completed using market -available sustainable...contractors to submit previous technology performance or test documentation, which is generally published as products are introduced to the market . If...evaluate the performance of the E2C2 in its final configuration. Energy use will be analyzed using a Building Infor- mation Model ( BIM ) to simulate

  5. 78 FR 33808 - Foreign-Trade Zone (FTZ) 39-Dallas-Fort Worth, Texas; Notification of Proposed Production...

    Science.gov (United States)

    2013-06-05

    ... Street, and 4600 Blue Mound Road, Fort Worth (Tarrant County), Texas. A separate application for ``usage... abroad include: plastic labels; parts of fans (housings, grills, pedestal assemblies, blades); electric...

  6. Ânion gap corrigido para albumina, fosfato e lactato é um bom preditor de íon gap forte em pacientes enfermos graves: estudo de coorte em nicho

    Directory of Open Access Journals (Sweden)

    Fernando Godinho Zampieri

    2013-09-01

    Full Text Available OBJETIVO: Ânion gap corrigido e íon gap forte são usados comumente para estimar os ânions não medidos. Avaliamos o desempenho do ânion gap corrigido para albumina, fosfato e lactato na predição do íon gap forte em uma população mista de pacientes enfermos graves. Formulamos a hipótese de que o ânion gap corrigido para albumina, fosfato e lactato seria um bom preditor do íon gap forte, independentemente da presença de acidose metabólica. Além disso, avaliamos o impacto do íon gap forte por ocasião da admissão na mortalidade hospitalar. MÉTODOS: Incluímos 84 pacientes gravemente enfermos. A correlação e a concordância entre o ânion gap corrigido para albumina, fosfato e lactato e o íon gap forte foi avaliada utilizando-se os testes de correlação de Pearson, regressão linear, plot de Bland-Altman e pelo cálculo do coeficiente de correlação interclasse. Foram realizadas duas análises de subgrupos: uma para pacientes com excesso de base -2mEq/L (grupo com alto excesso de base. Foi realizada uma regressão logística para avaliar a associação entre os níveis de íon gap forte na admissão e a mortalidade hospitalar. RESULTADOS: Houve correlação muito forte e uma boa concordância entre o ânion gap corrigido para albumina, fosfato e lactato e o íon gap forte na população geral (r2=0,94; bias 1,40; limites de concordância de -0,75 a 3,57. A correlação foi também elevada nos grupos com baixo excesso de base (r2=0,94 e alto excesso de base (r2=0,92. Estavam presentes níveis elevados de íon gap forte em 66% da população total e 42% dos casos do grupo alto excesso de. Íon gap forte não se associou com a mortalidade hospitalar, conforme avaliação pela regressão logística. CONCLUSÃO: O ânion gap corrigido para albumina, fosfato e lactato e o íon gap forte tiveram uma excelente correlação. Os ânions não medidos estão frequentemente elevados em pacientes gravemente enfermos com excesso de base

  7. Freight Advanced Traveler Information System (FRATIS) - Dallas-Fort Worth : as-built system architecture and design.

    Science.gov (United States)

    This document describes the As-Built System Architecture and Design for the FRATIS Dallas-Fort Worth : DFW prototype system. The FRATIS prototype in DFW consisted of the following components: : optimization algorithm, terminal wait time, route specif...

  8. Parametric study of the low-enriched uranium integrated Fort-Saint-Vrain element; comparative evaluation with the interacting tubular element

    International Nuclear Information System (INIS)

    Cerles, J.M.; Carvallo, G.; Vallepin, C.

    1971-11-01

    This paper presents a study of the influence of the different geometric and neutronic parameters on the calculation of the cycle with low-enriched uranium in a Fort-Saint-Vrain type brick. The study is divided in two parts: a stage of physics, essentially neutronics; an economical part where the costs are taken into account. At the level of studies of neutronics and costs, a parallel comparison is developed between the brick Fort-Saint-Vrain and the interacting tubular element, and even thorium. 6 refs. 29 figs [fr

  9. Master environmental plan for Fort Devens, Massachusetts

    Energy Technology Data Exchange (ETDEWEB)

    Biang, C.A.; Peters, R.W.; Pearl, R.H.; Tsai, S.Y. (Argonne National Lab., IL (United States). Energy Systems Div.)

    1991-11-01

    Argonne National Laboratory has prepared a master environmental plan (MEP) for Fort Devens, Massachusetts, for the US Army Toxic and Hazardous Materials Agency. The MEP is an assessment based on environmental laws and regulations of both the federal government and the Commonwealth of Massachusetts. The MEP assess the physical and environmental status of 58 potential hazardous waste sites, including 54 study areas (SAs) that pose a potential for releasing contamination into the environment and 4 areas of concern (AOCs) that are known to have substantial contamination. For each SA or AOC, this MEP describes the known history and environment, identifies additional data needs, and proposes possible response actions. Most recommended response actions consist of environmental sampling and monitoring and other characterization studies. 74 refs., 63 figs., 50 tabs.

  10. Fort Collins Science Center Ecosystem Dynamics Branch

    Science.gov (United States)

    Wilson, Jim; Melcher, C.; Bowen, Z.

    2009-01-01

    Complex natural resource issues require understanding a web of interactions among ecosystem components that are (1) interdisciplinary, encompassing physical, chemical, and biological processes; (2) spatially complex, involving movements of animals, water, and airborne materials across a range of landscapes and jurisdictions; and (3) temporally complex, occurring over days, weeks, or years, sometimes involving response lags to alteration or exhibiting large natural variation. Scientists in the Ecosystem Dynamics Branch of the U.S. Geological Survey, Fort Collins Science Center, investigate a diversity of these complex natural resource questions at the landscape and systems levels. This Fact Sheet describes the work of the Ecosystems Dynamics Branch, which is focused on energy and land use, climate change and long-term integrated assessments, herbivore-ecosystem interactions, fire and post-fire restoration, and environmental flows and river restoration.

  11. Energy Optimization Assessment at U.S. Army Installations: Fort Bliss, TX

    Science.gov (United States)

    2008-09-01

    Log dampers, temperatures, actuator signals, and other parameters to identify problems. Adjust chiller and boiler setpoints and control curves...installation. The lowest setpoints were found in the Centennial Club, with 52 °F during unoccupied hours (morn- ing). The chillers ran pretty much fully loaded...ER D C/ CE R L TR -0 8 -1 5 Energy Optimization Assessment at U.S. Army Installations Fort Bliss, TX David M. Underwood, Alexander M

  12. Data Mining the Corporate Dental System of USA DENTAC Fort Bragg

    Science.gov (United States)

    2016-06-10

    appointment data were queried for active duty Soldiers assigned to Fort Bragg, NC. All data were analyzed by using SPSS version 22.0 ( SPSS , Chicago, IL...Clinic. For each appointment the appointment type, date, and dental wellness classification were retained for analysis . For the purposes of this study...considered part of the Go First Class program. The analysis was split into multiple phases, beginning with a chi-square test for trend to

  13. Study of neutral composition of lower thermosphere at Fort Churchill.

    Science.gov (United States)

    Nier, A. O.; Hickman, D. R.

    1973-01-01

    On Feb. 4 and 6, 1969, and May 11, 1970, Aerobee rockets carrying neutral mass spectrometers were flown at Fort Churchill, Canada during conditions of low geomagnetic activity. As in earlier flights at White Sands, New Mexico, each rocket carried both 'open' and 'closed' ion source instruments. Vertical profiles of N2, O2, O, Ar, and He were measured. Results obtained were essentially the same as those observed at White Sands except that for the winter flights helium appeared to be in diffusive equilibrium.

  14. Vegetation inventory, mapping, and classification report, Fort Bowie National Historic Site

    Science.gov (United States)

    Studd, Sarah; Fallon, Elizabeth; Crumbacher, Laura; Drake, Sam; Villarreal, Miguel

    2013-01-01

    A vegetation mapping and characterization effort was conducted at Fort Bowie National Historic Site in 2008-10 by the Sonoran Desert Network office in collaboration with researchers from the Office of Arid lands studies, Remote Sensing Center at the University of Arizona. This vegetation mapping effort was completed under the National Park Service Vegetation Inventory program which aims to complete baseline mapping inventories at over 270 national park units. The vegetation map data was collected to provide park managers with a digital map product that met national standards of spatial and thematic accuracy, while also placing the vegetation into a regional and even national context. Work comprised of three major field phases 1) concurrent field-based classification data collection and mapping (map unit delineation), 2) development of vegetation community types at the National Vegetation Classification alliance or association level and 3) map accuracy assessment. Phase 1 was completed in late 2008 and early 2009. Community type descriptions were drafted to meet the then-current hierarchy (version 1) of the National Vegetation Classification System (NVCS) and these were applied to each of the mapped areas. This classification was developed from both plot level data and censused polygon data (map units) as this project was conducted as a concurrent mapping and classification effort. The third stage of accuracy assessment completed in the fall of 2010 consisted of a complete census of each map unit and was conducted almost entirely by park staff. Following accuracy assessment the map was amended where needed and final products were developed including this report, a digital map and full vegetation descriptions. Fort Bowie National Historic Site covers only 1000 acres yet has a relatively complex landscape, topography and geology. A total of 16 distinct communities were described and mapped at Fort Bowie NHS. These ranged from lush riparian woodlands lining the

  15. Procarti Forte in the Complex Treatment of Patients with Early-Stage Osteoarthritis

    Directory of Open Access Journals (Sweden)

    O.A. Burianov

    2016-04-01

    Full Text Available The article deals with the issue of the treatment of osteoarthritis. The review of current recommendations on the feasibility of using glucosamine sulfate, chondroitin sulfate, hyaluronic acid, using of SYSADOA drugs, metabolic drugs was performed. The study on the efficacy and safety of using combination drug Procarti Forte in the system of treatment of patients with early-stage osteoarthritis is presented.

  16. Historical Analysis of Land Cover/Condition Trends at Fort Bliss, Texas, Using Remotely Sensed Imagery

    National Research Council Canada - National Science Library

    Tweddale, Scott

    2001-01-01

    .... They need a cost-effective method of assessing and monitoring land condition. The objective of this research was to characterize the small scale, gross level change in land condition on a selected area of Fort Bliss over a 23-year period...

  17. 77 FR 51064 - Huntington Foam LLC, Fort Smith, AR; Notice of Affirmative Determination Regarding Application...

    Science.gov (United States)

    2012-08-23

    ... DEPARTMENT OF LABOR Employment and Training Administration [TA-W-81,475] Huntington Foam LLC, Fort Smith, AR; Notice of Affirmative Determination Regarding Application for Reconsideration By application dated May 21, 2012, the State Workforce Office requested administrative reconsideration of the negative...

  18. 75 FR 40034 - Northeastern Tributary Reservoirs Land Management Plan, Beaver Creek, Clear Creek, Boone, Fort...

    Science.gov (United States)

    2010-07-13

    ... TENNESSEE VALLEY AUTHORITY Northeastern Tributary Reservoirs Land Management Plan, Beaver Creek...-managed public land on Beaver Creek, Clear Creek, Boone, Fort Patrick Henry, South Holston, Watauga, and... Proposed Land Use Alternative) identified in the final environmental impact statement (FEIS). Under the...

  19. Revisiting "Narrow Bipolar Event" intracloud lightning using the FORTE satellite

    Science.gov (United States)

    Jacobson, A. R.; Light, T. E. L.

    2012-02-01

    The lightning stroke called a "Narrow Bipolar Event", or NBE, is an intracloud discharge responsible for significant charge redistribution. The NBE occurs within 10-20 μs, and some associated process emits irregular bursts of intense radio noise, fading at shorter timescales, sporadically during the charge transfer. In previous reports, the NBE has been inferred to be quite different from other forms of lightning strokes, in two ways: First, the NBE has been inferred to be relatively dark (non-luminous) compared to other lightning strokes. Second, the NBE has been inferred to be isolated within the storm, usually not participating in flashes, but when it is in a flash, the NBE has been inferred to be the flash initiator. These two inferences have sufficiently stark implications for NBE physics that they should be subjected to further independent test, with improved statistics. We attempt such a test with both optical and radio data from the FORTE satellite, and with lightning-stroke data from the Los Alamos Sferic Array. We show rigorously that by the metric of triggering the PDD optical photometer aboard the FORTE satellite, NBE discharges are indeed less luminous than ordinary lightning. Referred to an effective isotropic emitter at the cloud top, NBE light output is inferred to be less than ~3 × 108 W. To address isolation of NBEs, we first expand the pool of geolocated intracloud radio recordings, by borrowing geolocations from either the same flash's or the same storm's other recordings. In this manner we generate a pool of ~2 × 105 unique and independent FORTE intracloud radio recordings, whose slant range from the satellite can be inferred. We then use this slant range to calculate the Effective Radiated Power (ERP) at the radio source, in the passband 26-49 MHz. Stratifying the radio recordings by ERP into eight bins, from a lowest bin (140 kW), we document a trend for the radio recordings to become more isolated in time as the ERP increases. The highest

  20. Information management needs for Fort Calhoun's design basis reconstitution project

    International Nuclear Information System (INIS)

    Beach, D.R.; Erickson, E.A.; Gambhir, S.K.; Parsons, R.D.

    1989-01-01

    While the need for information management is not new to the nuclear industry or Omaha Public Power District (OPPD), the interrelationship among design information, multiple systems, and design basis issues has necessitated the management of this information in new ways. The project team involved in the reconstitution of the design basis for OPPD's Fort Calhoun nuclear station has experienced the need for the developed effective methods for managing the vast amount of interrelated information associated with this effort. This management of information has been necessary to ensure that design basis documents (DBDs) adequately reflect the interrelated nature of component, system, and plant design; are complete and accurate; and are produced and maintained in a cost-effective manner. Fort Calhoun's aggressive design basis reconstitution project began in early 1987. The present scope of the project includes the production of 52 system and plant level DBDs; currently the project is ∼50% complete with DBDs in various stages of completion, from pilot DBDs through DBDs with approved formats, which have been issued for use. The experience in producing these documents has lead to a growing understanding of the special need for information management in each stage of the project. The development of the information tracking and management processes for the various stages of DBD development has proven to be cost-effective and gives a level of assurance that information has been included in the DBDs consistently and accurately

  1. Wooden combs from the Roman fort at Vechten: the bodily appearance of soldiers

    NARCIS (Netherlands)

    Derks, A.M.J.; Vos, W.K.

    2010-01-01

    Abstract Excavations in the late 19th century and surveys carried out in the 1970s have produced 12 boxwood combs from the Roman fort at Vechten (NL). They are to be considered waste material that was dumped in the river Rhine which in the Roman period ran just north of the camp. In this article,

  2. Helium circulator design concepts for the modular high temperature gas-cooled reactor (MHTGR) plant

    International Nuclear Information System (INIS)

    McDonald, C.F.; Nichols, M.K.; Kaufman, J.S.

    1988-01-01

    Two helium circulators are featured in the Modular High-Temperature Gas-Cooled Reactor (MHTGR) power plant - (1) the main circulator, which facilitates the transfer of reactor thermal energy to the steam generator, and (2) a small shutdown cooling circulator that enables rapid cooling of the reactor system to be realized. The 3170 kW(e) main circulator has an axial flow compressor, the impeller being very similar to the unit in the Fort St. Vrain (FSV) plant. The 164 kW(e) shutdown cooling circulator, the design of which is controlled by depressurized conditions, has a radial flow compressor. Both machines are vertically oriented, have submerged electric motor drives, and embody rotors that are supported on active magnetic bearings. As outlined in this paper, both machines have been conservatively designed based on established practice. The circulators have features and characteristics that have evolved from actual plant operating experience. With a major goal of high reliability, emphasis has been placed on design simplicity, and both machines are readily accessible for inspection, repair, and replacement, if necessary. In this paper, conceptual design aspects of both machines are discussed, together with the significant technology bases. As appropriate for a plant that will see service well into the 21st century, new and emerging technologies have been factored into the design. Examples of this are the inclusion of active magnetic bearings, and an automated circulator condition monitoring system. (author). 18 refs, 20 figs, 13 tabs

  3. Dust Plume Modeling from Ranges and Maneuver Areas on Fort Bliss and the White Sands Missile Range: Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Chapman, Elaine G.; Barnard, James C.; Rutz, Frederick C.; Pekour, Mikhail S.; Rishel, Jeremy P.; Shaw, William J.

    2009-05-04

    The potential for air quality impacts from heavy mechanized vehicles operating on and between the unpaved main supply routes at Fort Bliss and White Sands Missile Range was investigated. This report details efforts by the staff of Pacific Northwest National Laboratory for the Fort Bliss Directorate of Environment in this investigation. Dust emission and dispersion from typical move-out activities occurring on the installations were simulated using the atmospheric modeling system DUSTRAN. Major assumptions associated with designing the modeling scenarios are summarized and results of simulations conducted under these assumptions are presented for four representative meteorological periods.

  4. Assessment of soil-gas, seep, and soil contamination at the North Range Road Landfill, Fort Gordon, Georgia, 2008-2009

    Science.gov (United States)

    Landmeyer, James E.; Falls, W. Fred; Ratliff, W. Hagan; Wellborn, John B.

    2011-01-01

    Soil gas, seeps, and soil were assessed for contaminants at the North Range Road Landfill at Fort Gordon, Georgia, from October 2008 to September 2009. The assessment included delineating organic contaminants present in soil-gas samples beneath the area estimated to be the landfill and in water samples collected from three seeps at the base of the landfill. Inorganic contaminants were determined in three seep samples and in soil samples. This assessment was conducted to provide environmental contamination data to Fort Gordon pursuant to requirements for the Resource Conservation and Recovery Act Part B Hazardous Waste Permit process.

  5. Biological Assessment of Streams Associated with the Northern Training Complex at Fort knox, Kentucky, August 2000

    National Research Council Canada - National Science Library

    Payne, Berry

    2001-01-01

    .... The benthic macroinvertebrate aspect of the U.S. Environmental Protection Agency's Rapid Bioassessment Protocol was applied in August 2000 to selected streams likely to be affected by proposed improvements of training facilities on Fort Knox...

  6. Reflector dowel strength test, Fort St. Vrain

    International Nuclear Information System (INIS)

    Doll, D.W.

    1975-01-01

    The strength of the 44.45 mm (1.75 in.) diameter Fort St. Vrain (FSV) reflector dowel for loads directed radially inward toward the center of the element was measured. For a statically applied load, the strength exceeded 5783 N (1300 lb) in direct shear. This strength remained after load cycling 100 times to 4448 N (1000 lb), 10 times to 4893 N (1100 lb), 10 times to 5338 N (1200 lb), and two times to 5783 N (1300 lb). Typically, the deflection to ultimate failure was approximately 1.0 mm (0.04 in.). At about 3316 N (750 lb) and 0.20 mm (0.008 in.) deflection, one of the webs between the dowel and a coolant hole cracked, apparently redistributing the load. No further failure occurred up to the ultimate load of 5783+ N (1300+ lb)

  7. End-use energy characterization and conservation potentials at DoD Facilities: An analysis of electricity use at Fort Hood, Texas

    Energy Technology Data Exchange (ETDEWEB)

    Akbari, H.; Konopacki, S.

    1995-05-01

    This report discusses the application of the LBL`s End-use Disaggregation Algorithm (EDA) to a DoD installation and presents hourly reconciled end-use data for all major building types and end uses. The project initially focused on achieving these objectives and pilot-testing the methodology at Fort Hood, Texas. Fort Hood, with over 5000 buildings was determined to have representative samples of nearly all of the major building types in use on DoD installations. These building types at Fort Hood include: office, administration, vehicle maintenance, shop, hospital, grocery store, retail store, car wash, church, restaurant, single-family detached housing, two and four-plex housings, and apartment building. Up to 11 end uses were developed for each prototype, consisting of 9 electric and 2 gas; however, only electric end uses were reconciled against known data and weather conditions. The electric end uses are space cooling, ventilation, cooking, miscellaneous/plugs, refrigeration, exterior lighting, interior lighting, process loads, and street lighting. The gas end uses are space heating and hot water heating. Space heating energy-use intensities were simulated only. The EDA was applied to 10 separate feeders from the three substations at Fort Hood. The results from the analyses of these ten feeders were extrapolated to estimate energy use by end use for the entire installation. The results show that administration, residential, and the bar-rack buildings are the largest consumers of electricity for a total of 250GWh per year (74% of annual consumption). By end use, cooling, ventilation, miscellaneous, and indoor lighting consume almost 84% of total electricity use. The contribution to the peak power demand is highest by residential sector (35%, 24 MW), followed by administration buildings (30%), and barrack (14%). For the entire Fort Hood installation, cooling is 54% of the peak demand (38 MW), followed by interior lighting at 18%, and miscellaneous end uses by 12%.

  8. 75 FR 36371 - Draft Environmental Impact Statement Addressing Campus Development at Fort Meade, MD

    Science.gov (United States)

    2010-06-25

    ...'s (NSA) continually evolving requirements and for Intelligence Community use. The purpose of the..., or e-mail [email protected]nsa.gov . SUPPLEMENTARY INFORMATION: Background: The NSA is a tenant DOD agency on Fort Meade. NSA is a high-technology organization that is on the frontier of communications and data...

  9. Craniofacial stability in patients with Crouzon or Apert syndrome after Le Fort III distraction osteogenesis

    NARCIS (Netherlands)

    Reitsma, J.H.; Ongkosuwito, E.M.; Buschang, P.H.; van Adrichem, L.N.A.; Prahl-Andersen, B.

    2013-01-01

    Objective: Le Fort III osteotomy with distraction osteogenesis (DO) is used to improve the retruded midface in patients with Crouzon or Apert syndrome. This study aimed to evaluate sagittal and vertical preoperative and postoperative cephalometric changes of DO of the midface in patients with

  10. Craniofacial stability in patients with crouzon or apert syndrome after le fort III distraction osteogenesis

    NARCIS (Netherlands)

    J.H. Reitsma (Jacobus Harmen); E.M. Ongkosuwito (Edwin); P.H. Buschang (Peter); L.N.A. V Adrichem (Léon); B. Prahl-Andersen (Birte)

    2013-01-01

    textabstractObjective: Le Fort III osteotomy with distraction osteogenesis (DO) is used to improve the retruded midface in patients with Crouzon or Apert syndrome. This study aimed to evaluate sagittal and vertical preoperative and postoperative cephalometric changes of DO of the midface in patients

  11. 78 FR 53494 - Dam Safety Modifications at Cherokee, Fort Loudoun, Tellico, and Watts Bar Dams

    Science.gov (United States)

    2013-08-29

    ... Bar Dams AGENCY: Tennessee Valley Authority. ACTION: Issuance of Record of Decision. SUMMARY: This... the dam safety modifications at Cherokee, Fort Loudoun, Tellico, and Watts Bar Dams. The notice of... Loudoun, Tellico, and Watts Bar Dams was published in the Federal Register on May 31, 2013. This...

  12. Preliminary assessment of streamflow characteristics for selected streams at Fort Gordon, Georgia, 1999-2000

    Science.gov (United States)

    Stamey, Timothy C.

    2001-01-01

    In 1999, the U.S. Geological Survey, in cooperation with the U.S. Army Signal Center and Fort Gordon, began collection of periodic streamflow data at four streams on the military base to assess and estimate streamflow characteristics of those streams for potential water-supply sources. Simple and reliable methods of determining streamflow characteristics of selected streams on the military base are needed for the initial implementation of the Fort Gordon Integrated Natural Resources Management Plan. Long-term streamflow data from the Butler Creek streamflow gaging station were used along with several concurrent discharge measurements made at three selected partial-record streamflow stations on Fort Gordon to determine selected low-flow streamflow characteristics. Streamflow data were collected and analyzed using standard U.S. Geological Survey methods and computer application programs to verify the use of simple drainage area to discharge ratios, which were used to estimate the low-flow characteristics for the selected streams. Low-flow data computed based on daily mean streamflow include: mean discharges for consecutive 1-, 3-, 7-, 14-, and 30-day period and low-flow estimates of 7Q10, 30Q2, 60Q2, and 90Q2 recurrence intervals. Flow-duration data also were determined for the 10-, 30-, 50-, 70-, and 90-percent exceedence flows. Preliminary analyses of the streamflow indicate that the flow duration and selected low-flow statistics for the selected streams averages from about 0.15 to 2.27 cubic feet per square mile. The long-term gaged streamflow data indicate that the streamflow conditions for the period analyzed were in the 50- to 90-percent flow range, or in which streamflow would be exceeded about 50 to 90 percent of the time.

  13. Assessment of loblolly pine decline and site conditions on Fort Benning Military Reservation, GA

    Science.gov (United States)

    Roger D. Menard; Lori G. Eckhardt; Nolan J. Hess

    2010-01-01

    A decline of loblolly pine (Pinus taeda L.), characterized by expanding areas of declining and dead trees, has become prevalent at Fort Benning, GA. A 3-year study was conducted to determine the kinds of fungi, insects, and site disturbances associated with this problem. The insects Dendroctonus terebrans, Hylastes salebrosus, H. tenuis, Pachylobius picivorus...

  14. American Recovery and Reinvestment Act (ARRA) Federal Energy Management Program Technical Assistance Project 282 Renewable Energy Opportunities at Fort Gordon, Georgia

    Energy Technology Data Exchange (ETDEWEB)

    Boyd, Brian K.; Gorrissen, Willy J.; Hand, James R.; Horner, Jacob A.; Orrell, Alice C.; Russo, Bryan J.; Weimar, Mark R.; Williamson, Jennifer L.; Nesse, Ronald J.

    2010-09-30

    This document provides an overview of renewable resource potential at Fort Gordon, based primarily upon analysis of secondary data sources supplemented with limited on-site evaluations. This effort focuses on grid-connected generation of electricity from renewable energy sources and also on ground source heat pumps for heating and cooling buildings. The effort was funded by the American Recovery and Reinvestment Act (ARRA) as follow-on to the 2005 Department of Defense (DoD) Renewables Assessment. The site visit to Fort Gordon took place on March 9, 2010.

  15. Exploration Drilling and Technology Demonstration At Fort Bliss

    Energy Technology Data Exchange (ETDEWEB)

    Barker, Ben; Moore, Joe [EGI; Segall, Marylin; Nash, Greg; Simmons, Stuart; Jones, Clay; Lear, Jon; Bennett, Carlon

    2014-02-26

    The Tularosa-Hueco basin in south-central New Mexico has long been known as an extensional area of high heat flow. Much of the basin is within the Fort Bliss military reservation, which is an exceptionally high value customer for power independent of the regional electric grid and for direct use energy in building climate control. A series of slim holes drilled in the 1990s established the existence of a thermal anomaly but not its practical value. This study began in 2009 with a demonstration of new exploration drilling technology. The subsequent phases reported here delivered a useful well, comparative exploration data sets and encouragement for further development. A production-size well, RMI56-5, was sited after extensive study of archival and newly collected data in 2010-2011. Most of 2012 was taken up with getting state and Federal authorities to agree on a lead agency for permitting purposes, getting a drilling permit and redesigning the drilling program to suit available equipment. In 2013 we drilled, logged and tested a 924 m well on the McGregor Range at Fort Bliss using a reverse circulation rig. Rig tests demonstrated commercial permeability and the well has a 7-inch slotted liner for use either in production or injection. An August 2013 survey of the completed well showed a temperature of 90 C with no reversal, the highest such temperature in the vicinity. The well’s proximity to demand suggests a potentially valuable resource for direct use heat and emergency power generation. The drilling produced cuttings of excellent size and quality. These were subjected to traditional analyses (thin sections, XRD) and to the QEMScan™ for comparison. QEMScan™ technology includes algorithms for determining such properties of rocks as density, mineralogy, heavy/light atoms, and porosity to be compared with direct measurements of the cuttings. In addition to a complete cuttings set, conventional and resistivity image logs were obtained in the open hole before

  16. Conceptual design report for the mechanical disassembly of Fort St. Vrain fuel elements

    International Nuclear Information System (INIS)

    Lord, D.L.; Wadsworth, D.C.; Sekot, J.P.; Skinner, K.L.

    1993-04-01

    A conceptual design study was prepared that: (1) reviewed the operations necessary to perform the mechanical disassembly of Fort St. Vrain fuel elements; (2) contained a description and survey of equipment capable of performing the necessary functions; and (3) performed a tradeoff study for determining the preferred concepts and equipment specifications. A preferred system was recommended and engineering specifications for this system were developed

  17. Conceptual design report for the mechanical disassembly of Fort St. Vrain fuel elements

    Energy Technology Data Exchange (ETDEWEB)

    Lord, D.L. [Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States); Wadsworth, D.C.; Sekot, J.P.; Skinner, K.L. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

    1993-04-01

    A conceptual design study was prepared that: (1) reviewed the operations necessary to perform the mechanical disassembly of Fort St. Vrain fuel elements; (2) contained a description and survey of equipment capable of performing the necessary functions; and (3) performed a tradeoff study for determining the preferred concepts and equipment specifications. A preferred system was recommended and engineering specifications for this system were developed.

  18. 78 FR 4356 - Proposed Modification of the Dallas/Fort Worth Class B Airspace Area; TX

    Science.gov (United States)

    2013-01-22

    ... Dallas/Fort Worth International Airport (DFW) and Dallas Love Field Airport (DAL) within Class B airspace... acknowledge receipt of their comments on this action must submit with those comments a self-addressed, stamped... configuration has not kept pace with airport expansions and increasing operations and the current design makes...

  19. 75 FR 17691 - Foreign-Trade Zone 196 - Fort Worth, Texas, Application for Temporary/Interim Manufacturing...

    Science.gov (United States)

    2010-04-07

    ... (Cell Phone Kitting and Distribution), Fort Worth, Texas An application has been submitted to the... cell phones (HTSUS 8517.12, duty free) under T/IM procedures at its facility (152 employees, 186,000... 96% of the value of the finished product) include: cell phone batteries; cell phone chargers and...

  20. Evaluation of Eurasian Watermilfoil Control Techniques Using Aquatic Herbicides in Fort Peck Lake, Montana

    Science.gov (United States)

    2015-07-01

    Dredge Cut #2) are located immediately below Fort Peck Dam (Figure 4). The Dredge Cuts were formed by the excavation of soil for construction of the... Enviro -USA) consisted of 50, 6 m × 4.1 m deep sections. When sections were connected, a total length of 305 m was achieved. The top of the curtain was

  1. Agriculture and Rural Development on Fort Hood Lands, 1849-1942: National Register Assessments of 710 Historic Archeological Properties

    National Research Council Canada - National Science Library

    Freeman, Martha

    2001-01-01

    In 1999, historians consulting with Prewitt & Associates, Inc., conducted archival research for the purpose of developing historic contexts relevant to the Fort Hood lands taken during the 1940s acquisition...

  2. Reactor theory and power reactors. 1. Calculational methods for reactors. 2. Reactor kinetics

    International Nuclear Information System (INIS)

    Henry, A.F.

    1980-01-01

    Various methods for calculation of neutron flux in power reactors are discussed. Some mathematical models used to describe transients in nuclear reactors and techniques for the reactor kinetics' relevant equations solution are also presented

  3. Geologic map of the Fort Morgan 7.5' quadrangle, Morgan County, Colorado

    Science.gov (United States)

    Berry, Margaret E.; Taylor, Emily M.; Slate, Janet L.; Paces, James B.; Hanson, Paul R.; Brandt, Theodore R.

    2018-06-08

    The Fort Morgan 7.5′ quadrangle is located on the semiarid plains of northeastern Colorado, along the South Platte River corridor where the river has incised into Upper Cretaceous Pierre Shale. The Pierre Shale is largely covered by surficial deposits that formed from alluvial, eolian, and hillslope processes operating in concert with environmental changes from the late Pliocene to the present. The South Platte River, originating high in the Colorado Rocky Mountains, has played a major role in shaping surficial geology in the map area, which is several tens of kilometers downstream from where headwater tributaries join the river. Recurrent glaciation (and deglaciation) of basin headwaters has affected river discharge and sediment supply far downstream, influencing deposition of alluvium and river incision in the Fort Morgan quadrangle. Distribution and characteristics of the alluvial deposits indicate that during the Pleistocene the course of the river within the map area shifted progressively southward as it incised, and by late middle Pleistocene the river was south of its present position, cutting and filling a deep paleochannel near the south edge of the quadrangle. The river shifted back to the north during the late Pleistocene. Kiowa and Bijou Creeks are unglaciated tributaries originating in the Colorado Piedmont east of the Front Range that also have played a major role in shaping surficial geology of the map area. Periodically during the late Pleistocene, major flood events on these tributaries deposited large volumes of sediment at and near their confluences, forming a broad, low-gradient fan composed of sidestream alluvium that could have occasionally dammed the river for short periods of time. Wildcat Creek, also originating on the Colorado Piedmont, and the small drainage of Cris Lee Draw dissect the map area north of the river. Eolian sand deposits of the Sterling (north of river) and Fort Morgan (south of river) dune fields cover much of the

  4. Reactor core in FBR type reactor

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Kawashima, Katsuyuki; Kurihara, Kunitoshi.

    1989-01-01

    In a reactor core in FBR type reactors, a portion of homogenous fuels constituting the homogenous reactor core is replaced with multi-region fuels in which the enrichment degree of fissile materials is lower nearer to the axial center. This enables to condition the composition such that a reactor core having neutron flux distribution either of a homogenous reactor core or a heterogenous reactor core has substantially identical reactivity. Accordingly, in the transfer from the homogenous reactor core to the axially heterogenous reactor core, the average reactivity in the reactor core is substantially equal in each of the cycles. Further, by replacing a portion of the homogenous fuels with a multi-region fuels, thereby increasing the heat generation near the axial center, it is possiable to reduce the linear power output in the regions above and below thereof and, in addition, to improve the thermal margin in the reactor core. (T.M.)

  5. Miniplate fixation of Le Fort I osteotomies.

    Science.gov (United States)

    Rosen, H M

    1986-12-01

    The use of rigid, internal, three-dimensional fixation using vitallium bone plates in 28 consecutive Le Fort I osteotomies is presented. A minimum follow-up period of 6 months was required for inclusion in this patient group. Maxillary movements included advancements (17), intrusions (9), lengthenings (5), and retrusions (2). The majority of maxillae were moved in more than one plane of space. Technical details, complications, and relapse potential are discussed. Advantages of rigid plate fixation include marked reductions in the length of intermaxillary fixation with light training elastics only. Immediate postoperative airway problems are thereby eliminated. Six months of follow-up would appear to indicate a low potential for osseous relapse when compared to wire osteosynthesis, regardless of the direction of maxillary movement. The major disadvantage is the decreased ability of postoperative orthodontics to move dento-osseous segments if skeletal occlusal disharmony persists postoperatively. For this reason, close attention to preoperative planning and operative technique is critical for the success of this fixation method.

  6. Tooth-borne distraction osteogenesis versus conventional Le Fort I in maxillary advancement of cleft lip and palate patients.

    Science.gov (United States)

    Jamilian, Abdolreza; Showkatbakhsh, Rahman; Behnaz, Mohammad; Ghassemi, Alireza; Kamalee, Zinat; Perillo, Letizia

    2018-01-31

    Distraction osteogenesis (DO) is rapidly becoming a mainstream surgical technique for correction of maxillary deficiency. The aim of this study was to compare the effectiveness of a newly designed tooth-borne osteogenic distraction device with conventional LeFort 1 osteotomy in maxillary advancement of cleft lip and palate patients. The DO group consisted of 10 subjects (7 males, 3 females) with a mean age of 21.2 (SD 4.2) years. In these patients, the newly designed distraction device which exerted force anteroposteriorly was cemented after mobilization of the maxilla. After a latency period of 7 days, the distractor was activated twice daily by a total amount of 0.5 mm per day. The activation was continued for 3 weeks. After an 8-week consolidation period, the distraction appliance was removed. Cephalograms of DO patients were obtained at the start of distraction and at the end of consolidation. The LeFort 1 group consisted of 11 subjects (6 males, 5 females) with a mean age of 22.3 (SD 3.7) years. Pre and post-surgery lateral cephalograms were obtained. T-Test and paired T-test were used to evaluate the data. At the end of treatment, the SNA angle of LeFort 1 patients increased by 5.5° (SD 2.3) (Pdistraction device can effectively advance the maxilla forward in patients with cleft lip.

  7. Final terms of reference for the Environmental Impact Assessment (EIA) report for the proposed Suncor Energy Inc., Project Millennium, Fort McMurray, Alberta

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-04

    This document identifies the information that Suncor will need to prepare and submit as an Environmental Impact Assessment (EIA) report as part of its application to the Alberta Energy and Utilities Board for the construction, operation and reclamation of its proposed Millenium extension of the Steepbank Mine. The report must identify development activities, describe environmental effects, mitigation options and residual effects that are relevant to the assessment of the project. The report must also include a description of the processing facilities, mining activities, utilities and transportation. Similarly, the report must provide a full description of the environmental management systems in place, as well as details of the proposed management of air emissions, water, waste, hydrocarbons, and chemicals. The report will be made public to allow for participation from those who may be affected by the project. This includes residents and organizations in the Fort McMurray, Fort McKay, and Fort Chipewyan areas.

  8. Detailed workplan for innovative technology demonstrations to support existing treatment operations at the Installation Logistics Center, DSERTS Site FTLE-33, Fort Lewis, Washington

    Energy Technology Data Exchange (ETDEWEB)

    Liikala, T.L.

    1998-07-01

    This workplan is an assemblage of documents for use by Pacific Northwest National Laboratory (PNNL) to direct and control project activities at Fort Lewis, Washington. Fort Lewis is a FORSCOM installation, whose Logistics Center (DSERTS Site FTLE-33) was placed on the National priorities List (NPL) in December 1989, as a result of trichloroethene (TCE) contamination in groundwater beneath the site. Site background information and brief descriptions of the Fort Lewis project and the main supporting documents, which will be used to direct and control the project activities, are provided. These are followed by a summary of the Work Breakdown Structure (WBS) elements, a general project schedule, a list of major deliverables, and a budget synopsis. Test plans for specific elements (Bench-Scale Testing) will be developed separately as those elements are initiated. If additional activities not specifically addressed in the Project Management Plan (Attachment 1) are added to the work scope, addendums to this workplan will be prepared to cover those activities.

  9. The Leavenworth Lamp: Symbol of the Command and General Staff College, Fort Leavenworth, Kansas, Presented 7 May 1956

    National Research Council Canada - National Science Library

    1956-01-01

    On the occasion of the 75th Anniversary of the founding of the Command and General Staff College, Fort Leavenworth, Kansas, on 7 May 1956, the "Leavenworth Lamp" was officially adopted by the College...

  10. Reactor core and initially loaded reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Koyama, Jun-ichi; Aoyama, Motoo.

    1989-01-01

    In BWR type reactors, improvement for the reactor shutdown margin is an important characteristic condition togehter with power distribution flattening . However, in the reactor core at high burnup degree, the reactor shutdown margin is different depending on the radial position of the reactor core. That is , the reactor shutdown margin is smaller in the outer peripheral region than in the central region of the reactor core. In view of the above, the reactor core is divided radially into a central region and as outer region. The amount of fissionable material of first fuel assemblies newly loaded in the outer region is made less than the amount of the fissionable material of second fuel assemblies newly loaded in the central region, to thereby improve the reactor shutdown margin in the outer region. Further, the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower portion of the first fuel assemblies is made smaller than the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower region of the second fuel assemblies, to thereby obtain a sufficient thermal margin in the central region. (K.M.)

  11. Adapting the deep burn in-core fuel management strategy for the gas turbine - modular helium reactor to a uranium-thorium fuel

    International Nuclear Information System (INIS)

    Talamo, Alberto; Gudowski, Waclaw

    2005-01-01

    In 1966, Philadelphia Electric has put into operation the Peach Bottom I nuclear reactor, it was the first high temperature gas reactor (HTGR); the pioneering of the helium-cooled and graphite-moderated power reactors continued with the Fort St. Vrain and THTR reactors, which operated until 1989. The experience on HTGRs lead General Atomics to design the gas turbine - modular helium reactor (GT-MHR), which adapts the previous HTGRs to the generation IV of nuclear reactors. One of the major benefits of the GT-MHR is the ability to work on the most different types of fuels: light water reactors waste, military plutonium, MOX and thorium. In this work, we focused on the last type of fuel and we propose a mixture of 40% thorium and 60% uranium. In a uranium-thorium fuel, three fissile isotopes mainly sustain the criticality of the reactor: 235 U, which represents the 20% of the fresh uranium, 233 U, which is produced by the transmutation of fertile 232 Th, and 239 Pu, which is produced by the transmutation of fertile 238 U. In order to compensate the depletion of 235 U with the breeding of 233 U and 239 Pu, the quantity of fertile nuclides must be much larger than that one of 235 U because of the small capture cross-section of the fertile nuclides, in the thermal neutron energy range, compared to that one of 235 U. At the same time, the amount of 235 U must be large enough to set the criticality condition of the reactor. The simultaneous satisfaction of the two above constrains induces the necessity to load the reactor with a huge mass of fuel; that is accomplished by equipping the fuel pins with the JAERI TRISO particles. We start the operation of the reactor with loading fresh fuel into all the three rings of the GT-MHR and after 810 days we initiate a refueling and shuffling schedule that, in 9 irradiation periods, approaches the equilibrium of the fuel composition. The analysis of the k eff and mass evolution, reaction rates, neutron flux and spectrum at the

  12. Archeological Testing at Fort St. Leon (16PL35), Plaquemines Parish, Louisiana.

    Science.gov (United States)

    1983-05-01

    Bend which is nebulous at best. 3. Test excavations downriver from the American fort (BHT 12, 13, 14, 15) (Figure 24b) encountered disturbed strata...unidentifiable 3 Unit 1, 2.07-1.82 m Plastron fragments (pond slider turtle ) 3 Unit 1, 2.02-1.82 m Plastron and carapace fragments (pond slider turtle ) 2 Unit...trench walls less than 1 m below the surface. The same is true for the pond slider turtle bones from Units 1 and 2. 160 . . . .. . . . . . . o Nutria

  13. Generalized surficial geologic map of the Fort Irwin area, San Bernadino: Chapter B in Geology and geophysics applied to groundwater hydrology at Fort Irwin, California

    Science.gov (United States)

    Miller, David M.; Menges, Christopher M.; Lidke, David J.; Buesch, David C.

    2014-01-01

    The geology and landscape of the Fort Irwin area, typical of many parts of the Mojave Desert, consist of rugged mountains separated by broad alluviated valleys that form the main coarse-resolution features of the geologic map. Crystalline and sedimentary rocks, Mesozoic and older in age, form most of the mountains with lesser accumulations of Miocene sedimentary and volcanic rocks. In detail, the area exhibits a fairly complex distribution of surficial deposits resulting from diverse rock sources and geomorphology that has been driven by topographic changes caused by recent and active faulting. Depositional environments span those typical of the Mojave Desert: alluvial fans on broad piedmonts, major intermittent streams along valley floors, eolian sand dunes and sheets, and playas in closed valleys that lack through-going washes. Erosional environments include rocky mountains, smooth gently sloping pediments, and badlands in readily eroded sediment. All parts of the landscape, from regional distribution of mountains, valleys, and faults to details of degree of soil development in surface materials, are portrayed by the surficial geologic map. Many of these attributes govern infiltration and recharge, and the surface distribution of permeable rock units such as Miocene sedimentary and volcanic rocks provides a basis for evaluating potential groundwater storage. Quaternary faults are widespread in the Fort Irwin area and include sinistral, east-striking faults that characterize the central swath of the area and the contrasting dextral, northwest-striking faults that border the east and west margins. Bedrock distribution and thickness of valley-fill deposits are controlled by modern and past faulting, and faults on the map help to identify targets for groundwater exploration.

  14. Precipitation and streamflow data from the Fort Carson Military Reservation and precipitation, streamflow, and suspended-sediment data from the Piñon Canyon Maneuver Site, Southeastern Colorado, 2008-2012

    Science.gov (United States)

    Brown, Christopher R.

    2014-01-01

    In 2013, the U.S. Geological Survey (USGS), in cooperation with the U. S. Department of the Army, compiled available precipitation and streamflow data for the years of 2008–2012 from the Fort Carson Military Reservation (Fort Carson) near Colorado Springs, Colo., and precipitation, streamflow, and suspended-sediment loads from the Piñon Canyon Maneuver Site (PCMS) near Trinidad, Colo. Graphical representations of the data presented herein are a continuation of work completed by the USGS in 2008 to gain a better understanding of spatial and temporal trends within the hydrologic data. Precipitation stations at Fort Carson and the PCMS were divided into groups based on their land-surface altitude (LSA) to determine if there is a spatial difference in precipitation amounts based on LSA for either military facility. Two-sample t-tests and Wilcoxon rank-sum tests indicated statistically significant differences exist between precipitation values at different groups for Fort Carson but not for the PCMS. All five precipitation stations at Fort Carson exhibit a decrease in median daily total precipitation from years 2002–2007 to 2008–2012. For the PCMS, median precipitation values decreased from the first study period to the second for the 13 stations monitored year-round except for Burson and Big Hills. Mean streamflow for 2008–2012 is less than mean streamflow for 1983–2007 for all stream-gaging stations at Fort Carson and at the PCMS. During the study period, each of the stream-gaging stations within the tributary channels at the PCMS accounted for less than three percent of the total streamflow at the Purgatoire River at Rock Crossing gage. Peak streamflow for 2008–2012 is less than peak streamflow for 2002–2007 at both Fort Carson and the PCMS. At the PCMS, mean suspended-sediment yield for 2008–2012 increased by 54 percent in comparison to the mean yield for 2002–2007. This increase is likely related to the destruction of groundcover by a series of

  15. Seasonal shifts in the diet of the big brown bat (Eptesicus fuscus), Fort Collins, Colorado

    Science.gov (United States)

    Valdez, Ernest W.; O'Shea, Thomas J.

    2014-01-01

    Recent analyses suggest that the big brown bat (Eptesicus fuscus) may be less of a beetle specialist (Coleoptera) in the western United States than previously thought, and that its diet might also vary with temperature. We tested the hypothesis that big brown bats might opportunistically prey on moths by analyzing insect fragments in guano pellets from 30 individual bats (27 females and 3 males) captured while foraging in Fort Collins, Colorado, during May, late July–early August, and late September 2002. We found that bats sampled 17–20 May (n = 12 bats) had a high (81–83%) percentage of volume of lepidopterans in guano, with the remainder (17–19% volume) dipterans and no coleopterans. From 28 May–9 August (n = 17 bats) coleopterans dominated (74–98% volume). On 20 September (n = 1 bat) lepidopterans were 99% of volume in guano. Migratory miller moths (Euxoa auxiliaris) were unusually abundant in Fort Collins in spring and autumn of 2002 and are known agricultural pests as larvae (army cutworms), suggesting that seasonal dietary flexibility in big brown bats has economic benefits.

  16. Notes on Chameleons IV. A New Chameleon, from the Miocene of Fort Ternan, Kenya (Chamaeleonidae, Reptilia)

    NARCIS (Netherlands)

    Hillenius, D.

    1978-01-01

    A new, fossil chameleon is described, † Chamaeleo intermedius, found on the surface at Fort Ternan, Kenya. Most probably it eroded from a layer of fossilized lahar, close to 14 million years old. † Chamaeleo intermedius possesses characters which still occur in recent chameleons, in fact it combines

  17. Ansel Adams's Eucalyptus Tree, Fort Ross: Nature, Photography, and the Search for California

    OpenAIRE

    Adam Arenson

    2005-01-01

    This article considers the image of California evoked in the unusual Ansel Adams photograph Eucalyptus Tree, Fort Ross, California (1969), a Polaroid Land image of the garrison fence and an aged eucalyptus tree. Considering the participation of Russian occupation, Australian cross-pollination, Carleton Watkins's early photographs of redwoods, automotive and tourist images in the creation of this distinctive California place, the article argues that to understand Ansel Adams's work, we must no...

  18. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    Baeten, P.

    2006-01-01

    The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

  19. Reactor core of FBR type reactor

    International Nuclear Information System (INIS)

    Hayashi, Hideyuki; Ichimiya, Masakazu.

    1994-01-01

    A reactor core is a homogeneous reactor core divided into two regions of an inner reactor core region at the center and an outer reactor core region surrounding the outside of the inner reactor core region. In this case, the inner reactor core region has a lower plutonium enrichment degree and less amount of neutron leakage in the radial direction, and the outer reactor core region has higher plutonium enrichment degree and greater amount of neutron leakage in the radial direction. Moderator materials containing hydrogen are added only to the inner reactor core fuels in the inner reactor core region. Pins loaded with the fuels with addition of the moderator materials are inserted at a ratio of from 3 to 10% of the total number of the fuel pins. The moderator materials containing hydrogen comprise zirconium hydride, titanium hydride, or calcium hydride. With such a constitution, fluctuation of the power distribution in the radial direction along with burning is suppressed. In addition, an absolute value of the Doppler coefficient can be increased, and a temperature coefficient of coolants can be reduced. (I.N.)

  20. The Fort McMurray Demonstration Project in Social Marketing: no demonstrable effect on already falling injury rates following intensive community and workplace intervention.

    Science.gov (United States)

    Guidotti, Tee L; Deb, Pooja; Bertera, Robert; Ford, Lynda

    2009-10-01

    The Fort McMurray Demonstration Project in Social Marketing attempted to achieve mutually reinforcing effects from thematically coordinated educational and awareness efforts in the community as a whole and in the workplace and the inclusion of occupational safety within the framework of a community health promotion project. The study community was Fort McMurray, a small, industrial city in northern Alberta. The Mistahiai Health Region, several hundred kilometers to the west and also dominated by one city, Grande Prairie, served as the reference community. The intervention was based on media and events staged at public events, with supporting educational activities in schools and the community. It relied heavily on community-based partners and volunteers. Data on healthcare utilization of selected preventable injuries were obtained from Alberta Health for the time period 1990-1996 for the Regional Health Authorities of Northern Lights, where the only large population centre is Fort McMurray, and Mistahia. Age-adjusted aggregate injury rates were analyzed for evidence of an effect of the intervention. Severity was measured by proxy, using the number of diagnostic claims submitted for reimbursement for medical services in a given year. The communities differed in age-specific injury rates, with Fort McMurray showing higher rates for residents aged less than 55. Young adults and older adolescents showed higher levels of severity. Injury rates fell substantially and at similar rates in both communities over the five-year period. However, in both communities injury rates were already falling before the intervention in Fort McMurray began and continued to fall at about the same rate, slowing toward the end of the period. No evidence was found for an effect of the Project or for acceleration of the reduction in injury frequency in the intervention area. Over the period, fewer medical services were delivered in office settings and more in emergency rooms, in both

  1. Grønland som del af den bibelske fortælling - en 1700-tals studie

    DEFF Research Database (Denmark)

    Kjærgaard, Kathrine

    2010-01-01

     For missionærerne i Grønland som for de fleste andre i 1700-tallet var Bibelen en historisk sand fortælling om verden, der omfattede hele verdenshistorien fra Skabelsen til de sidste tider. Bibelen var ikke bare en sand historie om fortiden, den var også en sand historie om nutiden og om fremtid...

  2. Revisiting Pearson's climate and forest type studies on the Fort Valley Experimental Forest (P-53)

    Science.gov (United States)

    Joseph E. Crouse; Margaret M. Moore; Peter Z. Fule

    2008-01-01

    Five weather station sites were established in 1916 by Fort Valley personnel along an elevational gradient from the Experimental Station to near the top of the San Francisco Peaks to investigate the factors that controlled and limited forest types. The stations were located in the ponderosa pine, Douglas-fir, limber pine, Engelmann spruce, and Engelmann spruce/...

  3. Identification of Insect-Plant Pollination Networks for a Midwest Installation: Fort McCoy, WI

    Science.gov (United States)

    2016-04-01

    species are dependent on animal pollinators, including many agricultural plants (Ollerton et al. 2011). The recent declines of polli- nator species...pollinator fauna be- cause these species were absent from the Fort McCoy Integrated Natural Resources Management Plan. For general application of these...Conservation Status Ranks were used to classify species according to their vulnerability to extinction . Only species with Global Ranks of G1 (critically

  4. Nuclear reactors

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2015-10-01

    After some remarks on the nuclear fuel, on the chain reaction control, on fuel loading and unloading, this article proposes descriptions of the design, principles and operations of different types of nuclear reactors as well as comments on their presence and use in different countries: pressurized water reactors (design of the primary and secondary circuits, volume and chemistry control, backup injection circuits), boiling water reactors, heavy water reactors, graphite and boiling water reactors, graphite-gas reactors, fast breeder reactors, and fourth generation reactors (definition, fast breeding). For these last ones, six concepts are presented: sodium-cooled fast reactor, lead-cooled fast reactor, gas-cooled fast reactor, high temperature gas-cooled reactor, supercritical water-cooled reactor, and molten salt reactor

  5. The gas-cooled high temperature reactor. Perspectives, problems and programmes

    International Nuclear Information System (INIS)

    Beckurts, K.H.; Engelmann, P.; Erb, D.E.

    1977-01-01

    For nearly 20 years extensive research and development programmes on helium-cooled high temperature reactors (HTR) have been carried out in several countries of the world. As a result of the long-standing efforts, satisfactory solutions have been found for many of the basic problems of this new reactor system, particularly in the field of high temperature fuels and materials technology. Three small experimental plants have been operated successfully over extended periods of time. Prototype steam-cycle plants of 300MW(e) are under way at Fort St. Vrain (full-power operation scheduled for 1977) and at Schmehausen (scheduled for 1979). Major delays have occurred in the construction and commissioning of these plants for various reasons but do not reveal specific problems of the HTR. Commercial market introduction of the steam-cycle electricity generating system has been attempted, but the first approach has not been successful. Major efforts both by governments and industry are now required to ensure a successful second approach. To reach competitivity with established nuclear power systems and to take full advantage of the fuel conservation potential of the HTR requires the implementation of the closed thorium fuel cycle on a commercial scale. While some key steps of this cycle have been implemented on a laboratory scale, progress towards a prototype recycling facility has been slow. Closing the thorium fuel cycle represents a major challenge and can only be achieved in a close international collaboration. The paper discusses the world-wide status and potential of HTR technology and reviews the major international development programmes. (author)

  6. 75 FR 52733 - Record of Decision (ROD) for Fort Bliss Army Growth and Force Structure Realignment

    Science.gov (United States)

    2010-08-27

    ... decrease in certain quality of life indicators (e.g., traffic, air quality). The ROD, FEIS and other environmental documents are available on the Fort Bliss Web site ( http://www.bliss.army.mil ) or at the... (Stationing Action Alternative 4); land use changes that allow fixed site bivouac areas, mission support...

  7. 78 FR 27364 - Reorganization of Foreign-Trade Zone 241 Under Alternative Site Framework Fort Lauderdale, Florida

    Science.gov (United States)

    2013-05-10

    ... Zone 241 Under Alternative Site Framework Fort Lauderdale, Florida Pursuant to its authority under the...-48-2012, docketed 6/27/2012) for authority to reorganize under the ASF with a service area comprised... Everglades Customs and Border Protection port of entry, to modify Site 1 by removing acreage, to expand Sites...

  8. Reactor core for LMFBR type reactors

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Azekura, Kazuo; Kurihara, Kunitoshi; Bando, Masaru; Watari, Yoshio.

    1987-01-01

    Purpose: To reduce the power distribution fluctuations and obtain flat and stable power distribution throughout the operation period in an LMFBR type reactor. Constitution: In the inner reactor core region and the outer reactor core region surrounding the same, the thickness of the inner region is made smaller than the axial height of the reactor core region and the radial width thereof is made smaller than that of the reactor core region and the volume thereof is made to 30 - 50 % for the reactor core region. Further, the amount of the fuel material per unit volume in the inner region is made to 70 - 90 % of that in the outer region. The difference in the neutron infinite multiplication factor between the inner region and the outer region is substantially constant irrespective of the burnup degree and the power distribution fluctuation can be reduced to about 2/3, by which the effect of thermal striping to the reactor core upper mechanisms can be moderated. Further, the maximum linear power during operation can be reduced by 3 %, by which the thermal margin in the reactor core is increased and the reactor core fuels can be saved by 3 %. (Kamimura, M.)

  9. 75 FR 39460 - Prevailing Rate Systems; Redefinition of the Chicago, IL; Fort Wayne-Marion, IN; Indianapolis, IN...

    Science.gov (United States)

    2010-07-09

    ...-AM21 Prevailing Rate Systems; Redefinition of the Chicago, IL; Fort Wayne-Marion, IN; Indianapolis, IN... wage area. These changes are based on recent consensus recommendations of the Federal Prevailing Rate... below. The Federal Prevailing Rate Advisory Committee (FPRAC), the national labor-management committee...

  10. Demonstration of Thermally Sprayed Metal and Polymer Coatings for Steel Structures at Fort Bragg, NC

    Science.gov (United States)

    2017-09-01

    ER D C/ CE RL T R- 17 -3 0 DoD Corrosion Prevention and Control Program Demonstration of Thermally Sprayed Metal and Polymer Coatings...and Polymer Coatings for Steel Structures at Fort Bragg, NC Final Report on Project F07-AR10 Larry D. Stephenson, Alfred D. Beitelman, Richard G...5 2.1.2 Thermoplastic polymer coating (flame spray

  11. Nuclear reactor construction with bottom supported reactor vessel

    International Nuclear Information System (INIS)

    Sharbaugh, J.E.

    1987-01-01

    This patent describes an improved liquid metal nuclear reactor construction comprising: (a) a nuclear reactor core having a bottom platform support structure; (b) a reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core; (c) a containment structure surrounding the reactor vessel and having a sidewall spaced outwardly from the reactor vessel side wall and having a base mat spaced below the reactor vessel bottom end wall; (d) a central small diameter post anchored to the containment structure base mat and extending upwardly to the reactor vessel to axially fix the bottom end wall of the reactor vessel and provide a center column support for the lower end of the reactor core; (e) annular support structure disposed in the reactor vessel on the bottom end wall and extending about the lower end of the core; (f) structural support means disposed between the containment structure base mat and bottom end of the reactor vessel wall and cooperating for supporting the reactor vessel at its bottom end wall on the containment structure base mat to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event; (g) a bed of insulating material disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall; freely expand radially from the central post as it heats up while providing continuous support thereof; (h) a deck supported upon the wall of the containment vessel above the top open end of the reactor vessel; and (i) extendible and retractable coupling means extending between the deck and the top open end of the reactor vessel and flexibly and sealably interconnecting the reactor vessel at its top end to the deck

  12. Territoriality of feral pigs in a highly persecuted population on Fort Benning, Georgia

    Science.gov (United States)

    Sparklin, B.D.; Mitchell, M.S.; Hanson, L.B.; Jolley, D.B.; Ditchkoff, S.S.

    2009-01-01

    We examined home range behavior of female feral pigs (Sus scrofa) in a heavily hunted population on Fort Benning Military Reservation in west-central Georgia, USA. We used Global Positioning System location data from 24 individuals representing 18 sounders (i.e., F social groups) combined with markrecapture and camera-trap data to evaluate evidence of territorial behavior at the individual and sounder levels. Through a manipulative experiment, we examined evidence for an inverse relationship between population density and home range size that would be expected for territorial animals. Pigs from the same sounder had extensive home range overlap and did not have exclusive core areas. Sounders had nearly exclusive home ranges and had completely exclusive core areas, suggesting that female feral pigs on Fort Benning were territorial at the sounder level but not at the individual level. Lethal removal maintained stable densities of pigs in our treatment area, whereas density increased in our control area; territory size in the 2 areas was weakly and inversely related to density of pigs. Territorial behavior in feral pigs could influence population density by limiting access to reproductive space. Removal strategies that 1) match distribution of removal efforts to distribution of territories, 2) remove entire sounders instead of individuals, and 3) focus efforts where high-quality food resources strongly influence territorial behaviors may be best for long-term control of feral pigs.

  13. Le fort I osteotomy approach for advanced nasopharyngeal angiofibroma with intracranial extension: Report of a case

    Directory of Open Access Journals (Sweden)

    "Naraghi M

    2002-08-01

    Full Text Available Angiofibromas are the most common benign tumors of the nasopharynx, Intracranial extension has been reported in approximately 20-25% of cases. Intracranial extension may be difficult to treat because of poor exposure that may lead to recurrence. A 16-year-old male patient presented with a 6-month history of nasal obstruction, intermittent epistaxis, right superior orbital fissure syndrome, and proptosis. Imaging studies revealed a large right sinonasal mass with significant intracranial and infratemporal extensions. The tumor was resected by Le fort I technique because of dissatisfaction with other approaches. Postoperative period was uneventful and follow-up visits showed marked improvement in proptosis and ophthalmologic symptoms, without the evidence of tumor recurrence. Commonly used to treat facial deformities. The Le Fort I osteotomy with down fracturing of the entire palate has been adopted as a surgical option in the management of some angiofibromas. Compared with other popular techniques, it provides excellent exposure for angiofibromas. The merits and limitations of this approach as well as its details are discussed.

  14. Fort Cochin in Kerala 1750-1830 : the social condition of a Dutch community in an Indian milieu

    NARCIS (Netherlands)

    Singh, Anjana

    2007-01-01

    Focussing on individuals and institutions, the economic and social condition of the people of Fort Cochin between 1781 and 1830 has been studied. This study of the Dutch East India Company's (VOC) establishment on the south west coast of India provides a detailed research into the functioning of the

  15. Arsenic Fate, Transport And Stability Study: Groundwater, Surface Water, Soil And Sediment Investigation At Fort Devens Superfund Site

    Science.gov (United States)

    A field investigation was conducted to examine the distribution of arsenic in groundwater, surface water, and sediments at the Fort Devens Superfund Site. The study area encompassed a portion of plow Shop Pond (Red Cove), which receives groundwater discharge from the aquifer und...

  16. A brief geological history of Cockspur Island at Fort Pulaski National Monument, Chatham County, Georgia

    Science.gov (United States)

    Swezey, Christopher S.; Seefelt, Ellen L.; Parker, Mercer

    2018-03-09

    Fort Pulaski National Monument is located on Cockspur Island in Chatham County, Georgia, within the Atlantic Coastal Plain province. The island lies near the mouth of the Savannah River, and consists of small mounds (hummocks), salt marshes, and sediment dredged from the river. A 1,017-foot (ft) (310-meter [m])-deep core drilled at Cockspur Island in 2010 by the U.S. Geological Survey revealed several sedimentary units ranging in age from 43 million years old to present. Sand and mud are present at drilling depths from 0 to 182 ft (56 m), limestone is present at depths from 182 ft (56 m) to 965 ft (295 m), and glauconitic sand is present at depths from 965 ft (295 m) to 1,017 ft (310 m). The limestone and the water within the limestone are referred to collectively as the Floridan aquifer system, which is the primary source of drinking water for the City of Savannah and surrounding communities. In addition to details of the subsurface geology, this fact sheet identifies the following geologic materials used in the construction of Fort Pulaski: (1) granite, (2) bricks, (3) sandstone, and (4) lime mud with oyster shells.

  17. Preliminary assessment report for National Guard Training Center, Georgia Army National Guard, Fort Stewart, Georgia

    International Nuclear Information System (INIS)

    1993-07-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Georgia Army National Guard (GAARNG) facility near Hinesville, Georgia, known as the National Guard Training Center (NGTC). Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a priority basis for completing corrective actions (where necessary) in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining previous site activities, types and quantities of hazardous substances utilized, and potential pathways by which contamination could affect public health and the environment. The scope of this assessment is limited to the facilities and past activities contained within the NGTC. Preliminary assessment site score sheet information is also provided for the NGTC. However, this assessment report is intended to be read in conjunction with a previous IRP assessment of Fort Stewart completed in 1992 (USATHAMA 1992) and to provide comprehensive information on the NGTC area for incorporation with information contained in that previous assessment for the entirety of Fort Stewart

  18. Summary and abstracts from Sudden Aspen Decline (SAD) Meeting; Fort Collins, Colorado, February 12-13, 2008

    Science.gov (United States)

    Paul C. Rogers

    2008-01-01

    In recent years the aspen research and management community has witnessed increasing accounts of unexplained aspen die-offs across the Rocky Mountain region. In response, two meetings were held to address the issue; this paper summarizes the most recent gathering, a symposium held in Fort Collins at the USDA Forest Service, Rocky Mountain Research Station, on February...

  19. Brugerdrevne standarder og pædagogisk ledelse: Skræddersyede teknikker eller prototypiske fortællinger

    DEFF Research Database (Denmark)

    Nissen, Morten

    2016-01-01

    brugerdrevne. Derfra udvides billedet til mere og mere omfattende og udfordrende udgaver, og de principielle spørgsmål og perspektiver, som de rejser, bl.a. om prototypiske fortællinger og anerkendelse. Så får jeg samtidig fortalt om nogle af de pædagogiske praksisser og fællesskaber, som jeg har studeret. Til...

  20. Fort St. Vrain fuel-handling system RAM analysis

    International Nuclear Information System (INIS)

    Azizi, S.M.; Berg, G.E.; Burton, J.H.; Durand, R.E.; Larson, E.M.; Pepe, D.J.; Rutherford, P.D.; Novachek, F.J.

    1989-01-01

    Public Service of Company of Colorado (PSC) is planning to decommission its Fort St. Vrain plant in 1990. This requires removal of 1,500 separate assemblies from the core. With the low historical availability of the fuel-handling system (FHS), defueling time was estimated at 36 months. With plant expenses of approximately $1.6 million per month during defueling, this would mean a schedule cost of $58 million. With their contractor, Rockwell International, PSC embarked on a reliability, availability, and maintainability (RAM) analysis to reduce projected defueling time. Key elements included (a) estimating availability of the FHS using a limited historical record, (b) assessing the defueling critical path, and (c) proposing and evaluating design/operational improvements. The most cost-effective improvements are being implemented and are expected to provide a reduction of >18 months in schedule and a net savings of $20 to 25 million. The paper describes the FHS design and operation, major problems associated with fuel-handling operations, and results and recommendations

  1. Generation IV reactors: reactor concepts

    International Nuclear Information System (INIS)

    Cardonnier, J.L.; Dumaz, P.; Antoni, O.; Arnoux, P.; Bergeron, A.; Renault, C.; Rimpault, G.; Delpech, M.; Garnier, J.C.; Anzieu, P.; Francois, G.; Lecomte, M.

    2003-01-01

    Liquid metal reactor concept looks promising because of its hard neutron spectrum. Sodium reactors benefit a large feedback experience in Japan and in France. Lead reactors have serious assets concerning safety but they require a great effort in technological research to overcome the corrosion issue and they lack a leader country to develop this innovative technology. In molten salt reactor concept, salt is both the nuclear fuel and the coolant fluid. The high exit temperature of the primary salt (700 Celsius degrees) allows a high energy efficiency (44%). Furthermore molten salts have interesting specificities concerning the transmutation of actinides: they are almost insensitive to irradiation damage, some salts can dissolve large quantities of actinides and they are compatible with most reprocessing processes based on pyro-chemistry. Supercritical water reactor concept is based on operating temperature and pressure conditions that infers water to be beyond its critical point. In this range water gets some useful characteristics: - boiling crisis is no more possible because liquid and vapour phase can not coexist, - a high heat transfer coefficient due to the low thermal conductivity of supercritical water, and - a high global energy efficiency due to the high temperature of water. Gas-cooled fast reactors combining hard neutron spectrum and closed fuel cycle open the way to a high valorization of natural uranium while minimizing ultimate radioactive wastes and proliferation risks. Very high temperature gas-cooled reactor concept is developed in the prospect of producing hydrogen from no-fossil fuels in large scale. This use implies a reactor producing helium over 1000 Celsius degrees. (A.C.)

  2. Adapting the deep burn in-core fuel management strategy for the gas turbine - modular helium reactor to a uranium-thorium fuel

    Energy Technology Data Exchange (ETDEWEB)

    Talamo, Alberto [Department of Nuclear and Reactor Physics, Royal Institute of Technology, Roslagstullsbacken 21, S-10691, Stockholm (Sweden)]. E-mail: alby@neutron.kth.se; Gudowski, Waclaw [Department of Nuclear and Reactor Physics, Royal Institute of Technology, Roslagstullsbacken 21, S-10691, Stockholm (Sweden)

    2005-11-15

    In 1966, Philadelphia Electric has put into operation the Peach Bottom I nuclear reactor, it was the first high temperature gas reactor (HTGR); the pioneering of the helium-cooled and graphite-moderated power reactors continued with the Fort St. Vrain and THTR reactors, which operated until 1989. The experience on HTGRs lead General Atomics to design the gas turbine - modular helium reactor (GT-MHR), which adapts the previous HTGRs to the generation IV of nuclear reactors. One of the major benefits of the GT-MHR is the ability to work on the most different types of fuels: light water reactors waste, military plutonium, MOX and thorium. In this work, we focused on the last type of fuel and we propose a mixture of 40% thorium and 60% uranium. In a uranium-thorium fuel, three fissile isotopes mainly sustain the criticality of the reactor: {sup 235}U, which represents the 20% of the fresh uranium, {sup 233}U, which is produced by the transmutation of fertile {sup 232}Th, and {sup 239}Pu, which is produced by the transmutation of fertile {sup 238}U. In order to compensate the depletion of {sup 235}U with the breeding of {sup 233}U and {sup 239}Pu, the quantity of fertile nuclides must be much larger than that one of {sup 235}U because of the small capture cross-section of the fertile nuclides, in the thermal neutron energy range, compared to that one of {sup 235}U. At the same time, the amount of {sup 235}U must be large enough to set the criticality condition of the reactor. The simultaneous satisfaction of the two above constrains induces the necessity to load the reactor with a huge mass of fuel; that is accomplished by equipping the fuel pins with the JAERI TRISO particles. We start the operation of the reactor with loading fresh fuel into all the three rings of the GT-MHR and after 810 days we initiate a refueling and shuffling schedule that, in 9 irradiation periods, approaches the equilibrium of the fuel composition. The analysis of the k {sub eff} and mass

  3. Analysis of natural gas supply strategies at Fort Drum

    International Nuclear Information System (INIS)

    Stucky, D.J.; Shankle, S.A.; Anderson, D.M.

    1992-07-01

    This analysis investigates strategies for Fort Drum to acquire a reliable natural gas supply while reducing its gas supply costs. The purpose of this study is to recommend an optimal supply mix based on the life-cycle costs of each strategy analyzed. In particular, this study is intended to provide initial guidance as to whether or not the building and operating of a propane-air mixing station is a feasible alternative to the current gas acquisition strategy. The analysis proceeded by defining the components of supply (gas purchase, gas transport, supplemental fuel supply); identifying alternative options for each supply component; constructing gas supply strategies from different combinations of the options available for each supply component and calculating the life-cycle costs of each supply strategy under a set of different scenarios reflecting the uncertainty of future events

  4. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sato, Morihiko.

    1994-01-01

    Liquid metals such as liquid metal sodium are filled in a reactor container as primary coolants. A plurality of reactor core containers are disposed in a row in the circumferential direction along with the inner circumferential wall of the reactor container. One or a plurality of intermediate coolers are disposed at the inside of an annular row of the reactor core containers. A reactor core constituted with fuel rods and control rods (module reactor core) is contained at the inside of each of the reactor core containers. Each of the intermediate coolers comprises a cylindrical intermediate cooling vessels. The intermediate cooling vessel comprises an intermediate heat exchanger for heat exchange of primary coolants and secondary coolants and recycling pumps for compulsorily recycling primary coolants at the inside thereof. Since a plurality of reactor core containers are thus assembled, a great reactor power can be attained. Further, the module reactor core contained in one reactor core vessel may be small sized, to facilitate the control for the reactor core operation. (I.N.)

  5. The CAREM reactor and present currents in reactor design

    International Nuclear Information System (INIS)

    Ordonez, J.P.

    1990-01-01

    INVAP has been working on the CAREM project since 1983. It concerns a very low power reactor for electrical energy generation. The design of the reactor and the basic criteria used were described in 1984. Since then, a series of designs have been presented for reactors which are similar to CAREM regarding the solutions presented to reduce the chance of major nuclear accidents. These designs have been grouped under different names: Advanced Reactors, Second Generation Reactors, Inherently Safe Reactors, or even, Revolutionary Reactors. Every reactor fabrication firm has, at least, one project which can be placed in this category. Presently, there are two main currents of Reactor Design; Evolutionary and Revolutionary. The present work discusses characteristics of these two types of reactors, some revolutionary designs and common criteria to both types. After, these criteria are compared with CAREM reactor design. (Author) [es

  6. Fort Huachuca to Benefit from New Solar Technology: Dish-Stirling System Couples Solar Power with Engine to Generate Electricity

    National Research Council Canada - National Science Library

    1995-01-01

    ... in partnership with industry. A prototype dish-Stirling solar system, which consists of a large dish of solar concentrators and a Stirling heat engine, will be installed at Fort Huachuca in July and should be in operation about two weeks later...

  7. Neutron behavior, reactor control, and reactor heat transfer. Volume four

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    Volume four covers neutron behavior (neutron absorption, how big are nuclei, neutron slowing down, neutron losses, the self-sustaining reactor), reactor control (what is controlled in a reactor, controlling neutron population, is it easy to control a reactor, range of reactor control, what happens when the fuel burns up, controlling a PWR, controlling a BWR, inherent safety of reactors), and reactor heat transfer (heat generation in a nuclear reactor, how is heat removed from a reactor core, heat transfer rate, heat transfer properties of the reactor coolant)

  8. Trace element, semivolatile organic, and chlorinated organic compound concentrations in bed sediments of selected streams at Fort Gordon, Georgia, February-April 2010

    Science.gov (United States)

    Thomas, Lashun K.; Journey, Celeste A.; Stringfield, Whitney J.; Clark, Jimmy M.; Bradley, Paul M.; Wellborn, John B.; Ratliff, Hagan; Abrahamsen, Thomas A.

    2011-01-01

    A spatial survey of streams was conducted from February to April 2010 to assess the concentrations of major ions, selected trace elements, semivolatile organic compounds, organochlorine pesticides, and polychlorinated biphenyls associated with the bed sediments of surface waters at Fort Gordon military installation near Augusta, Georgia. This investigation expanded a previous study conducted in May 1998 by the U.S. Geological Survey, in cooperation with the U.S. Department of the Army Environmental and Natural Resources Management Office of the U.S. Army Signal Center and Fort Gordon, that evaluated the streambed sediment quality of selected surface waters at Fort Gordon. The data presented in this report are intended to help evaluate bed sediment quality in relation to guidelines for the protection of aquatic life, and identify temporal trends in trace elements and semivolatile organic compound concentrations at streambed sites previously sampled. Concentrations of 34 major ions and trace elements and 102 semivolatile organic, organochlorine pesticide, and polychlorinated biphenyl compounds were determined in the fine-grained fraction of bed sediment samples collected from 13 of the original 29 sites in the previous study, and 22 additional sites at Fort Gordon. Three of the sites were considered reference sites as they were presumed to be located away from potential sources of contaminants and were selected to represent surface waters flowing onto the fort, and the remaining 32 nonreference sites were presumed to be located within the contamination area at the fort. Temporal trends in trace elements and semivolatile organic compound concentrations also were evaluated at 13 of the 32 nonreference sites to provide an assessment of the variability in the number of detections and concentrations of constituents in bed sediment associated with potential sources, accumulation, and attenuation processes. Major ion and trace element concentrations in fine-grained bed

  9. Reactor science and technology: operation and control of reactors

    International Nuclear Information System (INIS)

    Qiu Junlong

    1994-01-01

    This article is a collection of short reports on reactor operation and research in China in 1991. The operation of and research activities linked with the Heavy Water Research Reactor, Swimming Pool Reactor and Miniature Neutron Source Reactor are briefly surveyed. A number of papers then follow on the developing strategies in Chinese fast breeder reactor technology including the conceptual design of an experimental fast reactor (FFR), theoretical studies of FFR thermo-hydraulics and a design for an immersed sodium flowmeter. Reactor physics studies cover a range of topics including several related to work on zero power reactors. The section on reactor safety analysis is concerned largely with the assessment of established, and the presentation of new, computer codes for use in PWR safety calculations. Experimental and theoretical studies of fuels and reactor materials for FBRs, PWRs, BWRs and fusion reactors are described. A final miscellaneous section covers Mo-Tc isotope production in the swimming pool reactor, convective heat transfer in tubes and diffusion of tritium through plastic/aluminium composite films and Li 2 SiO 3 . (UK)

  10. Nuclear power reactors

    International Nuclear Information System (INIS)

    1982-11-01

    After an introduction and general explanation of nuclear power the following reactor types are described: magnox thermal reactor; advanced gas-cooled reactor (AGR); pressurised water reactor (PWR); fast reactors (sodium cooled); boiling water reactor (BWR); CANDU thermal reactor; steam generating heavy water reactor (SGHWR); high temperature reactor (HTR); Leningrad (RMBK) type water-cooled graphite moderated reactor. (U.K.)

  11. Biology and ecology of sickleweed (Falcaria vulgaris) in the Fort Pierre National Grassland of South Dakota

    Science.gov (United States)

    Brian L. Korman

    2011-01-01

    In the last two decades the exotic plant sickleweed (Falcaria vulgaris Bernh., Apiaceae) has invaded, and come to dominate, large areas of the Fort Pierre National Grassland (FPNG) in central South Dakota, USA. Currently sickleweed is estimated to infest over 3200 ha of FPNG. The purpose of this study was to examine several of the biological and ecological traits that...

  12. Inicial nasal mucosa detachment using piezoelectric device in the Le Fort I osteotomy: A technical note

    OpenAIRE

    Shinohara, Elio Hitoshi; Kaba, Shajadi Carlos Pardo; Ruiz, Marcelo Martinson; Horikawa, Fernando Kendi

    2013-01-01

    In maxillary Le Fort I type osteotomy the detachment of the nasal mucosa should be done carefully. Piezoelectric surgery contributed much to increase the safety of osteotomies, despite the initial advantage of minimizing the risk of injury in nervous tissue, mainly in bilateral sagittal split osteotomy; we use the piezoelectric device for the initial detachment of the nasal mucosa in the maxillary osteotomy.

  13. The Effects of Tactical Vehicle Training on the Lands of Fort Carson, Colorado. An Ecological Assessment.

    Science.gov (United States)

    1984-12-01

    p P 28 Table 10 (Cont’d) Fort Carson PJC PJT PC PT Species %C %F %C %F %C %F %C %F Muhlenbergia torreyi P .32 .71 3.45 8.70 2.10 3.00 Oenothera ...look pinkish-white from the flowers of evening primrose ( Oenothera albicaulis) that have invaded the S tracked areas. Other disturbance-related forbs are

  14. Research reactors

    International Nuclear Information System (INIS)

    Merchie, Francois

    2015-10-01

    This article proposes an overview of research reactors, i.e. nuclear reactors of less than 100 MW. Generally, these reactors are used as neutron generators for basic research in matter sciences and for technological research as a support to power reactors. The author proposes an overview of the general design of research reactors in terms of core size, of number of fissions, of neutron flow, of neutron space distribution. He outlines that this design is a compromise between a compact enough core, a sufficient experiment volume, and high enough power densities without affecting neutron performance or its experimental use. The author evokes the safety framework (same regulations as for power reactors, more constraining measures after Fukushima, international bodies). He presents the main characteristics and operation of the two families which represent almost all research reactors; firstly, heavy water reactors (photos, drawings and figures illustrate different examples); and secondly light water moderated and cooled reactors with a distinction between open core pool reactors like Melusine and Triton, pool reactors with containment, experimental fast breeder reactors (Rapsodie, the Russian BOR 60, the Chinese CEFR). The author describes the main uses of research reactors: basic research, applied and technological research, safety tests, production of radio-isotopes for medicine and industry, analysis of elements present under the form of traces at very low concentrations, non destructive testing, doping of silicon mono-crystalline ingots. The author then discusses the relationship between research reactors and non proliferation, and finally evokes perspectives (decrease of the number of research reactors in the world, the Jules Horowitz project)

  15. Roles of plasma neutron source reactor in development of fusion reactor engineering: Comparison with fission reactor engineering

    International Nuclear Information System (INIS)

    Hirayama, Shoichi; Kawabe, Takaya

    1995-01-01

    The history of development of fusion power reactor has come to a turning point, where the main research target is now shifting from the plasma heating and confinement physics toward the burning plasma physics and reactor engineering. Although the development of fusion reactor system is the first time for human beings, engineers have experience of development of fission power reactor. The common feature between them is that both are plants used for the generation of nuclear reactions for the production of energy, nucleon, and radiation on an industrial scale. By studying the history of the development of the fission reactor, one can find the existence of experimental neutron reactors including irradiation facilities for fission reactor materials. These research neutron reactors played very important roles in the development of fission power reactors. When one considers the strategy of development of fusion power reactors from the points of fusion reactor engineering, one finds that the fusion neutron source corresponds to the neutron reactor in fission reactor development. In this paper, the authors discuss the roles of the plasma-based neutron source reactors in the development of fusion reactor engineering, by comparing it with the neutron reactors in the history of fission power development, and make proposals for the strategy of the fusion reactor development. 21 refs., 6 figs

  16. Reactor physics aspects of CANDU reactors

    International Nuclear Information System (INIS)

    Critoph, E.

    1980-01-01

    These four lectures are being given at the Winter Course on Nuclear Physics at Trieste during 1978 February. They constitute part of the third week's lectures in Part II: Reactor Theory and Power Reactors. A physical description of CANDU reactors is given, followed by an overview of CANDU characteristics and some of the design options. Basic lattice physics is discussed in terms of zero energy lattice experiments, irradiation effects and analytical methods. Start-up and commissioning experiments in CANDU reactors are reviewed, and some of the more interesting aspects of operation discussed - fuel management, flux mapping and control of the power distribution. Finally, some of the characteristics of advanced fuel cycles that have been proposed for CANDU reactors are summarized. (author)

  17. Research reactors

    International Nuclear Information System (INIS)

    Kowarski, L.

    1955-01-01

    It brings together the techniques data which are involved in the discussion about the utility for a research institute to acquire an atomic reactor for research purposes. This type of decision are often taken by non-specialist people who can need a brief presentation of a research reactor and its possibilities in term of research before asking advises to experts. In a first part, it draws up a list of the different research programs which can be studied by getting a research reactor. First of all is the reactor behaviour and kinetics studies (reproducibility factor, exploration of neutron density, effect of reactor structure, effect of material irradiation...). Physical studies includes study of the behaviour of the control system, studies of neutron resonance phenomena and study of the fission process for example. Chemical studies involves the study of manipulation and control of hot material, characterisation of nuclear species produced in the reactor and chemical effects of irradiation on chemical properties and reactions. Biology and medicine research involves studies of irradiation on man and animals, genetics research, food or medical tools sterilization and neutron beams effect on tumour for example. A large number of other subjects can be studied in a reactor research as reactor construction material research, fabrication of radioactive sources for radiographic techniques or applied research as in agriculture or electronic. The second part discussed the technological considerations when choosing the reactor type. The technological factors, which are considered for its choice, are the power of the reactor, the nature of the fuel which is used, the type of moderator (water, heavy water, graphite or BeO) and the reflector, the type of coolants, the protection shield and the control systems. In the third part, it described the characteristics (place of installation, type of combustible and comments) and performance (power, neutron flux ) of already existing

  18. Comparison between TRU burning reactors and commercial fast reactor

    International Nuclear Information System (INIS)

    Fujimura, Koji; Sanda, Toshio; Ogawa, Takashi

    2001-03-01

    Research and development for stabilizing or shortening the radioactive wastes including in spent nuclear fuel are widely conducted in view point of reducing the environmental impact. Especially it is effective way to irradiate and transmute long-lived TRU by fast reactors. Two types of loading way were previously proposed. The former is loading relatively small amount of TRU in all commercial fast reactors and the latter is loading large amount of TRU in a few TRU burning reactors. This study has been intended to contribute to the feasibility studies on commercialized fast reactor cycle system. The transmutation and nuclear characteristics of TRU burning reactors were evaluated and compared with those of conventional transmutation system using commercial type fast reactor based upon the investigation of technical information about TRU burning reactors. Major results are summarized as follows. (1) Investigation of technical information about TRU burning reactors. Based on published reports and papers, technical information about TRU burning reactor concepts transmutation system using convectional commercial type fast reactors were investigated. Transmutation and nuclear characteristics or R and D issue were investigated based on these results. Homogeneously loading of about 5 wt% MAs on core fuels in the conventional commercial type fast reactor may not cause significant impact on the nuclear core characteristics. Transmutation of MAs being produced in about five fast reactors generating the same output is feasible. The helium cooled MA burning fast reactor core concept propose by JAERI attains criticality using particle type nitride fuels which contain more than 60 wt% MA. This reactor could transmute MAs being produced in more than ten 1000 MWe-LWRs. Ultra-long life core concepts attaining more than 30 years operation without refueling by utilizing MA's nuclear characteristics as burnable absorber and fertile nuclides were proposed. Those were pointed out that

  19. Nuclear reactor types

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

    The characteristics of different reactor types designed to exploit controlled fission reactions are explained. Reactors vary from low power research devices to high power devices especially designed to produce heat, either for direct use or to produce steam to drive turbines to generate electricity or propel ships. A general outline of basic reactors (thermal and fast) is given and then the different designs considered. The first are gas cooled, including the Magnox reactors (a list of UK Magnox stations and reactor performance is given), advanced gas cooled reactors (a list of UK AGRs is given) and the high temperature reactor. Light water cooled reactors (pressurized water [PWR] and boiling water [BWR] reactors) are considered next. Heavy water reactors are explained and listed. The pressurized heavy water reactors (including CANDU type reactors), boiling light water, steam generating heavy water reactors and gas cooled heavy water reactors all come into this category. Fast reactors (liquid metal fast breeder reactors and gas cooled fast reactors) and then water-cooled graphite-moderated reactors (RBMK) (the type at Chernobyl-4) are discussed. (U.K.)

  20. 78 FR 37527 - Draft Environmental Impact Statement for the Disposition of Hangars 2 and 3, Fort Wainwright, Alaska

    Science.gov (United States)

    2013-06-21

    ... Statement (EIS) for the disposition of two historic hangars at Fort Wainwright (FWA). The Draft EIS analyzes and evaluates the potential environmental impacts associated with proposed disposition options for two historic World War II-era hangars (Hangars 2 and 3) and supporting infrastructure located on the Main Post...

  1. 75 FR 27996 - Record of Decision (ROD) for the Training Land Acquisition (Including Purchase and Lease) at Fort...

    Science.gov (United States)

    2010-05-19

    ... DEPARTMENT OF DEFENSE Department of the Army Record of Decision (ROD) for the Training Land Acquisition (Including Purchase and Lease) at Fort Polk, LA AGENCY: Department of the Army, DoD. ACTION... which summarizes and documents its decision to proceed with Alternative 3, the acquisition of up to 100...

  2. Reactor containment and reactor safety in the United States

    International Nuclear Information System (INIS)

    Kouts, H.

    1986-01-01

    The reactor safety systems of two reactors are studied aiming at the reactor containment integrity. The first is a BWR type reactor and is called Peachbottom 2, and the second is a PWR type reactor, and is called surry. (E.G.) [pt

  3. Nasomaxillary hypoplasia with a congenitally missing tooth treated with LeFort II osteotomy, autotransplantation, and nickel-titanium alloy wire.

    Science.gov (United States)

    Ishida, Takayoshi; Ikemoto, Shigehiro; Ono, Takashi

    2015-09-01

    In some skeletal Class III adult patients with nasomaxillary hypoplasia, the LeFort I osteotomy provides insufficient correction. This case report describes a 20-year-old woman with a combination of nasomaxillary hypoplasia and a protrusive mandible with a congenitally missing mandibular second premolar. We performed a LeFort II osteotomy for maxillary advancement. Autotransplantation of a tooth was also performed; the donor tooth was used to replace the missing permanent tooth. To increase the chance of success, we applied light continuous force with an improved superelastic nickel-titanium alloy wire technique before extraction and after transplantation. The patient's profile and malocclusion were corrected, and the autotransplanted tooth functioned well. The postero-occlusal relationships were improved, and ideal overbite and overjet relationships were achieved. The methods used in this case represent a remarkable treatment. Copyright © 2015 American Association of Orthodontists. Published by Elsevier Inc. All rights reserved.

  4. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2002-01-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised

  5. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

  6. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

  7. Computerized training program usage at the Fort Calhoun Nuclear Power Station

    International Nuclear Information System (INIS)

    Ruzic, D.H.; Reed, W.H.; Lawton, R.K.; Fluehr, J.J.

    1987-01-01

    The increased US Nuclear Regulatory Commission and Institute of Nuclear Power Operations (INPO) interest in the nuclear power industry training programs resulted in the Omaha Public Power District staff at the Fort Calhoun Nuclear Power Station investigating the potential for computerizing their recently accredited training records, student training requirements, and the process of determining student certification status. Additional areas that were desirable were a computerized question data bank with random test generation, maintaining history of question usage, and tracking of the job task analysis process and course objectives. SCI Software's online personnel training information management system (OPTIM) was selected, subsequent to a bid evaluation, to provide these features while operating on the existing corporate IBM mainframe

  8. Le traité de Fort Jackson, 9 août 1814

    Directory of Open Access Journals (Sweden)

    Jean‑Marc Serme

    2006-04-01

    Full Text Available This paper aims to show the motives and goals of the different actors of the War of 1812 as expressed through the Muscogee Creek War (1813‑1814. The fate of the region was sealed when a gigantic land cession was conceded by Native Americans in the Treaty of Fort Jackson. Aug.9, 1814, symbolizes both the end of Native American clout in the Old Southwest and the beginning of a new era in Southern history. Andrew Jackson played a key‑role in this shift in power. Other individuals, but also social groups and entire nations were involved in a complex web of relationships and cultural, political and economic conflicts.

  9. Reactor

    International Nuclear Information System (INIS)

    Toyama, Masahiro; Kasai, Shigeo.

    1978-01-01

    Purpose: To provide a lmfbr type reactor wherein effusion of coolants through a loop contact portion is reduced even when fuel assemblies float up, and misloading of reactor core constituting elements is prevented thereby improving the reactor safety. Constitution: The reactor core constituents are secured in the reactor by utilizing the differential pressure between the high-pressure cooling chamber and low-pressure cooling chamber. A resistance port is formed at the upper part of a connecting pipe, and which is connect the low-pressure cooling chamber and the lower surface of the reactor core constituent. This resistance part is formed such that the internal sectional area of the connecting pipe is made larger stepwise toward the upper part, and the cylinder is formed larger so that it profiles the inner surface of the connecting pipe. (Aizawa, K.)

  10. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

  11. [The regulation of microecological disorders of the intestines in newborn infants with perinatal pathology using the new probiotic bifidumbacterin-forte].

    Science.gov (United States)

    Iakushenko, M N; Tkhagapsoeva, Zh M; Bondarenko, V M

    1997-01-01

    The study was made on 93 newborn infants with perinatal pathology, among them infants with the perinatal lesion of the central nervous system (52), hemolytic disease of newborns (19) and conjugation jaundice (12). All newborn infants were examined for the presence of intestinal microflora in its dynamics and for the state microbiocenosis, evaluated by the rapid method based on the determination of the caseinolytic activity of fecal supernatants after the correction of normal flora with bifidumbacterin in 55 infants and with bifidumbacterin-forte in 38 infants. The comparative study of these two preparations revealed that the use of probiotics containing Bifidobacterium bifidum was mainly substitutional, promoting the colonization of the intestine by lactobacteria, which later determined the suppression opportunistic microflora. The effectiveness of bifidumbacterin-forte containing live B. bifidum, immobilized on sorbent, proved to be most pronounced.

  12. Ecological restoration experiments (1992-2007) at the G.A. Pearson Natural Area, Fort Valley Experimental Forest (P-53)

    Science.gov (United States)

    Margaret M. Moore; Wallace Covington; Peter Z. Fulé; Stephen C. Hart; Thomas E. Kolb; Joy N. Mast; Stephen S. Sackett; Michael R. Wagner

    2008-01-01

    In 1992 an experiment was initiated at the G. A. Pearson Natural Area on the Fort Valley Experimental Forest to evaluate long-term ecosystem responses to two restoration treatments: thinning only and thinning with prescribed burning. Fifteen years of key findings about tree physiology, herbaceous, and ecosystem responses are presented.

  13. First records of two species of mammals in the Huachuca Mountains: results of ecological stewardship at Fort Huachuca

    Science.gov (United States)

    Ronnie Sidner; H. Sheridan Stone

    2005-01-01

    We report the first voucher of the cliff chipmunk (Neotamias dorsalis) and observations of Brazilian free-tailed bats (Tadarida brasiliensis) from the Huachuca Mountains, Arizona, where these species had not been documented. While presence of T. brasiliensis was expected on Fort Huachuca, N. dorsalis was a surprise after a century...

  14. Research reactor standards and their impact on the TRIGA reactor community

    International Nuclear Information System (INIS)

    Richards, W.J.

    1980-01-01

    The American Nuclear Society has established a standards committee devoted to writing standards for research reactors. This committee was formed in 1971 and has since that time written over 15 standards that cover all aspects of research reactor operation. The committee has representation from virtually every group concerned with research reactors and their operation. This organization includes University reactors, National laboratory reactors, Nuclear Regulatory commission, Department of Energy and private nuclear companies and insurers. Since its beginning the committee has developed standards in the following areas: Standard for the development of technical specifications for research reactors; Quality control for plate-type uranium-aluminium fuel elements; Records and reports for research reactors; Selection and training of personnel for research reactors; Review of experiments for research reactors; Research reactor site evaluation; Quality assurance program requirements for research reactors; Decommissioning of research reactors; Radiological control at research reactor facilities; Design objectives for and monitoring of systems controlling research reactor effluents; Physical security for research reactor facilities; Criteria for the reactor safety systems of research reactors; Emergency planning for research reactors; Fire protection program requirements for research reactors; Standard for administrative controls for research reactors. Besides writing the above standards, the committee is very active in using communications with the nuclear regulatory commission on proposed rules or positions which will affect the research reactor community

  15. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

    Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation.The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also exp

  16. Inicial nasal mucosa detachment using piezoelectric device in the Le Fort I osteotomy: A technical note

    Science.gov (United States)

    Shinohara, Elio Hitoshi; Kaba, Shajadi Carlos Pardo; Ruiz, Marcelo Martinson; Horikawa, Fernando Kendi

    2013-01-01

    In maxillary Le Fort I type osteotomy the detachment of the nasal mucosa should be done carefully. Piezoelectric surgery contributed much to increase the safety of osteotomies, despite the initial advantage of minimizing the risk of injury in nervous tissue, mainly in bilateral sagittal split osteotomy; we use the piezoelectric device for the initial detachment of the nasal mucosa in the maxillary osteotomy. PMID:23853472

  17. Inicial nasal mucosa detachment using piezoelectric device in the Le Fort I osteotomy: A technical note

    Directory of Open Access Journals (Sweden)

    Elio Hitoshi Shinohara

    2013-01-01

    Full Text Available In maxillary Le Fort I type osteotomy the detachment of the nasal mucosa should be done carefully. Piezoelectric surgery contributed much to increase the safety of osteotomies, despite the initial advantage of minimizing the risk of injury in nervous tissue, mainly in bilateral sagittal split osteotomy; we use the piezoelectric device for the initial detachment of the nasal mucosa in the maxillary osteotomy.

  18. Chitosan Dilutable and Dilactin Forte: Assessment of Their Efficiency for Safety and Quality of Foodstuff

    Science.gov (United States)

    Iurchikova, N.; Khlebosolova, O.

    2018-01-01

    The modern natural food preservatives used to process and store foodstuff allow to ensure its safety and high quality. Chitosan and dilactin-forte are among such medicines. These preservatives are not only safe, but also are beneficial to a human body in virtue of their effects onto human digestive system. The article describes the results of the research conducted to identify the impact of these natural preservatives on safety of carrot (Daucus carota subsp. sativus)

  19. Improved nuclear reactor construction with bottom supported reactor vessel

    International Nuclear Information System (INIS)

    Sharbaugh, J.E.

    1987-01-01

    An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding liquid metal coolant and housing the core within the pool. A generally cylindrical concrete containment structure surrounds the reactor vessel and a central support pedestal is anchored to the containment structure base mat and supports the bottom wall of the reactor vessel and the reactor core. The periphery of the reactor vessel bore is supported by an annular structure which allows thermal expansion but not seismic motion of the vessel, and a bed of thermally insulating material uniformly supports the vessel base whilst allowing expansion thereof. A guard ring prevents lateral seismic motion of the upper end of the reactor vessel. The periphery of the core is supported by an annular structure supported by the vessel base and keyed to the vessel wall so as to be able to expand but not undergo seismic motion. A deck is supported on the containment structure above the reactor vessel open top by annular bellows, the deck carrying the reactor control rods such that heating of the reactor vessel results in upward expansion against the control rods. (author)

  20. Reactor as furnace and reactor as lamp

    International Nuclear Information System (INIS)

    Goldanskii, V.I.

    1992-01-01

    There are presented general characteristics of the following ways of transforming of nuclear energy released in reactors into chemical : ordinary way (i.e. trough the heat, mechanical energy and electricity); chemonuclear synthesis ; use of high-temperature fuel elements (reactor as furnace); use of the mixed nγ-radiation of reactors; use of the radiation loops; radiation - photochemical synthesis (reactor as lamp). Advantage and disadvantages of all above variants are compared. The yield of the primary product of fixation of nitrogen (nitric oxide NO) in reactor with the high-temperature (above ca. 1900degC) fuel elements (reactor-furnace) can exceed W ∼ 200 kg per gram of burned uranium. For the latter variant (reactor-lamp) the yield of chemical products can reach W ∼ 60 kg. per gram of uranium. Such values of W are close to or even strongly exceed the yields of chemical products for other abovementioned variants and - what is particularly important - are not connected to the necessity of archscrupulous removal of radioactive contamination of products. (author)

  1. Development of Reactor Console Simulator for PUSPATI TRIGA Reactor

    International Nuclear Information System (INIS)

    Mohd Idris Taib; Izhar Abu Hussin; Mohd Khairulezwan Abdul Manan; Nufarhana Ayuni Joha; Mohd Sabri Minhat

    2012-01-01

    The Reactor Console Simulator will be an interactive tool for operator training and teaching of PUSPATI TRIGA Reactor. Behaviour and characteristic for reactor console and reactor itself can be evaluated and understand. This Simulator will be used as complement for actual present reactor console. Implementation of man-machine interface is using computer screens, keyboard and mouse. Multiple screens are used to match the physical of present reactor console. LabVIEW software are using for user interface and mathematical calculation. Polynomial equation based on control rods calibration data as well as operation parameters record was used to calculate the estimated reactor console parameters. (author)

  2. Budget Impact Analysis of Oral Fisiogen Ferro Forte® versus Intravenous Iron for the Management of Iron Deficiency in Chronic Kidney Disease in Spain.

    Science.gov (United States)

    Darbà, Josep; Ascanio, Meritxell

    2018-06-22

    Iron deficiency is a frequent complication of chronic kidney disease (CKD) that is associated with a decrease in the quality of life of patients and an increase in the risk of other clinical complications. Iron therapy represents one of the fundamentals of patients with CKD. Sucrosomial ® oral iron allows Fisiogen Ferro Forte ® to be used in all patients who are intolerant to treatment by the oral route of administration, or who present with malabsorption of conventional oral iron preparations. The main objective of this study was to assess the economic impact of the oral iron Fisiogen Ferro Forte ® for the management of iron deficiency in CKD patients in Spain. A 4-year budget impact model was developed for the period 2017-2020 for CKD patients with iron deficiency who were candidates for intravenous iron due to a lack of response to oral iron, from the perspective of the Spanish healthcare system. Three subgroups of CKD patients were included in the analysis: predialysis, peritoneal dialysis, and post-transplant. The intravenous iron formulations Ferinject ® , Venofer ® , and Feriv ® were considered appropriate comparators to be used in the model. National data on the prevalence of CKD for the three subgroups of patients were obtained from the literature, and input data on drug utilization and outpatient hospitalizations associated with iron administration were obtained by consulting nephrologists. Nephrology experts were also asked about resources used during medical visits and monitoring tests. Based on the unit costs for each iron therapy and the resources used, the total treatment cost per patient associated with each product was obtained to estimate the global budget impact of increasing the use of Fisiogen Ferro Forte ® . The average annual budget savings due to an increase in Fisiogen Ferro Forte ® and a decrease in intravenous iron have been estimated at €398,685, €180,937, and €195,842 over 4 years for the predialysis, peritoneal dialysis

  3. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

    Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

  4. Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) are compared

    International Nuclear Information System (INIS)

    Greneche, D.

    2014-01-01

    This article compares the 2 types of light water reactors that are used to produce electricity: the Pressurized Water Reactor (PWR) and the Boiling Water Reactor (BWR). Historically the BWR concept was developed after the PWR concept. Today 80% of light water reactors operating in the world are of PWR-type. This comparison is comprehensive and detailed. First the main technical features are reviewed and compared: reactor architecture, core and fuel design, reactivity control, reactor vessel, cooling systems and reactor containment. Secondly, various aspects concerning reactor operations like reactor control, fuel management, maintenance, inspections, radiation protection, waste generation and reactor reliability are presented and compared for both reactors. As for the issue of safety, it is highlighted that the accidental situations are too different for the 2 reactors to be compared. The main features of reactor safety are explained for both reactors

  5. Depositional environment of the Fort Member of the Jurasic Jaisalmer Formation (western Rajasthan, India), as revealed from lithofacies and grain-size analysis

    International Nuclear Information System (INIS)

    Ahmad, F.; Quasim, M.; Ghaznavi, A.; Khan, Z.; Ahmad, A.H.M.

    2017-01-01

    Lithofacies and granulometric analysis were carried out to decipher the depositional environment of the Fort Member of the Jurassic Jaisalmer Formation. Based on field data nine lithofacies have been identified including trough cross-bedded sandstones, planar cross-bedded sandstones, matrix supported conglomerates, thinly bedded siltstone and sandstones, herringbone cross-bedded sandstones, wave rippled sandstones, laminated sandstones, hummocky cross-bedded sandstones, limestones and shales. Granulometric analysis of the sandstones samples has been carried out for their statistical and textural parameters. Bivariant plots of textural parameters such as graphic skewness versus graphic standard deviation and kewness versus standard deviation confirm the high energy (beach) origin of sandstones. These results suggest a wide spectrum of marine environments ranging from inner shelf to upper shoreface for the Fort Member sandstones.

  6. Control of reactor coolant flow path during reactor decay heat removal

    International Nuclear Information System (INIS)

    Hunsbedt, A.N.

    1988-01-01

    This patent describes a sodium cooled reactor of the type having a reactor hot pool, a slightly lower pressure reactor cold pool and a reactor vessel liner defining a reactor vessel liner flow gap separating the hot pool and the cold pool along the reactor vessel sidewalls and wherein the normal sodium circuit in the reactor includes main sodium reactor coolant pumps having a suction on the lower pressure sodium cold pool and an outlet to a reactor core; the reactor core for heating the sodium and discharging the sodium to the reactor hot pool; a heat exchanger for receiving sodium from the hot pool, and removing heat from the sodium and discharging the sodium to the lower pressure cold pool; the improvement across the reactor vessel liner comprising: a jet pump having a venturi installed across the reactor vessel liner, the jet pump having a lower inlet from the reactor vessel cold pool across the reactor vessel liner and an upper outlet to the reactor vessel hot pool

  7. The research reactors their contribution to the reactors physics

    International Nuclear Information System (INIS)

    Barral, J.C.; Zaetta, A.; Johner, J.; Mathoniere, G.

    2000-01-01

    The 19 october 2000, the french society of nuclear energy organized a day on the research reactors. This associated report of the technical session, reactors physics, is presented in two parts. The first part deals with the annual meeting and groups general papers on the pressurized water reactors, the fast neutrons reactors and the fusion reactors industry. The second part presents more technical papers about the research programs, critical models, irradiation reactors (OSIRIS and Jules Horowitz) and computing tools. (A.L.B.)

  8. Reactor noise analysis of experimental fast reactor 'JOYO'

    International Nuclear Information System (INIS)

    Ohtani, Hideji; Yamamoto, Hisashi

    1980-01-01

    As a part of dynamics tests in experimental fast reactor ''JOYO'', reactor noise tests were carried out. The reactor noise analysis techniques are effective for study of plant characteristics by determining fluctuations of process signals (neutron signal, reactor inlet temperature signals, etc.), which are able to be measured without disturbances for reactor operations. The aims of reactor noise tests were to confirm that no unstable phenomenon exists in ''JOYO'' and to gain initial data of the plant for reference of the future data. Data for the reactor noise tests treated in this paper were obtained at 50 MW power level. Fluctuations of process signals were amplified and recorded on analogue tapes. The analysis was performed using noise code (NOISA) of digital computer, with which statistical values of ASPD (auto power spectral density), CPSD (cross power spectral density), and CF (coherence function) were calculated. The primary points of the results are as follows. 1. RMS value of neutron signal at 50 MW power level is about 0.03 MW. This neutron fluctuation is not disturbing reactor operations. 2. The fluctuations of A loop reactor inlet temperatures (T sub(AI)) are larger than the fluctuations of B loop reactor inlet temperature (T sub(BI)). For this reason, the major driving force of neutron fluctuations seems to be the fluctuations of T sub(AI). 3. Core and blanket subassemblies can be divided into two halves (A and B region), with respect to the spacial motion of temperature in the reactor core. A or B region means the region in which sodium temperature fluctuations in subassembly are significantly affected by T sub(AI) or T sub(BI), respectively. This phenomenon seems to be due to the lack of mixing of A and B loop sodium in lower plenum of reactor vessel. (author)

  9. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Ronen, Y.; Elias, E.

    1994-01-01

    Mathematical methods and computer calculations for nuclear and thermonuclear reactor kinetics, reactor physics, neutron transport theory, core lattice parameters, waste treatment by transmutation, breeding, nuclear and thermonuclear fuels are the main interests of the conference

  10. Reactor water spontaneous circulation structure in reactor pressure vessel

    International Nuclear Information System (INIS)

    Takahashi, Kazumi

    1998-01-01

    The gap between the inner wall of a reactor pressure vessel of a BWR type reactor and a reactor core shroud forms a down comer in which reactor water flows downwardly. A feedwater jacket to which feedwater at low temperature is supplied is disposed at the outer circumference of the pressure vessel just below a gas/water separator. The reactor water at the outer circumferential portion just below the air/water separator is cooled by the feedwater jacket, and the feedwater after cooling is supplied to the feedwater entrance disposed below the feedwater jacket by way of a feedwater introduction line to supply the feedwater to the lower portion of the down comer. This can cool the reactor water in the down comer to increase the reactor water density in the down comer thereby forming strong downward flows and promote the recycling of the reactor water as a whole. With such procedures, the reactor water can be recycled stably only by the difference of the specific gravity of the reactor water without using an internal pump. In addition, the increase of the height of the pressure vessel can be suppressed. (I.N.)

  11. Reactor

    International Nuclear Information System (INIS)

    Ikeda, Masaomi; Kashimura, Kazuo; Inoue, Kazuyuki; Nishioka, Kazuya.

    1979-01-01

    Purpose: To facilitate the construction of a reactor containment building, whereby the inspections of the outer wall of a reactor container after the completion of the construction of the reactor building can be easily carried out. Constitution: In a reactor accommodated in a container encircled by a building wall, a space is provided between the container and the building wall encircling the container, and a metal wall is provided in the space so that it is fitted in the building wall in an attachable or detatchable manner. (Aizawa, K.)

  12. Chemistry, toxicology, and persistence of particulates during and after the 2016 Fort McMurray Wildfires in Alberta, Canada

    Science.gov (United States)

    Kohl, L.; Chan, A. W. H.; Cooke, C. A.; Hustins, S.; Jackson, B.; Wang, S.; Jing, X.; Meng, M.

    2017-12-01

    The Horse River Fire in May 2016 forced the evacuation of 88,000 Fort McMurray residents, and led to the destruction of over 2000 houses. After re-entry to homes, there is significant concern about exposures to residual fire-derived contaminants in residential houses. Wildfire research, however, provides little guidance on how long ashes and pollutants persist in household dust after major fires. The FACET project studies the chemistry and toxicology of samples of urban and forest ashes and airborne particles collected during the fire, as well as over 500 house dust samples collected in July 2017 (14 months after the fire). Here we present results on the chemical composition of the urban and forest ash samples collected during the fire along with initial results from house dust samples. Wildfire ashes contained elevated concentrations of polycyclic aromatic hydrocarbons (PAH), heavy metals, and dioxin like compounds (DLC). Relative to EPA reference doses, As and Sb constitute the greatest non-carcinogenic health hazard, whereas PAHs Benzo(a)pyrene and Indeno(1,2,3-cd)pyrene are the most relevant carcinogens. Ashes from urban locations contained higher concentrations of heavy metals and DLC than samples collected from forested areas outside of the City of Fort McMurray. Urban samples furthermore had a greater potential for generating oxidative stress than rural samples, as determined by dithiothreitol (DTT) consumption assays. The oxidative potential was positively correlated to Al, Cu, As, and V concentrations. Airborne particulate matter samples from the smoke plume contained consistent concentrations of levoglucosan (99 ± 5 mg g-1), along with other tracers for biomass burning (free lignin monomers, retene). Together these results will serve as proxies for understanding the contribution and the persistence of fire-derived pollutants in house dust in Fort McMurray homes.

  13. Reactor Physics Training

    International Nuclear Information System (INIS)

    Baeten, P.

    2007-01-01

    University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

  14. NRHP Eligibility of the Fort Huachuca, Arizona, Elevated Water Tank (Facility 49001) and Reservoir (Facility 22020)

    Science.gov (United States)

    2016-08-01

    historic district. DISCLAIMER: The contents of this report are not to be used for advertising , publication, or promotional purposes. Citation of trade...district, Fort Huachuca Historic District, nestled in a valley overlooking the San Pedro River valley (Figure 1). The Army established Camp Huachuca in...designs serve a secondary advertising purpose (e.g., the water tower at the G. S. Suppiger catsup bottling plant in Collinsville, Illinois, Figure

  15. 75 FR 55401 - Notice of Intent To Rule on Request To Release Airport Property at the Dallas/Fort Worth...

    Science.gov (United States)

    2010-09-10

    ... To Release Airport Property at the Dallas/Fort Worth International Airport, DFW Airport, TX AGENCY... airport property. SUMMARY: The FAA proposes to rule and invite public comment on the request for permanent... H. Ford Aviation Investment Reform Act for the 21st Century (AIR 21). DATES: Comments must be...

  16. 78 FR 9105 - Notice of Intent To Rule on Request To Release Airport Property at the Dallas/Fort Worth...

    Science.gov (United States)

    2013-02-07

    ... To Release Airport Property at the Dallas/Fort Worth International Airport, DFW Airport, TX AGENCY... Airport Property. SUMMARY: The FAA proposes to rule and invite public comment on the request for permanent... H. Ford Aviation Investment Reform Act for the 21st Century (AIR 21). DATES: Comments must be...

  17. History of the Fort Collins Science Center, U.S. Geological Survey

    Science.gov (United States)

    O'Shea, Thomas J. (compiler)

    2006-01-01

    The U.S. Geological Survey’s Fort Collins Science Center ("the Center") has been a nucleus of research, technology development, and associated scientific activities within the Department of the Interior for more than 30 years. The Center’s historical activities are deeply rooted in federal biological resources research and its supporting disciplines, particularly as they relate to the needs of the U.S. Department of the Interior and its resource management agencies. The organizational framework and activities of the Center have changed and adapted over the years in response to shifts in the scientific issues and challenges facing the U.S. Department of the Interior and with the development of new strategies to meet these challenges. Thus, the history of the Center has been dynamic.

  18. FBR type reactor

    International Nuclear Information System (INIS)

    Kimura, Kimitaka; Fukuie, Ken; Iijima, Tooru; Shimpo, Masakazu.

    1994-01-01

    In an FBR type reactor for exchanging fuels by pulling up reactor core upper mechanisms, a connection mechanism is disposed for connecting the top of the reactor core and the lower end of the reactor core upper mechanisms. In addition, a cylindrical body is disposed surrounding the reactor core upper mechanisms, and a support member is disposed to the cylindrical body for supporting an intermediate portion of the reactor core upper mechanisms. Then, the lower end of the reactor core upper mechanisms is connected to the top of the reactor core. Same displacements are caused to both of them upon occurrence of earthquakes and, as a result, it is possible to eliminate mutual horizontal displacement between a control rod guide hole of the reactor core upper mechanisms and a control rod insertion hole of the reactor core. In addition, since the intermediate portion of the reactor core upper mechanisms is supported by the support member disposed to the cylindrical body surrounding the reactor core upper mechanisms, deformation caused to the lower end of the reactor core upper mechanisms is reduced, so that the mutual horizontal displacement with respect to the control rod insertion hole of the reactor core can be reduced. As a result, performance of control rod insertion upon occurrence of the earthquakes is improved, so that reactor shutdown is conducted more reliably to improve reactor safety. (N.H.)

  19. RB Research nuclear reactor RB reactor, Annual report for 2000

    International Nuclear Information System (INIS)

    Milosevic, M.

    2000-12-01

    Report on RB reactor operation during 2000 contains 3 parts. Part one contains a brief description of reactor operation and reactor components, relevant dosimetry data and radiation protection issues, personnel and financial data. Part two is devoted to maintenance of the reactor components, namely, fuel, heavy water, reactor vessel, heavy water circulation system, absorption rods and heavy water level-meters, maintenance of electronic, mechanical, electrical and auxiliary equipment. Part three contains data concerned with reactor operation and utilization with a comprehensive list of publications resulting from experiments done at the RB reactor. It contains data about reactor operation during previous 14 years, i.e. from 1986 - 2000

  20. Reactor container

    International Nuclear Information System (INIS)

    Kato, Masami; Nishio, Masahide.

    1987-01-01

    Purpose: To prevent the rupture of the dry well even when the melted reactor core drops into a reactor pedestal cavity. Constitution: In a reactor container in which a dry well disposed above the reactor pedestal cavity for containing the reactor pressure vessel and a torus type suppression chamber for containing pressure suppression water are connected with each other, the pedestal cavity and the suppression chamber are disposed such that the flow level of the pedestal cavity is lower than the level of the pressure suppression water. Further, a pressure suppression water introduction pipeway for introducing the pressure suppression water into the reactor pedestal cavity is disposed by way of an ON-OFF valve. In case if the melted reactor core should fall into the pedestal cavity, the ON-OFF valve for the pressure suppression water introduction pipeway is opened to introduce the pressure suppression water in the suppression chamber into the pedestal cavity to cool the melted reactor core. (Ikeda, J.)

  1. Reactor Physics Programme

    Energy Technology Data Exchange (ETDEWEB)

    De Raedt, C

    2000-07-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

  2. Reactor Physics Programme

    International Nuclear Information System (INIS)

    De Raedt, C.

    2000-01-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

  3. Effectiveness of adenoplex forte with or without heparegene as radioprotective and curative agent for controlling radiation induced hepatic metabolic dysfunction

    International Nuclear Information System (INIS)

    Mohamed, S.H.; EL-Sayed, N.M.; Hussein, A.M.

    2004-01-01

    The present work aims to evaluate the combined radioprotective and curative capacities of a known drug namely adenoplex forte [combination of adenosine tetraphosphate (ATP), co carboxylase, cyanocobalamin (Bn) and nicotinamide (vitamin P.P)] in dependency or in combination with heparegen [thiazolidine 4 -carboxylic acid] on liver metabolic processes of rats irradiated at 5 Gy. Therefore, the levels of plasma total lipids, triglycerides, total cholesterol, HDL-cholesterol and LDL-cholesterol were estimated as indicative parameters for lipid metabolism. Estimations of plasma glucose, pyruvate and lactate levels as well as liver glycogen content were employed as a useful means for testing the carbohydrate metabolism. The tested parameters were undertaken on 3, 7, 14, 21 and 30 days post-radiation exposure of rats to 5 Gy. Data of the present study revealed that exposure of rats to gamma irradiation at a dose level of 5 Gy was associated with disturbances in liver metabolic functions as reflected by alterations observed in all the tested parameters of both lipid and carbohydrate metabolism up to 30 days post-irradiation. The data further indicated that appropriate use of the selected drug adenoplex forte either independently or in combination with heparegen can preferentially modify liver metabolic disturbances induced by radiation exposure, which creates a therapeutic advantage in radiation therapy. In conclusion, this study suggest the potential use of adenoplex forte (with dose of 290 mg/kg) in combination with heparegen (with dose of 2 mg/kg) in patients receiving radiotherapy and suffering disturbed liver metabolic function mainly in carbohydrate and lipid metabolism

  4. Analysis of Atmospheric Mercury and Associated Trace Gases in Dallas Fort Worth, TX (Barnett Shale area)

    Science.gov (United States)

    Laine, P. L.; Talbot, R. W.; Lefer, B. L.; Flynn, J. H.

    2012-12-01

    Throughout the month of June 2011, a variety of air quality measurements were obtained in the Dallas Fort Worth (Barnett Shale) field campaign. Species such as Hg0, O3, CO, NO, NO2, SO2 were monitored continuously along with a variety of volatile organic carbon (VOC) species ranging in size from C2 (ethane) to C9 aromatics to sesquiterpines. Mixed layer boundary heights were also monitored by Ceilometer measurements. At first glance, the mercury data has peaks that reach as high as 750 ppqv (parts per quadrillion by volume) which is approximately a 5 fold increase over the typical background values observed (~ 150 ppqv). The Fort Worth area has underlying Barnett Shale with thousands of natural gas compressor stations scattered throughout the surrounding landscape. We believe that a potential source of the elevated Hg0 is the result of leakage from these stations under the nocturnal boundary layer. A closer look at diurnal variations and backward wind trajectories will yield information pertaining to the types of air masses spanning the area. We will utilize the suite of chemical and meteorological measurements conducted during the campaign to facilitate source identification for specific time periods. Analysis of these data should provide new information on as yet unexplored sources of atmospheric mercury.

  5. Nuclear reactors. Introduction

    International Nuclear Information System (INIS)

    Boiron, P.

    1997-01-01

    This paper is an introduction to the 'nuclear reactors' volume of the Engineers Techniques collection. It gives a general presentation of the different articles of the volume which deal with: the physical basis (neutron physics and ionizing radiations-matter interactions, neutron moderation and diffusion), the basic concepts and functioning of nuclear reactors (possible fuel-moderator-coolant-structure combinations, research and materials testing reactors, reactors theory and neutron characteristics, neutron calculations for reactor cores, thermo-hydraulics, fluid-structure interactions and thermomechanical behaviour of fuels in PWRs and fast breeder reactors, thermal and mechanical effects on reactors structure), the industrial reactors (light water, pressurized water, boiling water, graphite moderated, fast breeder, high temperature and heavy water reactors), and the technology of PWRs (conceiving and building rules, nuclear parks and safety, reactor components and site selection). (J.S.)

  6. Nuclear reactor, reactor core thereof, and device for constituting the reactor

    International Nuclear Information System (INIS)

    Takiyama, Masashi.

    1994-01-01

    A reactor core is constituted by charging coolants (light water) in a reactor pressure vessel and distributing fuel assemblies, reflecting material sealing pipes, moderator (heavy water and helium gas) sealing pipes, and gas sealing pipes therein. A fuel guide tube is surrounded by a cap and the gap therebetween is made hollow and filled with coolant steams. The cap is supported by a baffle plate. The moderator sealing pipe is disposed in a flow channel of coolants in adjacent with the cap. The position of the moderator sealing tube in the reactor core is controlled by water stream from a hydraulic pump with a guide tube extending below the baffle plate being as a guide. Then, the position of the moderator sealing tube is varied to conduct power control, burnup degree compensation, and reactor shut down. With such procedures, moderator cooling facility is no more necessary to simplify the structure. Further, heat generated from the moderator is transferred to the coolants thereby improving heat efficiency of the reactor. (I.N.)

  7. Slurry reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kuerten, H; Zehner, P [BASF A.G., Ludwigshafen am Rhein (Germany, F.R.)

    1979-08-01

    Slurry reactors are designed on the basis of empirical data and model investigations. It is as yet not possible to calculate the flow behavior of such reactors. The swarm of gas bubbles and cluster formations of solid particles and their interaction in industrial reactors are not known. These effects control to a large extent the gas hold-up, the gas-liquid interface and, similarly as in bubble columns, the back-mixing of liquids and solids. These hydrodynamic problems are illustrated in slurry reactors which constructionally may be bubble columns, stirred tanks or jet loop reactors. The expected effects are predicted by means of tests with model systems modified to represent the conditions in industrial hydrogenation reactors. In his book 'Mass Transfer in Heterogeneous Catalysis' (1970) Satterfield complained of the lack of knowledge about the design of slurry reactors and hence of the impossible task of the engineer who has to design a plant according to accepted rules. There have been no fundamental changes since then. This paper presents the problems facing the engineer in designing slurry reactors, and shows new development trends.

  8. Optimal reactor strategy for commercializing fast breeder reactors

    International Nuclear Information System (INIS)

    Yamaji, Kenji; Nagano, Koji

    1988-01-01

    In this paper, a fuel cycle optimization model developed for analyzing the condition of selecting fast breeder reactors in the optimal reactor strategy is described. By dividing the period of planning, 1966-2055, into nine ten-year periods, the model was formulated as a compact linear programming model. With the model, the best mix of reactor types as well as the optimal timing of reprocessing spent fuel from LWRs to minimize the total cost were found. The results of the analysis are summarized as follows. Fast breeder reactors could be introduced in the optimal strategy when they can economically compete with LWRs with 30 year storage of spent fuel. In order that fast breeder reactors monopolize the new reactor market after the achievement of their technical availability, their capital cost should be less than 0.9 times as much as that of LWRs. When a certain amount of reprocessing commitment is assumed, the condition of employing fast breeder reactors in the optimal strategy is mitigated. In the optimal strategy, reprocessing is done just to meet plutonium demand, and the storage of spent fuel is selected to adjust the mismatch of plutonium production and utilization. The price hike of uranium ore facilitates the commercial adoption of fast breeder reactors. (Kako, I.)

  9. Computerized reactor monitor and control for nuclear reactors

    International Nuclear Information System (INIS)

    Buerger, L.

    1982-01-01

    The analysis of a computerized process control system developed by Transelektro-KFKI-Videoton (Hangary) for a twenty-year-old research reactor in Budapest and or a new one in Tajura (Libya) is given. The paper describes the computer hardware (R-10) and the implemented software (PROCESS-24K) as well as their applications at nuclear reactors. The computer program provides for man-machine communication, data acquisition and processing, trend and alarm analysis, the control of the reactor power, reactor physical calculations and additional operational functions. The reliability and the possible further development of the computerized systems which are suitable for application at reactors of different design are also discussed. (Sz.J.)

  10. Steam generator materials performance in high temperature gas-cooled reactors

    International Nuclear Information System (INIS)

    Chafey, J.E.; Roberts, D.I.

    1980-11-01

    This paper reviews the materials technology aspects of steam generators for HTGRs which feature a graphite-moderated, uranium-thorium, all-ceramic core and utilizes high-pressure helium as the primary coolant. The steam generators are exposed to gas-side temperatures approaching 760 0 C and produce superheated steam at 538 0 C and 16.5 MPa (2400 psi). The prototype Peach Bottom I 40-MW(e) HTGR was operated for 1349 EFPD over 7 years. Examination after decommissioning of the U-tube steam generators and other components showed the steam generators to be in very satisfactory condition. The 330-MW(e) Fort St. Vrain HTGR, now in the final stages of startup, has achieved 70% power and generated more than 1.5 x 10 6 MWh of electricity. The steam generators in this reactor are once-through units of helical configuration, requiring a number of new materials factors including creep-fatigue and water chemistry control. Current designs of larger HTGRs also feature steam generators of helical once-through design. Materials issues that are important in these designs include detailed consideration of time-dependent behavior of both base metals and welds, as required by current American Society of Mechanical Engineers (ASME) Code rules, evaluation of bimetallic weld behavior, evaluation of the properties of large forgings, etc

  11. Safeguarding research reactors

    International Nuclear Information System (INIS)

    Powers, J.A.

    1983-03-01

    The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

  12. Control of reactor coolant flow path during reactor decay heat removal

    Science.gov (United States)

    Hunsbedt, Anstein N.

    1988-01-01

    An improved reactor vessel auxiliary cooling system for a sodium cooled nuclear reactor is disclosed. The sodium cooled nuclear reactor is of the type having a reactor vessel liner separating the reactor hot pool on the upstream side of an intermediate heat exchanger and the reactor cold pool on the downstream side of the intermediate heat exchanger. The improvement includes a flow path across the reactor vessel liner flow gap which dissipates core heat across the reactor vessel and containment vessel responsive to a casualty including the loss of normal heat removal paths and associated shutdown of the main coolant liquid sodium pumps. In normal operation, the reactor vessel cold pool is inlet to the suction side of coolant liquid sodium pumps, these pumps being of the electromagnetic variety. The pumps discharge through the core into the reactor hot pool and then through an intermediate heat exchanger where the heat generated in the reactor core is discharged. Upon outlet from the heat exchanger, the sodium is returned to the reactor cold pool. The improvement includes placing a jet pump across the reactor vessel liner flow gap, pumping a small flow of liquid sodium from the lower pressure cold pool into the hot pool. The jet pump has a small high pressure driving stream diverted from the high pressure side of the reactor pumps. During normal operation, the jet pumps supplement the normal reactor pressure differential from the lower pressure cold pool to the hot pool. Upon the occurrence of a casualty involving loss of coolant pump pressure, and immediate cooling circuit is established by the back flow of sodium through the jet pumps from the reactor vessel hot pool to the reactor vessel cold pool. The cooling circuit includes flow into the reactor vessel liner flow gap immediate the reactor vessel wall and containment vessel where optimum and immediate discharge of residual reactor heat occurs.

  13. Biological Assessment of the Effects of Military Associated Activities on Endangered Species at Fort Hood, Texas

    Science.gov (United States)

    1992-12-01

    monographing the genus Croton. Dr. Joe Allen Farmer published a dissertation on the species in 1962. Studies on the Fort Hood population have begun under...Woodhouse, S.W., "Descriptions of New Species of the Genus Vireo, VieilL, and Zonorrichia, Swains," Proceeding of the Academy of Natural Sciences of...sinuata Skunkbush Saumac Rhus aroma tica Texas Oak Quercus texazza Texas Persimmon, Diospyros texana Texas Ashe Fraxinus texensis Virginia Creeper Paz

  14. Methodology for the evaluation of a 4000-home geothermal heat pump retrofit at Fort Polk, Louisiana

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, P.J.; Shonder, J.A.; White, D.L.; Huang, H.L.

    1998-03-01

    The US Army and a private energy service company are developing a comprehensive energy efficiency project to upgrade the family housing at Fort Polk, Louisiana. The project includes converting the space conditioning systems of more than 4,000 housing units to geothermal (or ground-source) heat pumps (GHPs). This interim report describes the methodology of the evaluation associated with this project, including the field monitoring that has been conducted at the base.

  15. The development of Shevchenko’s studies in the PRC in the 20th – at the beginning of the 21st century

    Directory of Open Access Journals (Sweden)

    Diachenko, O. V.

    2015-07-01

    Full Text Available The article discusses the development of Shevchenko’s Studies in China from the early twentieth century to the present day. The author established that the first publication of Ukrainian poet’s poems in China were done in the 1920s. Originally poems by Taras Shevchenko were published in Ukrainian editions of our emigration in Harbin and Shanghai. Publications by Kobzar’s poems in Chinese began in the late 1920s – early 1930s. First article about Ukrainian writer and his poem «Oh, three wide ways» was published by a Chinese writer and literary critic Zhou Tszozhen. Overall, this article is devoted to works in the field of Shevchenko’s Studies by Chinese literary critics, including Lu Xun, Xiao Sanya Chen Yuan, Sun Wei, Meng Hai, Zhang Tesyan and others. The most prominent Chinese expert in Shevchenko’s Studies today is a connoisseur of Slavic literature, translator, literary critic Professor Ge Baotsyuan, who first translated the poems by Shevchenko from to Ukrainian Chinese (his precursors carried translations of Kobzar’s poems mainly from Russian, German and English. It is also found that studying of life and works of Taras Shevchenko in China is included into many university courses in foreign literature, «Testament» is studied in Chinese schools. In 2008 the monument to Kobzar was opened. A collection of Kobzar’s poems in Chinese which contains 139 texts was published in 2016.

  16. Land-Use Analysis and Simulated Effects of Land-Use Change and Aggregate Mining on Groundwater Flow in the South Platte River Valley, Brighton to Fort Lupton, Colorado

    Science.gov (United States)

    Arnold, L.R.; Mladinich, C.S.; Langer, W.H.; Daniels, J.S.

    2010-01-01

    Land use in the South Platte River valley between the cities of Brighton and Fort Lupton, Colo., is undergoing change as urban areas expand, and the extent of aggregate mining in the Brighton-Fort Lupton area is increasing as the demand for aggregate grows in response to urban development. To improve understanding of land-use change and the potential effects of land-use change and aggregate mining on groundwater flow, the U.S. Geological Survey, in cooperation with the cities of Brighton and Fort Lupton, analyzed socioeconomic and land-use trends and constructed a numerical groundwater flow model of the South Platte alluvial aquifer in the Brighton-Fort Lupton area. The numerical groundwater flow model was used to simulate (1) steady-state hydrologic effects of predicted land-use conditions in 2020 and 2040, (2) transient cumulative hydrologic effects of the potential extent of reclaimed aggregate pits in 2020 and 2040, (3) transient hydrologic effects of actively dewatered aggregate pits, and (4) effects of different hypothetical pit spacings and configurations on groundwater levels. The SLEUTH (Slope, Land cover, Exclusion, Urbanization, Transportation, and Hillshade) urban-growth modeling program was used to predict the extent of urban area in 2020 and 2040. Wetlands in the Brighton-Fort Lupton area were mapped as part of the study, and mapped wetland locations and areas of riparian herbaceous vegetation previously mapped by the Colorado Division of Wildlife were compared to simulation results to indicate areas where wetlands or riparian herbaceous vegetation might be affected by groundwater-level changes resulting from land-use change or aggregate mining. Analysis of land-use conditions in 1957, 1977, and 2000 indicated that the general distribution of irrigated land and non-irrigated land remained similar from 1957 to 2000, but both land uses decreased as urban area increased. Urban area increased about 165 percent from 1957 to 1977 and about 56 percent from

  17. Reactor operations Brookhaven medical research reactor, Brookhaven high flux beam reactor informal monthly report

    International Nuclear Information System (INIS)

    Hauptman, H.M.; Petro, J.N.; Jacobi, O.

    1995-04-01

    This document is the April 1995 summary report on reactor operations at the Brookhaven Medical Research Reactor and the Brookhaven High Flux Beam Reactor. Ongoing experiments/irradiations in each are listed, and other significant operations functions are also noted. The HFBR surveillance testing schedule is also listed

  18. El Paso County Geothermal Project at Fort Bliss. Final Project Report

    Energy Technology Data Exchange (ETDEWEB)

    Lear, Jon [Ruby Mountain Inc., Salt Lake City, UT (United State); Bennett, Carlon [Ruby Mountain Inc., Salt Lake City, UT (United State); Lear, Dan [Ruby Mountain Inc., Salt Lake City, UT (United State); Jones, Phil L. [Ruby Mountain Inc., Salt Lake City, UT (United State); Burdge, Mark [Evergreen Clean Energy Management, Provo, UT (United States); Barker, Ben [Evergreen Clean Energy Management, Provo, UT (United States); Segall, Marylin [Univ. of Utah, Salt Lake City, UT (United States). Energy and Geoscience Inst.; Moore, Joseph [Univ. of Utah, Salt Lake City, UT (United States). Energy and Geoscience Inst.; Nash, Gregory [Univ. of Utah, Salt Lake City, UT (United States). Energy and Geoscience Inst.; Jones, Clay [Univ. of Utah, Salt Lake City, UT (United States). Energy and Geoscience Inst.; Simmons, Stuart [Univ. of Utah, Salt Lake City, UT (United States). Energy and Geoscience Inst.; Taylor, Nancy [Univ. of Utah, Salt Lake City, UT (United States). Energy and Geoscience Inst.

    2016-02-01

    The El Paso County Geothermal Project at Fort Bliss was an effort to determine the scale and scope of geothermal resources previously identified on Fort Bliss’ McGregor Range in southern Otero County, New Mexico. The project was funded with a $5,000,000 grant to El Paso County from the U.S. Department of Energy (DOE) as part of the American Recovery and Reinvestment Act of 2009 and a $4,812,500 match provided by private sector partners. The project was administered through the DOE Golden Field Office to awardee El Paso County. The primary subcontractor to El Paso County and project Principal Investigator - Ruby Mountain Inc. (RMI) of Salt Lake City, Utah - assembled the project team consisting of Evergreen Clean Energy Management (ECEM) of Provo, Utah, and the Energy & Geoscience Institute at the University of Utah (EGI) in Salt Lake City, UT to complete the final phases of the project. The project formally began in May of 2010 and consisted of two preliminary phases of data collection and evaluation which culminated in the identification of a drilling site for a Resource Confirmation Well on McGregor Range. Well RMI 56-5 was drilled May and June 2013 to a depth of 3,030 ft. below ground level. A string of slotted 7 inch casing was set in 8.75 inch hole on bottom fill at 3,017 ft. to complete the well. The well was drilled using a technique called flooded reverse circulation, which is most common in mineral exploration. This technique produced an exceptionally large and complete cuttings record. An exciting development at the conclusion of drilling was the suspected discovery of a formation that has proven to be of exceptionally high permeability in three desalinization wells six miles to the south. Following drilling and preliminary testing and analysis, the project team has determined that the McGregor Range thermal anomaly is large and can probably support development in the tens of megawatts.

  19. Reactor core for FBR type reactor

    International Nuclear Information System (INIS)

    Fujita, Tomoko; Watanabe, Hisao; Kasai, Shigeo; Yokoyama, Tsugio; Matsumoto, Hiroshi.

    1996-01-01

    In a gas-sealed assembly for a FBR type reactor, two or more kinds of assemblies having different eigen frequency and a structure for suppressing oscillation of liquid surface are disposed in a reactor core. Coolant introduction channels for introducing coolants from inside and outside are disposed in the inside of structural members of an upper shielding member to form a shielding member-cooling structure in the reactor core. A structure for promoting heat conduction between a sealed gas in the assembly and coolants at the inner side or the outside of the assembly is disposed in the reactor core. A material which generates heat by neutron irradiation is disposed in the assembly to heat the sealed gases positively by radiation heat from the heat generation member also upon occurrence of power elevation-type event to cause temperature expansion. Namely, the coolants flown out from or into the gas sealed-assemblies cause differential fluctuation on the liquid surface, and the change of the capacity of a gas region is also different on every gas-sealed assemblies thereby enabling to suppress fluctuation of the reactor power. Pressure loss is increased by a baffle plate or the like to lower the liquid surface of the sodium coolants or decrease the elevating speed thereof thereby suppressing fluctuation of the reactor power. (N.H.)

  20. Space-time reactor kinetics for heterogeneous reactor structure

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1969-11-15

    An attempt is made to formulate time dependent diffusion equation based on Feinberg-Galanin theory in the from analogue to the classical reactor kinetic equation. Parameters of these equations could be calculated using the existing codes for static reactor calculation based on the heterogeneous reactor theory. The obtained kinetic equation could be analogues in form to the nodal kinetic equation. Space-time distribution of neutron flux in the reactor can be obtained by solving these equations using standard methods.

  1. Nuclear Reactor RA Safety Report, Vol. 4, Reactor

    International Nuclear Information System (INIS)

    1986-11-01

    RA research reactor is thermal heavy water moderated and cooled reactor. Metal uranium 2% enriched fuel elements were used at the beginning of its operation. Since 1976, 80% enriched uranium oxide dispersed in aluminium fuel elements were gradually introduced into the core and are the only ones presently used. Reactor core is cylindrical, having diameter 40 cm and 123 cm high. Reaktor core is made up of 82 fuel elements in aluminium channels, lattice is square, lattice pitch 13 cm. Reactor vessel is cylindrical made of 8 mm thick aluminium, inside diameter 140 cm and 5.5 m high surrounded with neutron reflector and biological shield. There is no containment, the reactor building is playing the shielding role. Three pumps enable circulation of heavy water in the primary cooling circuit. Degradation of heavy water is prevented by helium cover gas. Control rods with cadmium regulate the reactor operation. There are eleven absorption rods, seven are used for long term reactivity compensation, two for automatic power regulation and two for safety shutdown. Total anti reactivity of the rods amounts to 24%. RA reactor is equipped with a number of experimental channels, 45 vertical (9 in the core), 34 in the graphite reflector and two in the water biological shield; and six horizontal channels regularly distributed in the core. This volume include detailed description of systems and components of the RA reactor, reactor core parameters, thermal hydraulics of the core, fuel elements, fuel elements handling equipment, fuel management, and experimental devices [sr

  2. Feasible reactor power cutback logic development for an integral reactor

    International Nuclear Information System (INIS)

    Han, Soon-Kyoo; Lee, Chung-Chan; Choi, Suhn; Kang, Han-Ok

    2013-01-01

    Major features of integral reactors that have been developed around the world recently are simplified operating systems and passive safety systems. Even though highly simplified control system and very reliable components are utilized in the integral reactor, the possibility of major component malfunction cannot be ruled out. So, feasible reactor power cutback logic is required to cope with the malfunction of components without inducing reactor trip. Simplified reactor power cutback logic has been developed on the basis of the real component data and operational parameters of plant in this study. Due to the relatively high rod worth of the integral reactor the control rod assembly drop method which had been adapted for large nuclear power plants was not desirable for reactor power cutback of the integral reactor. Instead another method, the control rod assembly control logic of reactor regulating system controls the control rod assembly movements, was chosen as an alternative. Sensitivity analyses and feasibility evaluations were performed for the selected method by varying the control rod assembly driving speed. In the results, sensitivity study showed that the performance goal of reactor power cutback system could be achieved with the limited range of control rod assembly driving speed. (orig.)

  3. Final Report; Arsenic Fate, Transport and Stability Study; Groundwater, Surface Water, Soil And Sediment Investigation, Fort Devens Superfund Site, Devens, Massachusetts

    Science.gov (United States)

    This document presents results from the Fiscal Years 2006-2008 field investigation at the Fort Devens Superfund Site, Operable Unit 1 (Shepley's Hill Landfill) to fulfill the research objectives outlined in the proposal entitled, 'Fate and Transport of Arsenic in an Urban, Milita...

  4. RA Reactor

    International Nuclear Information System (INIS)

    1978-02-01

    In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation [sr

  5. Fate of TCE in heated Fort Lewis soil.

    Science.gov (United States)

    Costanza, Jed; Fletcher, Kelly E; Löffler, Frank E; Pennell, Kurt D

    2009-02-01

    This study explores the transformation of trichloroethene (TCE) caused by heating contaminated soil and groundwater samples obtained from the East Gate Disposal Yard (EGDY) located in Fort Lewis, WA. After field samples transferring into glass ampules and introducing 1.5 micromol of TCE, the sealed ampules were incubated at temperatures of 25, 50, and 95 degrees C for periods of up to 95.5 days. Although TCE was completely transformed into cis-1,2-dichloroethene (cis-DCE) after 42 days at 25 degrees C by microbial activity, this transformation was not observed at 50 or 95 degrees C. Chloride levels increased after 42 days at 25 degrees C corresponding to the mass of TCE transformed to cis-DCE, were constant at 50 degrees C, and increased at 95 degrees C yielding a TCE degradation half-life of 1.6-1.9 years. These findings indicate that indigenous microbes contribute to the partial dechlorination of TCE to cis-DCE at temperatures of less than 50 degrees C, whereas interphase mass transfer and physical recovery of TCE will predominate over in situ degradation processes at temperatures of greater than 50 degrees C during thermal treatment at the EGDY site.

  6. Permafrost delineation for remediation planning : Fort Wainwright, Alaska

    Energy Technology Data Exchange (ETDEWEB)

    Astley, B. [Cold Regions Research and Engineering Laboratory, Anchorage, AK (United States); Snyder, C. [YEC Inc., Valley Cottage, NJ (United States); Delaney, A. [Cold Regions Research and Engineering Laboratory, Fairbanks, AK (United States); Arcone, S.; Lawson, D. [Cold Regions Research and Engineering Laboratory, Hanover, NH (United States)

    2003-07-01

    In the summer of 1999, geophysical and hydrogeological surveys were conducted at the Birch Hill Tank Farm and Truck Fill Stand in Fort Wainwright, Alaska to assess the distribution of benzene, 1,2-dichloroethane, and 1,2-dibromoethane. The Birch Hill site consists of a silt, sand and gravel fluvial deposit that overlies bedrock. Permafrost occurs discontinuously throughout the alluvium and underlying bedrock, resulting in a complex aquifer distribution. The bedrock beneath the Tank Farm is highly fractured and faulted with a weathered horizon that is 30 meters thick. The goal of this study was to map the discontinuous permafrost and aquifers in the alluvial deposits and weathered bedrock zone for the purpose of delineating bedrock depth and structural features that influence ground water flow. Several methods were used to define subsurface conditions, including borehole logs, DC resistivity, and ground-penetrating radar. A 3-D hydrogeologic model was used to develop a ground water flow model used to determine contaminant migration pathways and rates. The permafrost configuration was found to be the most important boundary condition in this model. 7 refs., 1 tab., 5 figs.

  7. H Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The H Reactor was the first reactor to be built at Hanford after World War II.It became operational in October of 1949, and represented the fourth nuclear reactor on...

  8. Raising the camp living bar : a Shell Canada and Fort MacKay First Nation joint venture results in a unique housing solution

    Energy Technology Data Exchange (ETDEWEB)

    Stastny, P.

    2006-11-15

    Shell Canada and the Fort MacKay First Nation have joined forces to construct the Buena Vista Hotel, a staff accommodation project for Shell, Chevron, and Western project managers and supervisors. The hotel will provide a higher level of comfort than current housing available to employees in the Athabasca region, and it is hoped that the project will help to attract more employees. Under the arrangement, Shell and its partners will have exclusive access to the hotel for the first 10 years, and there is a commitment from Fort MacKay First Nation to purchase the hotel outright within a certain period. To oversee the hotel's construction, the First Nations band formed a construction company and partnered with the Milk Creek Group. The hotel is currently being constructed in Saskatchewan and will be trucked to Fort MacKay in 279 modules. The 12 by 28 foot units are fully appointed with carpets, millwork, painted walls and granite countertops. After being trucked to Alberta, the modules will be assembled and stacked along central hallways built on-site. A Vancouver-based architect designed the overall concept for the hotel, and aimed to blend the project into its environment wherever possible by leaving buffers of trees. Many of the rooms will have beautiful views of the river. It was concluded that Aboriginal involvement has been a crucial factor in the hotel's development. 1 fig.

  9. Reactor container

    International Nuclear Information System (INIS)

    Naruse, Yoshihiro.

    1990-01-01

    The thickness of steel shell plates in a reactor container embedded in sand cussions is monitored to recognize the corrosion of the steel shell plates. That is, the reactor pressure vessel is contained in a reactor container shell and the sand cussions are disposed on the lower outside of the reactor container shell to elastically support the shell. A pit is disposed at a position opposing to the sand cussions for measuring the thickness of the reactor container shell plates. The pit is usually closed by a closing member. In the reactor container thus constituted, the closing member can be removed upon periodical inspection to measure the thickness of the shell plates. Accordingly, the corrosion of the steel shell plates can be recognized by the change of the plate thickness. (I.S.)

  10. Hybrid reactors

    International Nuclear Information System (INIS)

    Moir, R.W.

    1980-01-01

    The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of 233 U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m -2 , and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid

  11. Nuclear research reactors

    International Nuclear Information System (INIS)

    1985-01-01

    It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.) [pt

  12. Strategic planning for research reactors. Guidance for reactor managers

    International Nuclear Information System (INIS)

    2001-04-01

    The purpose of this publication is to provide guidance on how to develop a strategic plan for a research reactor. The IAEA is convinced of the need for research reactors to have strategic plans and is issuing a series of publications to help owners and operators in this regard. One of these covers the applications of research reactors. That report brings together all of the current uses of research reactors and enables a reactor owner or operator to evaluate which applications might be possible with a particular facility. An analysis of research reactor capabilities is an early phase in the strategic planning process. The current document provides the rationale for a strategic plan, outlines the methodology of developing such a plan and then gives a model that may be followed. While there are many purposes for research reactor strategic plans, this report emphasizes the use of strategic planning in order to increase utilization. A number of examples are given in order to clearly illustrate this function

  13. Federal land management, carbon sequestration, and climate change in the Southeastern U.S.: a case study with fort benning

    Science.gov (United States)

    Zhao, S.; Liu, S.; Li, Z.; Sohl, Terry L.

    2010-01-01

    Land use activities can have a major impact on the temporal trendsandspatialpatternsofregionalland-atmosphereexchange of carbon. Federal lands generally have substantially different land management strategies from surrounding areas, and the carbon consequences have rarely been quantified and assessed. Using the Fort Benning Installation as a case study, we used the General Ensemble biogeochemical Modeling System (GEMS) to simulate and compare ecosystem carbon sequestration between the U.S. Army's Fort Benning and surrounding areas from 1992 to 2050. Our results indicate that the military installation sequestered more carbon than surrounding areas from 1992 to 2007 (76.7 vs 18.5 g C m-2 yr-1), and is projected to continue sequestering more carbon from 2008 to 2050 (75.7 vs 25.6 g C m-2 yr-1), mostly because of the proactive management approaches adopted on military training lands. Our results suggest that federal lands might play a positive and important role in sequestering and conserving atmospheric carbon because some anthropogenic disturbances (e.g., urbanization, forest harvesting, and agriculture) can be minimized or prevented on federal lands

  14. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    1991-04-01

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

  15. Research reactors - an overview

    International Nuclear Information System (INIS)

    West, C.D.

    1997-01-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs

  16. Multiregion reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The study of reflected reactors can be done employing the multigroup diffusion method. The neutron conservation equations, inside the intervals, can be written by fluxes and group constants. A reflected reactor (one and two groups) for a slab geometry is studied, aplying the continuity of flux and current in the interface. At the end, the appropriated solutions for a infinite cylindrical reactor and for a spherical reactor are presented. (Author) [pt

  17. Gravity survey and interpretation of Fort Irwin and vicinity, Mojave Desert, California: Chapter H in Geology and geophysics applied to groundwater hydrology at Fort Irwin, California

    Science.gov (United States)

    Jachens, Robert C.; Langenheim, V.E.; Buesch, David C.

    2014-01-01

    In support of a hydrogeologic study of the groundwater resources on Fort Irwin, we have combined new gravity data with preexisting measurements to produce an isostatic residual gravity map, which we then separated into two components reflecting (1) the density distribution in the pre-Cenozoic basement complex and (2) the distribution of low-density Cenozoic volcanic and sedimentary deposits that lie on top of the basement complex. The second component was inverted to estimate the three-dimensional distribution of Cenozoic deposits by using constraints from geology, drillholes, and time-domain electromagnetic soundings. In most of the base, the Cenozoic deposits are no more than 300 m thick, except in the basins with more than 500 m of fill beneath Coyote Lake, Red Pass Lake, west of Nelson Lake, west of Superior Lake, Bicycle Lake, and in the vicinity of Nelson Lake.

  18. Discrimination Using the Geonics EM63 in a Cued Interrogation Mode at Fort McClellan, AL

    Science.gov (United States)

    2009-03-01

    vectors of the nine items measured at the Ashland test plot: (a) Pasion - Oldenburg k1 versus k2; (b) Ratio of the primary polarization tensor at the 10th...discrimination potential of the Geonics EM63 at Fort McClellan, Alabama (AL) when deployed in a cued interrogation mode. Pasion - Oldenburg polarization...scrap metal, shrapnel and geology (e.g. Hart et al., 2001; Collins et al., 2001; Pasion & Oldenburg, 2001; Zhang et al., 2003a, 2003b; Billings

  19. Reactor building

    International Nuclear Information System (INIS)

    Maruyama, Toru; Murata, Ritsuko.

    1996-01-01

    In the present invention, a spent fuel storage pool of a BWR type reactor is formed at an upper portion and enlarged in the size to effectively utilize the space of the building. Namely, a reactor chamber enhouses reactor facilities including a reactor pressure vessel and a reactor container, and further, a spent fuel storage pool is formed thereabove. A second spent fuel storage pool is formed above the auxiliary reactor chamber at the periphery of the reactor chamber. The spent fuel storage pool and the second spent fuel storage pool are disposed in adjacent with each other. A wall between both of them is formed vertically movable. With such a constitution, the storage amount for spent fuels is increased thereby enabling to store the entire spent fuels generated during operation period of the plant. Further, since requirement of the storage for the spent fuels is increased stepwisely during periodical exchange operation, it can be used for other usage during the period when the enlarged portion is not used. (I.S.)

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    Garabedian, G.

    1988-01-01

    A liquid reactor is described comprising: (a) a reactor vessel having a core; (b) one or more satellite tanks; (c) pump means in the satellite tank; (d) heat exchanger means in the satellite tank; (e) an upper liquid metal conduit extending between the reactor vessel and the satellite tank; (f) a lower liquid metal duct extending between the reactor vessel and satellite tanks the upper liquid metal conduit and the lower liquid metal duct being arranged to permit free circulation of liquid metal between the reactor vessel core and the satellite tank by convective flow of liquid metal; (g) a separate sealed common containment vessel around the reactor vessel, conduits and satellite tanks; (h) the satellite tank having space for a volume of liquid metal that is sufficient to dampen temperature transients resulting from abnormal operating conditions

  1. HTGR safety research concerns at NRC

    International Nuclear Information System (INIS)

    Minogue, R.B.

    1982-01-01

    A general discussion of HTGR technical and safety-related problems is given. The broad areas of current research programs specific to the Fort St. Vrain reactor and applicable to HTGR technology are summarized

  2. Reactor physics challenges in GEN-IV reactor design

    Energy Technology Data Exchange (ETDEWEB)

    Driscoll, Michael K.; Hejzlar, Pavel [Massachusetts Institute of Technology, MA (United States)

    2005-02-15

    An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources.

  3. Reactor physics challenges in GEN-IV reactor design

    International Nuclear Information System (INIS)

    Driscoll, Michael K.; Hejzlar, Pavel

    2005-01-01

    An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources

  4. Reactor Vessel Surveillance Program for Advanced Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyeong-Hoon; Kim, Tae-Wan; Lee, Gyu-Mahn; Kim, Jong-Wook; Park, Keun-Bae; Kim, Keung-Koo

    2008-10-15

    This report provides the design requirements of an integral type reactor vessel surveillance program for an integral type reactor in accordance with the requirements of Korean MEST (Ministry of Education, Science and Technology Development) Notice 2008-18. This report covers the requirements for the design of surveillance capsule assemblies including their test specimens, test block materials, handling tools, and monitors of the surveillance capsule neutron fluence and temperature. In addition, this report provides design requirements for the program for irradiation surveillance of reactor vessel materials, a layout of specimens and monitors in the surveillance capsule, procedures of installation and retrieval of the surveillance capsule assemblies, and the layout of the surveillance capsule assemblies in the reactor.

  5. Career Advancement and Work Support Services on the Job: Implementing the Fort Worth Work Advancement and Support Center Program

    Science.gov (United States)

    Schultz, Caroline; Seith, David

    2011-01-01

    The Work Advancement and Support Center (WASC) program in Fort Worth was part of a demonstration that is testing innovative strategies to help increase the income of low-wage workers, who make up a large segment of the U.S. workforce. The program offered services to help workers stabilize their employment, improve their skills, and increase their…

  6. Sinus lifting before Le Fort I maxillary osteotomy: a suitable method for oral rehabilitation of edentulous patients with skelettal class-III conditions: review of the literature and report of a case

    Directory of Open Access Journals (Sweden)

    Meyer Ulrich

    2007-01-01

    Full Text Available Abstract Background Functional rehabilitation of patients afflicted with severe mandibular and maxillary alveolar atrophy might be challenging especially in malformed patients. Methods Treatment planning using sinus lifting and implant placement before Le Fort I maxillary osteotomy in a patient with severe mandibular and posterior maxillary alveolar atrophy and skelettal class-III conditions due to cleft palate are described. Results A full functional and esthetic rehabilitation of the patient was achieved by a stepwise surgical approach performed through sinus lifting as the primary approach followed by implant placement and subsequent Le Fort I maxillary osteotomy to correct the maxillo-mandibular relation. Conclusion Stabilisation of the maxillary complex by a sinus lifting procedure in combination with computer aided implant placement as preorthodontic planning procedure before Le Fort I maxillary osteotomy seems to be suitable in order to allow ideal oral rehabilitation especially in malformed patients.

  7. The nuclear reactor strategy between fast breeder reactors and advanced pressurized water reactors

    International Nuclear Information System (INIS)

    Seifritz, W.

    1983-01-01

    A nuclear reactor strategy between fast breeder reactors (FBRs) and advanced pressurized water reactors (APWRs) is being studied. The principal idea of this strategy is that the discharged plutonium from light water reactors (LWRs) provides the inventories of the FBRs and the high-converter APWRs, whereby the LWRs are installed according to the derivative of a logistical S curve. Special emphasis is given to the dynamics of reaching an asymptotic symbiosis between FBRs and APWRs. The main conclusion is that if a symbiotic APWR-FBR family with an asymptotic total power level in the terawatt range is to exist in about half a century from now, we need a large number of FBRs already in an early phase

  8. Simultaneous measurements of helium and heavy nuclei fluxes in cosmic rays over Fort Churchill

    International Nuclear Information System (INIS)

    Bhatia, V.S.; Paruthi, S.; Kainth, G.S.

    1977-01-01

    We have made simultaneous measurements of fluxes of He an heavy nuclei (Z< or =10) in primary cosmic rays at three levels of solar activity. These nuclei have been studied in three nuclear emulsion stacks exposed over Fort Churchill, Canada, in 1963, 1964, and 1967. We had earlier reported our results on the heavy nuclei at the Hobart conference (Bhatia et al., 1971). Experimental results based on 1514 He nuclei tracks that were measured in these three stacks are presented in this paper. The experimentally obtained He and heavy nuclei differential energy spectra have been compared with the theoretically calculated near-earth spectra

  9. Increased SRP reactor power

    International Nuclear Information System (INIS)

    MacAfee, I.M.

    1983-01-01

    Major changes in the current reactor hydraulic systems could be made to achieve a total of about 1500 MW increase of reactor power for P, K, and C reactors. The changes would be to install new, larger heat exchangers in the reactor buildings to increase heat transfer area about 24%, to increase H 2 O flow about 30% per reactor, to increase D 2 O flow 15 to 18% per reactor, and increase reactor blanket gas pressure from 5 psig to 10 psig. The increased reactor power is possible because of reduced inlet temperature of reactor coolant, increased heat removal capacity, and increased operating pressure (larger margin from boiling). The 23% reactor power increase, after adjustment for increased off-line time for reactor reloading, will provide a 15% increase of production from P, K, and C reactors. Restart of L Reactor would increase SRP production 33%

  10. Tokamak reactor studies

    International Nuclear Information System (INIS)

    Baker, C.C.

    1981-01-01

    This paper presents an overview of tokamak reactor studies with particular attention to commercial reactor concepts developed within the last three years. Emphasis is placed on DT fueled reactors for electricity production. A brief history of tokamak reactor studies is presented. The STARFIRE, NUWMAK, and HFCTR studies are highlighted. Recent developments that have increased the commercial attractiveness of tokamak reactor designs are discussed. These developments include smaller plant sizes, higher first wall loadings, improved maintenance concepts, steady-state operation, non-divertor particle control, and improved reactor safety features

  11. Computerized reactor monitor and control for research reactors

    International Nuclear Information System (INIS)

    Buerger, L.; Vegh, E.

    1981-09-01

    The computerized process control system developed in the Central Research Institute for Physics, Budapest, Hungary, is described together with its special applications at research reactors. The nuclear power of the Hungarian research reactor is controlled by this computerized system, too, while in Lybia many interesting reactor-hpysical calculations are built into the computerized monitor system. (author)

  12. Calculation of low-energy reactor neutrino spectra reactor for reactor neutrino experiments

    Energy Technology Data Exchange (ETDEWEB)

    Riyana, Eka Sapta; Suda, Shoya; Ishibashi, Kenji; Matsuura, Hideaki [Dept. of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Kyushu (Japan); Katakura, Junichi [Dept. of Nuclear System Safety Engineering, Nagaoka University of Technology, Nagaoka (Japan)

    2016-06-15

    Nuclear reactors produce a great number of antielectron neutrinos mainly from beta-decay chains of fission products. Such neutrinos have energies mostly in MeV range. We are interested in neutrinos in a region of keV, since they may take part in special weak interactions. We calculate reactor antineutrino spectra especially in the low energy region. In this work we present neutrino spectrum from a typical pressurized water reactor (PWR) reactor core. To calculate neutrino spectra, we need information about all generated nuclides that emit neutrinos. They are mainly fission fragments, reaction products and trans-uranium nuclides that undergo negative beta decay. Information in relation to trans-uranium nuclide compositions and its evolution in time (burn-up process) were provided by a reactor code MVP-BURN. We used typical PWR parameter input for MVP-BURN code and assumed the reactor to be operated continuously for 1 year (12 months) in a steady thermal power (3.4 GWth). The PWR has three fuel compositions of 2.0, 3.5 and 4.1 wt% {sup 235}U contents. For preliminary calculation we adopted a standard burn-up chain model provided by MVP-BURN. The chain model treated 21 heavy nuclides and 50 fission products. The MVB-BURN code utilized JENDL 3.3 as nuclear data library. We confirm that the antielectron neutrino flux in the low energy region increases with burn-up of nuclear fuel. The antielectron-neutrino spectrum in low energy region is influenced by beta emitter nuclides with low Q value in beta decay (e.g. {sup 241}Pu) which is influenced by burp-up level: Low energy antielectron-neutrino spectra or emission rates increase when beta emitters with low Q value in beta decay accumulate. Our result shows the flux of low energy reactor neutrinos increases with burn-up of nuclear fuel.

  13. Nuclear Reactor Physics

    Science.gov (United States)

    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.

  14. Reactor. Mind picture of the future Jules-Horowitz Reactor (RHJ)

    International Nuclear Information System (INIS)

    Eustache, S.

    1999-01-01

    This paper gives information about the future research reactor, named Reactor Jules-Horowitz (RJH). This irradiation reactor will be placed at industrialists disposal, for research concerning the competitiveness and the safety french electro-nuclear park. Principles and innovations are detailed. This reactor will respect the ALARA principle (as low as reasonably achievable). (A.L.B.)

  15. An Archaeological Curation-Needs Assessment for Fort Irwin, Naval Air Station, North Island, Edwards Air Force Base, Marine Corps Air-Ground Combat Center, Twentynine Palms

    National Research Council Canada - National Science Library

    Trimble, Michael

    1997-01-01

    .... Louis District, conducted an investigation of all archaeological materials and associated records in the care of NAS North Island, Edwards Air Force Base, Fort Irwin, and MCAGCC Twentynine Palms...

  16. The analysis for inventory of experimental reactor high temperature gas reactor type

    International Nuclear Information System (INIS)

    Sri Kuntjoro; Pande Made Udiyani

    2016-01-01

    Relating to the plan of the National Nuclear Energy Agency (BATAN) to operate an experimental reactor of High Temperature Gas Reactors type (RGTT), it is necessary to reactor safety analysis, especially with regard to environmental issues. Analysis of the distribution of radionuclides from the reactor into the environment in normal or abnormal operating conditions starting with the estimated reactor inventory based on the type, power, and operation of the reactor. The purpose of research is to analyze inventory terrace for Experimental Power Reactor design (RDE) high temperature gas reactor type power 10 MWt, 20 MWt and 30 MWt. Analyses were performed using ORIGEN2 computer code with high temperatures cross-section library. Calculation begins with making modifications to some parameter of cross-section library based on the core average temperature of 570 °C and continued with calculations of reactor inventory due to RDE 10 MWt reactor power. The main parameters of the reactor 10 MWt RDE used in the calculation of the main parameters of the reactor similar to the HTR-10 reactor. After the reactor inventory 10 MWt RDE obtained, a comparison with the results of previous researchers. Based upon the suitability of the results, it make the design for the reactor RDE 20MWEt and 30 MWt to obtain the main parameters of the reactor in the form of the amount of fuel in the pebble bed reactor core, height and diameter of the terrace. Based on the main parameter or reactor obtained perform of calculation to get reactor inventory for RDE 20 MWT and 30 MWT with the same methods as the method of the RDE 10 MWt calculation. The results obtained are the largest inventory of reactor RDE 10 MWt, 20 MWt and 30 MWt sequentially are to Kr group are about 1,00E+15 Bq, 1,20E+16 Bq, 1,70E+16 Bq, for group I are 6,50E+16 Bq, 1,20E+17 Bq, 1,60E+17 Bq and for groups Cs are 2,20E+16 Bq, 2,40E+16 Bq, 2,60E+16 Bq. Reactor inventory will then be used to calculate the reactor source term and it

  17. FBR type reactors

    International Nuclear Information System (INIS)

    Suzuoki, Akira; Yamakawa, Masanori.

    1985-01-01

    Purpose: To enable safety and reliable after-heat removal from a reactor core. Constitution: During ordinary operation of a FBR type reactor, sodium coolants heated to a high temperature in a reactor core are exhausted therefrom, collide against the reactor core upper mechanisms to radially change the flowing direction and then enter between each of the guide vanes. In the case if a main recycling pump is failed and stopped during reactor operation and the recycling force is eliminated, the swirling stream of sodium that has been resulted by the flow guide mechanism during normal reactor operation is continuously maintained within a plenum at a high temperature. Accordingly, the sodium recycling force in the coolant flow channels within the reactor vessel can surely be maintained for a long period of time due to the centrifugal force of the sodium swirling stream. In this way, since the reactor core recycling flow rate can be secured even after the stopping of the main recycling pump, after-heat from the reactor core can safely and surely be removed. (Seki, T.)

  18. FBR type reactor

    International Nuclear Information System (INIS)

    Hayase, Tamotsu.

    1991-01-01

    The present invention concerns an FBR type reactor in which transuranium elements are eliminated by nuclear conversion. There are loaded reactor core fuels being charged with mixed oxides of plutonium and uranium, and blanket fuels mainly comprising depleted uranium. Further, liquid sodium is used as coolants. As transuranium elements, isotope elements of neptunium, americium and curium contained in wastes taken out from light water reactors or the composition thereof are used. The reactor core comprises a region with a greater mixing ratio and a region with a less mixing ratio of the transuranium elements. The mixing ratio of the transuranium elements is made greater for the fuels in the reactor core region at the boundary with the blanket of great neutron leakage. With such a constitution, since the positive reactivity value at the reactor core central portion is small in the Na void reactivity distribution in the reactor core, the positive reactivity is small upon Na boiling in the reactor core central region upon occurrence of imaginable accident, to attain reactor safety. (I.N.)

  19. Atitudes linguísticas e r-forte em Carambeí = Linguistics attitudes and strong-R in Carambeí

    Directory of Open Access Journals (Sweden)

    Letícia Fraga

    2009-04-01

    Full Text Available Considerando que o município de Carambeí é bastante complexo cultural e linguisticamente, este estudo pretende, de acordo com o método etnográfico: a fazer um levantamento das atitudes linguísticas que os ‘holandeses’ manifestam em relação às línguas holandesa e portuguesa; b analisar a variedade de português falada pelos‘holandeses’ de Carambeí no que diz respeito ao uso do r-forte; e c estabelecer que tipo de relação se dá entre atitudes linguísticas e uso de determinada variante de r-forte no português. No que diz respeito às atitudes em relação ao holandês, os Grupos 1M, 1F e2Fa manifestam atitudes positivas, ao passo que os Grupos 2M e 2Fb têm atitudes negativas, assim como os Grupos 3M e 3F. Já em relação ao português, a comunidade como um todo manifesta atitudes positivas. No que diz respeito ao uso de r-forte, os grupos 1M e 1F usam vibrante múltipla e tepe; o Grupo 2M também usa a vibrante e otepe; já o Grupo 2Fa usa somente vibrante e tepe e o Grupo 2Fb usa fricativa e vibrante. Os Grupos 3M e 3F usam somente fricativa. Enfim, pode-se dizer que determinadas atitudes contribuem para o uso de determinada variedade de r-forte.Considering that Carambeí Township is fairly complex, both culturally and linguistically, this study intends to: a survey the linguistic attitudes that the ‘Dutch’ reveal concerning the Dutch and Portuguese languages; b analyze the variety of Portuguese spoken by the ‘Dutch’ of Carambeí regarding the use of strong-R; c establish what sort of relationship takes place between linguistic attitudes and use of certain varieties of the strong-R in Portuguese. About the attitudes regarding the Dutch language, Groups 1M, 1F and 2Fa show positive attitudes, while Groups 2M, 2Fb, 3M and 3F show negative attitudes.Portuguese, on the other hand, elicits positive attitudes in the community as a whole. Regarding the use of strong-R, groups 1M and 1F use trill and tap; group 2M also

  20. Mito e representação feminina em "O Forte" de Adonias Filho

    Directory of Open Access Journals (Sweden)

    Luciano Santos Neiva

    2012-05-01

    Full Text Available Com o objetivo de analisar os aspectos que tornam as representações de gênero como atualizadoras da redefinição da construção identitária, em contraponto ao legado fonofalologocêntrico eurodescendente, a partir da constituição do mito em O Forte de Adonias Filho; este artigo parte do princípio de que natureza fragmentada do ser humano contraria a pretensa homogeneização do ser, moldada pela abstrata universalidade moderna, cuja máxima é a racionalidade. Tal racionalidade ocidental, falocêntrica, branca, ignorou a heterogeneidade e não permitiu o surgimento de outras vozes, enquanto sujeitos do conhecimento. O presente artigo parte da hipótese de que o Forte é um elemento totêmico e desencadeia as relações míticas, que estabelecem tabus e possibilita – por ser o mito uma entidade pré-lógica ocidental – uma redefinição das representações femininas, em contraponto ao legado fonofalologocêntrico eurodescendente, ao longo das narrativas. O amor incondicional de Adonias Filho à condição humana nos permitiu, neste artigo, adentrar no recôndito de seres, marcados tanto pelo espaço, quanto pelo tempo, numa dimensão mítica. Se a memória do discurso ocidental revelou, em sua formação, pela via da padronização e da racionalização, princípios como a unidade, o fechamento, a ordem, o anseio do absoluto e a racionalidade, a memória mítica transpõe o pré-dado, possibilitando o olhar multifacetado.

  1. Nuclear reactor

    International Nuclear Information System (INIS)

    Tilliette, Z.

    1975-01-01

    A description is given of a nuclear reactor and especially a high-temperature reactor in which provision is made within a pressure vessel for a main cavity containing the reactor core and a series of vertical cylindrical pods arranged in spaced relation around the main cavity and each adapted to communicate with the cavity through two collector ducts or headers for the primary fluid which flows downwards through the reactor core. Each pod contains two superposed steam-generator and circulator sets disposed in substantially symmetrical relation on each side of the hot primary-fluid header which conveys the primary fluid from the reactor cavity to the pod, the circulators of both sets being mounted respectively at the bottom and top ends of the pod

  2. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.

    1992-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

  3. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.

    1992-07-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

  4. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1992-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing

  5. Thai research reactor

    International Nuclear Information System (INIS)

    Aramrattana, M.

    1987-01-01

    The Office of Atomic Energy for Peace (OAEP) was established in 1962, as a reactor center, by the virtue of the Atomic Energy for Peace Act, under operational policy and authority of the Thai Atomic Energy for Peace Commission (TAEPC); and under administration of Ministry of Science, Technology and Energy. It owns and operates the only Thai Research Reactor (TRR-1/M1). The TRR-1/M1 is a mixed reactor system constituting of the old MTR type swimming pool, irradiation facilities and cooling system; and TRIGA Mark III core and control instrumentation. The general performance of TRR-1/M1 is summarized in Table I. The safe operation of TRR-1/M1 is regulated by Reactor Safety Committee (RSC), established under TAEPC, and Health Physics Group of OAEP. The RCS has responsibility and duty to review of and make recommendations on Reactor Standing Orders, Reactor Operation Procedures, Reactor Core Loading and Requests for Reactor Experiments. In addition,there also exist of Emergency Procedures which is administered by OAEP. The Reactor Operation Procedures constitute of reactor operating procedures, system operating procedures and reactor maintenance procedures. At the level of reactor routine operating procedures, there is a set of Specifications on Safety and Operation Limits and Code of Practice from which reactor shift supervisor and operators must follow in order to assure the safe operation of TRR-1/M1. Table II is the summary of such specifications. The OAEP is now upgrading certain major components of the TRR-1/M1 such as the cooling system, the ventilation system and monitoring equipment to ensure their adequately safe and reliable performance under normal and emergency conditions. Furthermore, the International Atomic Energy Agency has been providing assistance in areas of operation and maintenance and safety analysis. (author)

  6. Proposed Advanced Reactor Adaptation of the Standard Review Plan NUREG-0800 Chapter 4 (Reactor) for Sodium-Cooled Fast Reactors and Modular High-Temperature Gas-Cooled Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Poore, III, Willis P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Flanagan, George F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Holbrook, Mark [Idaho National Lab. (INL), Idaho Falls, ID (United States); Moe, Wayne [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sofu, Tanju [Argonne National Lab. (ANL), Argonne, IL (United States)

    2017-03-01

    This report proposes adaptation of the previous regulatory gap analysis in Chapter 4 (Reactor) of NUREG 0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition. The proposed adaptation would result in a Chapter 4 review plan applicable to certain advanced reactors. This report addresses two technologies: the sodium-cooled fast reactor (SFR) and the modular high temperature gas-cooled reactor (mHTGR). SRP Chapter 4, which addresses reactor components, was selected for adaptation because of the possible significant differences in advanced non-light water reactor (non-LWR) technologies compared with the current LWR-based description in Chapter 4. SFR and mHTGR technologies were chosen for this gap analysis because of their diverse designs and the availability of significant historical design detail.

  7. Nuclear reactor instrumentation at research reactor renewal

    International Nuclear Information System (INIS)

    Baers, B.; Pellionisz, P.

    1981-10-01

    The paper overviews the state-of-the-art of research reactor renewals. As a case study the instrumentation reconstruction of the Finnish 250 kW TRIGA reactor is described, with particular emphasis on the nuclear control instrumentation and equipment which has been developed and manufactured by the Central Research Institute for Physics, Budapest. Beside the presentation of the nuclear instrument family developed primarily for research reactor reconstructions, the quality assurance policy conducted during the manufacturing process is also discussed. (author)

  8. Reactor System Design

    International Nuclear Information System (INIS)

    Chi, S. K.; Kim, G. K.; Yeo, J. W.

    2006-08-01

    SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

  9. BWR type reactor

    International Nuclear Information System (INIS)

    Watanabe, Shoichi

    1983-01-01

    Purpose : To flatten the radial power distribution in the reactor core thereby improve the thermal performance of the reactor core by making the moderator-fuel ratio of fuel assemblies different depending on their position in the reactor core. Constitution : The volume of fuels disposed in the peripheral area of the reactor core is decreased by the increase of the volume of moderators in fuel assemblies disposed in the peripheral area of the reactor core to thereby make the moderator-fuel volume greater in the peripheral area than that in the central area. The moderator-fuel ratio adjustment is attained by making the number of water rods greater, decreasing the diameter of fuel pellets or decreasing the number of fuel pins in fuel assemblies disposed at the peripheral area of the reactor core as compared with fuel assemblies disposed at the central area of the reactor core. In this way, the infinite multiplication factors of fuels can be increased to thereby improve the reactor core performance. (Aizawa, K.)

  10. Prevention device for rapid reactor core shutdown in BWR type reactors

    International Nuclear Information System (INIS)

    Koshi, Yuji; Karatsu, Hiroyuki.

    1986-01-01

    Purpose: To surely prevent rapid shutdown of a nuclear reactor upon partial load interruption due to rapid increase in the system frequency. Constitution: If a partial load interruption greater than the sum of the turbine by-pass valve capacity and the load setting bias portion is applied in a BWR type power plant, the amount of main steams issued from the reactor is decreased, the thermal input/output balance of the reactor is lost, the reactor pressure is increased, the void is collapsed, the neutron fluxes are increased and the reactor power rises to generate rapid reactor shutdown. In view of the above, the turbine speed signal is compared with a speed setting value in a recycling flowrate control device and the recycling pump is controlled to decrease the recycling flowrate in order to compensate the increase in the neutron fluxes accompanying the reactor power up. In this way, transient changes in the reactor core pressure and the neutron fluxes are kept within a setting point for the rapid reactor shutdown operation thereby enabling to continue the plant operation. (Horiuchi, T.)

  11. Two Expeditions to Capture Fort Duquesne: A Study in Understanding the Operational Environment and Attendant Failure (1755) and Success (1758)

    Science.gov (United States)

    2013-03-27

    Empire in the Ohio Valley………………………………………………….…5 The Objective: Fort Duquesne…………………………………………………………....7 The Physical Enviroment

  12. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Sasagawa, Masaru; Masuda, Hiroyuki; Mogi, Toshihiko; Kanazawa, Nobuhiro.

    1994-01-01

    In a reactor core, a fuel inventory at an outer peripheral region is made smaller than that at a central region. Fuel assemblies comprising a small number of large-diameter fuel rods are used at the central region and fuel assemblies comprising a great number of smalldiameter fuel rods are used at the outer peripheral region. Since a burning degradation rate of the fuels at the outer peripheral region can be increased, the burning degradation rate at the infinite multiplication factor of fuels at the outer region can substantially be made identical with that of the fuels in the inner region. As a result, the power distribution in the direction of the reactor core can be flattened throughout the entire period of the burning cycle. Further, it is also possible to make the degradation rate of fuels at the outer region substantially identical with that of fuels at the inner side. A power peak formed at the outer circumferential portion of the reactor core of advanced burning can be lowered to improve the fuel integrity, and also improve the reactor safety and operation efficiency. (N.H.)

  13. High-temperature and breeder reactors - economic nuclear reactors of the future

    International Nuclear Information System (INIS)

    Djalilzadeh, A.M.

    1977-01-01

    The thesis begins with a review of the theory of nuclear fission and sections on the basic technology of nuclear reactors and the development of the first generation of gas-cooled reactors applied to electricity generation. It then deals in some detail with currently available and suggested types of high temperature reactor and with some related subsidiary issues such as the coupling of different reactor systems and various schemes for combining nuclear reactors with chemical processes (hydrogenation, hydrogen production, etc.), going on to discuss breeder reactors and their application. Further sections deal with questions of cost, comparison of nuclear with coal- and oil-fired stations, system analysis of reactor systems and the effect of nuclear generation on electricity supply. (C.J.O.G.)

  14. Heterogeneous reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The microscopic study of a cell is meant for the determination of the infinite multiplication factor of the cell, which is given by the four factor formula: K(infinite) = n(epsilon)pf. The analysis of an homogeneous reactor is similar to that of an heterogeneous reactor, but each factor of the four factor formula can not be calculated by the formulas developed in the case of an homogeneous reactor. A great number of methods was developed for the calculation of heterogeneous reactors and some of them are discussed. (Author) [pt

  15. Nuclear reactor neutron shielding

    Science.gov (United States)

    Speaker, Daniel P; Neeley, Gary W; Inman, James B

    2017-09-12

    A nuclear reactor includes a reactor pressure vessel and a nuclear reactor core comprising fissile material disposed in a lower portion of the reactor pressure vessel. The lower portion of the reactor pressure vessel is disposed in a reactor cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear reactor core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the reactor pressure vessel and the wall of the reactor cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactor cavity, and an inner neutron stop ring attached to the reactor pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.

  16. Fast breeder reactors

    International Nuclear Information System (INIS)

    Heinzel, V.

    1975-01-01

    The author gives a survey of 'fast breeder reactors'. In detail the process of breeding, the reasons for the development of fast breeders, the possible breeder reactors, the design criteria, fuels, cladding, coolant, and safety aspects are reported on. Design data of some experimental reactors already in operation are summarized in stabular form. 300 MWe Prototype-Reactors SNR-300 and PFR are explained in detail and data of KWU helium-cooled fast breeder reactors are given. (HR) [de

  17. Reactor container

    International Nuclear Information System (INIS)

    Shibata, Satoru; Kawashima, Hiroaki

    1984-01-01

    Purpose: To optimize the temperature distribution of the reactor container so as to moderate the thermal stress distribution on the reactor wall of LMFBR type reactor. Constitution: A good heat conductor (made of Al or Cu) is appended on the outer side of the reactor container wall from below the liquid level to the lower face of a deck plate. Further, heat insulators are disposed to the outside of the good heat conductor. Furthermore, a gas-cooling duct is circumferentially disposed at the contact portion between the good heat conductor and the deck plate around the reactor container. This enables to flow the cold heat from the liquid metal rapidly through the good heat conductor to the cooling duct and allows to maintain the temperature distribution on the reactor wall substantially linear even with the abrupt temperature change in the liquid metal. Further, by appending the good heat conductor covered with inactive metals not only on the outer side but also on the inside of the reactor wall to introduce the heat near the liquid level to the upper portion and escape the same to the cooling layer below the roof slab, the effect can be improved further. (Ikeda, J.)

  18. Reactor technology: power conversion systems and reactor operation and maintenance

    International Nuclear Information System (INIS)

    Powell, J.R.

    1977-01-01

    The use of advanced fuels permits the use of coolants (organic, high pressure helium) that result in power conversion systems with good thermal efficiency and relatively low cost. Water coolant would significantly reduce thermal efficiency, while lithium and salt coolants, which have been proposed for DT reactors, will have comparable power conversion efficiencies, but will probably be significantly more expensive. Helium cooled blankets with direct gas turbine power conversion cycles can also be used with DT reactors, but activation problems will be more severe, and the portion of blanket power in the metallic structure will probably not be available for the direct cycle, because of temperature limitations. A very important potential advantage of advanced fuel reactors over DT fusion reactors is the possibility of easier blanket maintenance and reduced down time for replacement. If unexpected leaks occur, in most cases the leaking circuit can be shut off and a redundant cooling curcuit will take over the thermal load. With the D-He 3 reactor, it appears practical to do this while the reactor is operating, as long as the leak is small enough not to shut down the reactor. Redundancy for Cat-D reactors has not been explored in detail, but appears feasible in principle. The idea of mobile units operating in the reactor chamber for service and maintenance of radioactive elements is explored

  19. Fusion-fission hybrid reactors

    International Nuclear Information System (INIS)

    Greenspan, E.

    1984-01-01

    This chapter discusses the range of characteristics attainable from hybrid reactor blankets; blanket design considerations; hybrid reactor designs; alternative fuel hybrid reactors; multi-purpose hybrid reactors; and hybrid reactors and the energy economy. Hybrid reactors are driven by a fusion neutron source and include fertile and/or fissile material. The fusion component provides a copious source of fusion neutrons which interact with a subcritical fission component located adjacent to the plasma or pellet chamber. Fissile fuel and/or energy are the main products of hybrid reactors. Topics include high F/M blankets, the fissile (and tritium) breeding ratio, effects of composition on blanket properties, geometrical considerations, power density and first wall loading, variations of blanket properties with irradiation, thermal-hydraulic and mechanical design considerations, safety considerations, tokamak hybrid reactors, tandem-mirror hybrid reactors, inertial confinement hybrid reactors, fusion neutron sources, fissile-fuel and energy production ability, simultaneous production of combustible and fissile fuels, fusion reactors for waste transmutation and fissile breeding, nuclear pumped laser hybrid reactors, Hybrid Fuel Factories (HFFs), and scenarios for hybrid contribution. The appendix offers hybrid reactor fundamentals. Numerous references are provided

  20. Reactor protection systems for the Replacement Research Reactor, ANSTO

    International Nuclear Information System (INIS)

    Morris, C.R.

    2003-01-01

    The 20-MW Replacement Research Reactor Project which is currently under construction at ANSTO will have a combination of a state of the art triplicated computer based reactor protection system, and a fully independent, and diverse, triplicated analogue reactor protection system, that has been in use in the nuclear industry, for many decades. The First Reactor Protection System (FRPS) consists of a Triconex triplicated modular redundant system that has recently been approved by the USNRC for use in the USA?s power reactor program. The Second Reactor Protection System is a hardwired analogue system supplied by Foxboro, the Spec 200 system, which is also Class1E qualified. The FRPS is used to drop the control rods when its safety parameter setpoints have been reached. The SRPS is used to drain the reflector tank and since this operation would result in a reactor poison out due to the time it would take to refill the tank the FRPS trip setpoints are more limiting. The FRPS and SRPS have limited hardwired indications on the control panels in the main control room (MCR) and emergency control centre (ECC), however all FRPS and SRPS parameters are capable of being displayed on the reactor control and monitoring system (RCMS) video display units. The RCMS is a Foxboro Series I/A control system which is used for plant control and monitoring and as a protection system for the cold neutron source. This paper will provide technical information on both systems, their trip logics, their interconnections with each other, and their integration into the reactor control and monitoring system and control panels. (author)

  1. Reactor container

    International Nuclear Information System (INIS)

    Fukazawa, Masanori.

    1991-01-01

    A system for controlling combustible gases, it has been constituted at present such that the combustible gases are controlled by exhausting them to the wet well of a reactor container. In this system, however, there has been a problem, in a reactor container having plenums in addition to the wet well and the dry well, that the combustible gases in such plenums can not be controlled. In view of the above, in the present invention, suction ports or exhaust ports of the combustible gas control system are disposed to the wet well, the dry well and the plenums to control the combustible gases in the reactor container. Since this can control the combustible gases in the entire reactor container, the integrity of the reactor container can be ensured. (T.M.)

  2. Soil classification using CPTu in Fort McMurray

    Energy Technology Data Exchange (ETDEWEB)

    Elbanna, M. [AMEC Earth and Environmental, Nanaimo, BC (Canada); El Sabbagh, M. [AMEC Earth and Environmental, Burnaby, BC (Canada); Sharp, J. [ConeTec Investigations Ltd., Richmond, BC (Canada)

    2009-07-01

    This paper evaluated 4 piezocone penetration testing (CPTu) classification methods using data from 3 different sites near Fort McMurray in northern Alberta. For comparative purposes, other in-situ tests, field observations, and laboratory tests were performed at all sites in close proximity to the CPTu soundings. The study evaluated pleistocene sand and sand till deposits with low fines content. Profiling these deposits is necessary because they are often used as filler material for earth retaining structures in many oilsands projects. The study also evaluated pleistocene clay and clay tills that are often used as low permeability material for seepage control. In thick layers, pleistocene clay is known to cause foundation problems. CPTu with dissipation data was shown to be a useful tool in geotechnical engineering practice to provide near continuous soil profiling and material properties. CPTu tip resistance and sleeve friction combined with pore pressure measurement provided useful evaluation of subsurface soil types. It was concluded that although all of the CPTu classification charts provided reasonable soil classification in typical soil conditions, local experience and understanding of soil behaviour is needed to make an appropriate selection of the most applicable charts in a given geological condition. 7 refs., 11 figs.

  3. A multi-purpose reactor

    International Nuclear Information System (INIS)

    Changwen Ma

    2000-01-01

    An integrated natural circulation self pressurized reactor can be used for sea water desalination, electrogeneration, ship propulsion and district or process heating. The reactor can be used for ship propulsion because it has following advantages: it is a integrated reactor. Whole primary loop is included in a size limited pressure vessel. For a 200 MW reactor the diameter of the pressure vessel is about 5 m. It is convenient to arranged on a ship. Hydraulic driving facility of control rods is used on the reactor. It notably decreases the height of the reactor. For ship propulsion, smaller diameter and smaller height are important. Besides these, the operation reliability of the reactor is high enough, because there is no rotational machine (for example, circulating pump) in safety systems. Reactor systems are simple. There are no emergency water injection system and boron concentration regulating system. These features for ship propulsion reactor are valuable. Design of the reactor is based on existing demonstration district heating reactor design. The mechanic design principles are the same. But boiling is introduced in the reactor core. Several variants to use the reactor as a movable seawater desalination plant are presented in the paper. When the sea water desalination plant is working to produce fresh water, the reactor can supply electricity at the same time to the local electricity network. Some analyses for comprehensive application of the reactor have been done. Main features and parameters of the small (Thermopower 200 MW) reactor are given in the paper. (author)

  4. TU Electric reactor physics model verification: Power reactor benchmark

    International Nuclear Information System (INIS)

    Willingham, C.E.; Killgore, M.R.

    1988-01-01

    Power reactor benchmark calculations using the advanced code package CASMO-3/SIMULATE-3 have been performed for six cycles of Prairie Island Unit 1. The reload fuel designs for the selected cycles included gadolinia as a burnable absorber, natural uranium axial blankets and increased water-to-fuel ratio. The calculated results for both startup reactor physics tests (boron endpoints, control rod worths, and isothermal temperature coefficients) and full power depletion results were compared to measured plant data. These comparisons show that the TU Electric reactor physics models accurately predict important measured parameters for power reactors

  5. Supercritical Water Reactors

    International Nuclear Information System (INIS)

    Bouchter, J.C.; Dufour, P.; Guidez, J.; Latge, C.; Renault, C.; Rimpault, G.

    2014-01-01

    The supercritical water reactor (SCWR) is one of the 6 concepts selected for the 4. generation of nuclear reactors. SCWR is a new concept, it is an attempt to optimize boiling water reactors by using the main advantages of supercritical water: only liquid phase and a high calorific capacity. The SCWR requires very high temperatures (over 375 C degrees) and very high pressures (over 22.1 MPa) to operate which allows a high conversion yield (44% instead of 33% for a PWR). Low volumes of coolant are necessary which makes the neutron spectrum shift towards higher energies and it is then possible to consider fast reactors operating with supercritical water. The main drawbacks of supercritical water is the necessity to use very high pressures which has important constraints on the reactor design, its physical properties (density, calorific capacity) that vary strongly with temperatures and pressures and its very high corrosiveness. The feasibility of the concept is not yet assured in terms of adequate materials that resist to corrosion, reactor stability, reactor safety, and reactor behaviour in accidental situations. (A.C.)

  6. Tank type reactor

    International Nuclear Information System (INIS)

    Otsuka, Fumio.

    1989-01-01

    The present invention concerns a tank type reactor capable of securing reactor core integrity by preventing incorporation of gases to an intermediate heat exchanger, thgereby improving the reliability. In a conventional tank type reactor, since vortex flows are easily caused near the inlet of an intermediate heat exchanger, there is a fear that cover gases are involved into the coolant main streams to induce fetal accidents. In the present invention, a reactor core is suspended by way of a suspending body to the inside of a reactor vessel and an intermediate heat exchanger and a pump are disposed between the suspending body and the reactor vessel, in which a vortex current preventive plate is attached at the outside near the coolant inlet on the primary circuit of the intermediate heat exchanger. In this way vortex or turbulence near the inlet of the intermediate heata exchanger or near the surface of coolants can be prevented. Accordingly, the cover gases are no more involved, to insure the reactor core integrity and obtain a tank type nuclear reactor of high reliability. (I.S.)

  7. New about research reactors

    International Nuclear Information System (INIS)

    Egorenkov, P.M.

    2001-01-01

    The multi-purpose research reactor MAPLE (Canada) and concept of new reactor MAPLE-CNF as will substitute the known Canadian research reactor NRU are described. New reactor will be used as contributor for investigations into materials, neutron beams and further developments for the CANDU type reactor. The Budapest research reactor (BRR) and its application after the last reconstruction are considered also [ru

  8. LeFort I osteotomy and secondary procedures in full-face transplant patients.

    Science.gov (United States)

    Barret, Juan P; Serracanta, Jordi

    2013-05-01

    Composite tissue allotransplantion has been the latest addition to reconstructive plastic surgery of limbs and faces. These techniques have opened up a new paradigm in reconstruction. However, plastic surgeons will have to face a new patient population that receives the application of vascularised tissue allografts and immunosuppression. Secondary surgery may be necessary in this population, especially in the transplanted tissues, to improve aesthetics and function following the transplant, although little is known regarding the exact clinical protocol to be followed and the feasibility of standard plastic surgery techniques on transplanted tissues. We present our experience of a LeFort I osteotomy, limited ritidectomy and blepharoplasty in a full-face transplant recipient. Copyright © 2012 British Association of Plastic, Reconstructive and Aesthetic Surgeons. Published by Elsevier Ltd. All rights reserved.

  9. Evaluation of Pressure Changes in HANARO Reactor Hall after a Reactor Shutdown

    International Nuclear Information System (INIS)

    Han, Geeyang; Han, Jaesam; Ahn, Gukhoon; Jung, Hoansung

    2013-01-01

    The major objective of this work is intended to evaluate the characteristics of the thermal behavior regarding how the decay heat will be affected by the reactor hall pressure change and the increase of pool water temperature induced in the primary coolant after a reactor shutdown. The particular reactor pool water temperature at the surface where it is evaporated owing to the decay heat resulting in the local heat transfer rate is related to the pressure change response in the reactor hall associated with the primary cooling system because of the reduction of the heat exchanger to remove the heat. The increase in the pool water temperature is proportional to the heat transfer rate in the reactor pool. Consequently, any limit on the reactor pool water temperature imposes a corresponding limit on the reactor hall pressure. At HANARO, the decay heat after a reactor shutdown is mainly removed by the natural circulation cooling in the reactor pool. This paper is written for the safety feature of the pressure change related leakage rate from the reactor hall. The calculation results show that the increase of pressure in the reactor hall will not cause any serious problems to the safety limits although the reactor hall pressure is slightly increased. Therefore, it was concluded that the pool water temperature increase is not so rapid as to cause the pressure to vary significantly in the reactor hall. Furthermore, the mathematical model developed in this work can be a useful analytical tool for scoping and parametric studies in the area of thermal transient analysis, with its proper representation of the interaction between the temperature and pressure in the reactor hall

  10. Design guide for Category III reactors: pool type reactors

    International Nuclear Information System (INIS)

    Brynda, W.J.; Lobner, P.R.; Powell, R.W.; Straker, E.A.

    1978-11-01

    The Department of Energy (DOE) in the ERDA Manual requires that all DOE-owned reactors be sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that gives adequate consideration to health and safety factors. Specific guidance pertinent to the safety of DOE-owned reactors is found in Chapter 0540 of the ERDA Manual. The purpose of this Design Guide is to provide additional guidance to aid the DOE facility contractor in meeting the requirement that the siting, design, construction, modification, operation, maintenance, and decommissioning of DOE-owned reactors be in accordance with generally uniform standards, guides, and codes which are comparable to those applied to similar reactors licensed by the Nuclear Regulatory Commission (NRC). This Design Guide deals principally with the design and functional requirement of Category III reactor structures, components, and systems

  11. The computerized reactor period measurement system for China fast burst reactor-II

    International Nuclear Information System (INIS)

    Zhao Wuwen; Jiang Zhiguo

    1996-01-01

    The article simply introduces the hardware, principle, and software of the computerized reactor period measurement system for China Fast Burst Reactor-II (CFBR-II). It also gives the relation between fission yield and pre-reactivity of CFBR-II reactor system of bared reactor with decoupled-component and system of bared reactor with multiple light-material. The computerized measurement system makes the reactor period measurement into automatical and intelligent and also improves the speed and precision of period data on-line process

  12. Computer measurement system of reactor period for China fast burst reactor-II

    International Nuclear Information System (INIS)

    Zhao Wuwen; Jiang Zhiguo

    1997-01-01

    The author simply introduces the hardware, principle, and software of the reactor period computer measure system for China Fast Burst Reactor-II (CFBR-II). It also gives the relation between Fission yield and Pre-reactivity of CFBR-II reactor system of bared reactor with decoupled-component and system of bared reactor with multiple light-material. The computer measure system makes the reactor period measurement into automation and intellectualization and also improves the speed and precision of period data process on-line

  13. Reactor safety method

    International Nuclear Information System (INIS)

    Vachon, L.J.

    1980-01-01

    This invention relates to safety means for preventing a gas cooled nuclear reactor from attaining criticality prior to start up in the event the reactor core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the reactor coolant channels with a neutral absorbing material that will vaporize at the reactor's operating temperature

  14. Small propulsion reactor design based on particle bed reactor concept

    International Nuclear Information System (INIS)

    Ludewig, H.; Lazareth, O.; Mughabghab, S.; Perkins, K.; Powell, J.R.

    1989-01-01

    In this paper Particle Bed Reactor (PBR) designs are discussed which use 233 U and /sup 242m/Am as fissile materials. A constant total power of 100MW is assumed for all reactors in this study. Three broad aspects of these reactors is discussed. First, possible reactor designs are developed, second physics calculations are outlined and discussed and third mass estimates of the various candidates reactors are made. It is concluded that reactors with a specific mass of 1 kg/MW can be envisioned of 233 U is used and approximately a quarter of this value can be achieved if /sup 242m/Am is used. If this power level is increased by increasing the power density lower specific mass values are achievable. The limit will be determined by uncertainties in the thermal-hydraulic analysis. 5 refs., 5 figs., 6 tabs

  15. Physics of nuclear reactors

    International Nuclear Information System (INIS)

    Baeten, Peter

    2006-01-01

    This course gives an introduction to Nuclear Reactor Physics. The first chapter explains the most important parameters and concepts in nuclear reactor physics such as fission, cross sections and the effective multiplication factor. Further on, in the second chapter, the flux distributions in a stationary reactor are derived from the diffusion equation. Reactor kinetics, reactor control and reactor dynamics (feedback effects) are described in the following three chapters. The course concludes with a short description of the different types of existing and future reactors. (author)

  16. Investigation on the Core Bypass Flow in a Very High Temperature Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Hassan, Yassin

    2013-10-22

    Uncertainties associated with the core bypass flow are some of the key issues that directly influence the coolant mass flow distribution and magnitude, and thus the operational core temperature profiles, in the very high-temperature reactor (VHTR). Designers will attempt to configure the core geometry so the core cooling flow rate magnitude and distribution conform to the design values. The objective of this project is to study the bypass flow both experimentally and computationally. Researchers will develop experimental data using state-of-the-art particle image velocimetry in a small test facility. The team will attempt to obtain full field temperature distribution using racks of thermocouples. The experimental data are intended to benchmark computational fluid dynamics (CFD) codes by providing detailed information. These experimental data are urgently needed for validation of the CFD codes. The following are the project tasks: • Construct a small-scale bench-top experiment to resemble the bypass flow between the graphite blocks, varying parameters to address their impact on bypass flow. Wall roughness of the graphite block walls, spacing between the blocks, and temperature of the blocks are some of the parameters to be tested. • Perform CFD to evaluate pre- and post-test calculations and turbulence models, including sensitivity studies to achieve high accuracy. • Develop the state-of-the art large eddy simulation (LES) using appropriate subgrid modeling. • Develop models to be used in systems thermal hydraulics codes to account and estimate the bypass flows. These computer programs include, among others, RELAP3D, MELCOR, GAMMA, and GAS-NET. Actual core bypass flow rate may vary considerably from the design value. Although the uncertainty of the bypass flow rate is not known, some sources have stated that the bypass flow rates in the Fort St. Vrain reactor were between 8 and 25 percent of the total reactor mass flow rate. If bypass flow rates are on the

  17. Generation III+ Reactor Portfolio

    International Nuclear Information System (INIS)

    2010-03-01

    While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO 2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPR TM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1 TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENA TM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENA TM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

  18. Guide to power reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-07-15

    The IAEA's major first scientific publication is the Directory of Power Reactors now in operation or under construction in various parts of the world. The purpose of the directory is to present important details of various power projects in such a way as to provide a source of easy reference for anyone interested in the development of the peaceful uses of atomic energy, either at the technical or management level. Six pages have been devoted to each reactor the first of which contains general information, reactor physics data and information about the core. The second and third contain sketches of the fuel element or of the fuel element assembly, and of the horizontal and vertical sections of the reactor. On the fourth page information is grouped under the following heads: fuel element, core heat transfer, control, reactor vessel and over-all dimensions, and fluid flow. The fifth page shows a simplified flow diagram, while the sixth provides information on reflector and shielding, containment and turbo generator. Some information has also been given, when available, on cost estimates and operating staff requirements. Remarks and a bibliography constitute the last part of the description of each reactor. Reactor projects included in this directory are pressurized light water cooled power reactors. Boiling light water cooled power reactors, heavy water cooled power reactors, gas cooled power reactors, organic cooled power reactors liquid metal cooled power reactors and liquid metal cooled power reactors

  19. Analysis of dynamic stability and safety of reactor system by reactor simulator

    International Nuclear Information System (INIS)

    Raisic, N.

    1963-11-01

    In order to enable qualitative analysis of dynamic properties of reactors RA and RB, mathematical models of these reactors were formulated and adapted for solution on analog computer. This report contains basic assessments for creating the model and complete equations for each reactor. Model was used to analyse three possible accidents at the RA reactor and possible hypothetical accidents at the RB reactor

  20. Nuclear reactor physics

    CERN Document Server

    Stacey, Weston M

    2010-01-01

    Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. The second edition of this successful comprehensive textbook and reference on basic and advanced nuclear reactor physics has been completely updated, revised and enlarged to include the latest developme