WorldWideScience

Sample records for unit operating status

  1. Integrated Ground Operations Demonstration Units Testing Plans and Status

    Science.gov (United States)

    Johnson, Robert G.; Notardonato, William U.; Currin, Kelly M.; Orozco-Smith, Evelyn M.

    2012-01-01

    Cryogenic propellant loading operations with their associated flight and ground systems are some of the most complex, critical activities in launch operations. Consequently, these systems and operations account for a sizeable portion of the life cycle costs of any launch program. NASA operations for handling cryogens in ground support equipment have not changed substantially in 50 years, despite advances in cryogenics, system health management and command and control technologies. This project was developed to mature, integrate and demonstrate advancement in the current state of the art in these areas using two distinct integrated ground operations demonstration units (GODU): GODU Integrated Refrigeration and Storage (IRAS) and GODU Autonomous Control

  2. Licensed operating reactors. Operating units status report, data as of 2-28-79

    International Nuclear Information System (INIS)

    1979-03-01

    This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices and IE Headquarters; and the third section is an appendix containing comparative statistics of U.S. nuclear/fossil capacity, identification of nuclear power plants within regional Electric Reliability Councils, the relative status of U.S. nuclear electric production to all U.S. electric production by state, and selected Edison Electric Institute operating statistics. Throughout the report, statistical factors for periods greater than a report month, or for more than one unit, are computed as the arithmetic average of each unit's individual operating statistics. The statistical factors for each unit for the report month are computed from actual power production for the month. The factors for the life-span of each unit (the ''Cumulative'' column) are reported by the utility and are not entirely re-computed by NRC. Utility power production data is checked for consistency with previously submitted statistics

  3. Preparation status for continuous operation of Kori unit 1 NPP in Korea

    International Nuclear Information System (INIS)

    Choi, C.H. . E-mail : chechee@khnp.co.kr

    2005-01-01

    Kori unit 1 Nuclear Power Plant is the first commercial operation plant in Korea. In Korea, the life extension of NPP beyond design lifetime reached practically application stage. Preparations status for continuous operation of Kori unit 1, Many researches have demonstrated that life extension beyond design lifetime is possible in terms of technology. This paper is to introduce and to share the continuous operation preparations status and schedule for Kori unit 1 License Renewal Process an additional every 10 years beyond the design life 30 years term. (author)

  4. Status of remedial investigation activities in the Hanford Site 300 Area groundwater operable unit

    International Nuclear Information System (INIS)

    Hulstrom, L.C.; Innis, B.E.; Frank, M.A.

    1993-09-01

    The Phase 1 remedial investigation (RI) and Phase 1 and 2 feasibility studies (FS) for the 300-FF-5 groundwater operable unit underlying the 300 Area on the Hanford Site have been completed. Analysis and evaluation of soil, sediment, and surface water, and biotic sampling data, groundwater chemistry, and radiological data gathered over the past 3 years has been completed. Risk assessment calculations have been performed. Use of the data gathered, coupled with information from an automated water level data collection system, has enabled engineers to track three plumes that represent the most significant contamination of the groundwater

  5. Status of TRISTAN operation

    International Nuclear Information System (INIS)

    Satoh, Kotaro

    1990-01-01

    The present status of the TRISTAN operation is summarized mainly after the installation of superconducting cavities in the 1988 summer shutdown. The paper describes the initial experience of the superconducting cavity operation, the colliding operation at 30.4 GeV and the beam injection. Future improvement is also reported. (author)

  6. Waste Area Group 10, Operable Unit 10-08, Remedial Investigation/Feasibility Study Annual Status Report for Fiscal Year 2006

    Energy Technology Data Exchange (ETDEWEB)

    R. P. Wells

    2007-05-09

    This report provides a status of the progress made in Fiscal Year 2006 on tasks identified in the Waste Area Group 10, Operable Unit 10-08, Remedial Investigation/Feasibility Study Work Plan. Major accomplishments include: (1) groundwater sampling and review of the groundwater monitoring data, (2) installation of a Sitewide groundwater-level monitoring network, (3) update of the Groundwater Monitoring and Field Sampling Plan of Operable Unit 10-08, (4) re-evaluation of the risk at Site TSF-08, (5) progress on the Operable Unit 10-08 Sitewide Groundwater Model.

  7. Operable Unit Boundaries

    Data.gov (United States)

    U.S. Environmental Protection Agency — This dataset consists of operable unit data from multiple Superfund sites in U.S. EPA Region 8. These data were acquired from multiple sources at different times and...

  8. Product Operations Status Summary Metrics

    Science.gov (United States)

    Takagi, Atsuya; Toole, Nicholas

    2010-01-01

    The Product Operations Status Summary Metrics (POSSUM) computer program provides a readable view into the state of the Phoenix Operations Product Generation Subsystem (OPGS) data pipeline. POSSUM provides a user interface that can search the data store, collect product metadata, and display the results in an easily-readable layout. It was designed with flexibility in mind for support in future missions. Flexibility over various data store hierarchies is provided through the disk-searching facilities of Marsviewer. This is a proven program that has been in operational use since the first day of the Phoenix mission.

  9. Nuclear units operating improvement by using operating experience

    International Nuclear Information System (INIS)

    Rotaru, I.; Bilegan, I.C.

    1997-01-01

    The paper presents how the information experience can be used to improve the operation of nuclear units. This areas include the following items: conservative decision making; supervisory oversight; teamwork; control room distraction; communications; expectations and standards; operator training and fundamental knowledge, procedure quality and adherence; plant status awareness. For each of these topics, the information illustrate which are the principles, the lessons learned from operating experience and the most appropriate exemplifying documents. (authors)

  10. Integrated Ground Operations Demonstration Units

    Data.gov (United States)

    National Aeronautics and Space Administration — The overall goal of the AES Integrated Ground Operations Demonstration Units (IGODU) project is to demonstrate cost efficient cryogenic operations on a relevant...

  11. Status report on cyclotron operation

    International Nuclear Information System (INIS)

    Kovacs, P.; Szuecs, I.; Ander, I.; Lakatos, T.; Fenyvesi, A.; Ditroi, F.; Takacs, S.; Tarkanyi, F.

    2004-01-01

    The operation of the cyclotron in 2003 was again concentrated to 9 months; January, July and August were reserved for maintenance, renewal works and holidays. The overall working time of the accelerator was 4051 hours. The cyclotron was available for users for 3682 hours. In order to improve the circumstances of the irradiations renewal and improvements were done. (N.T.)

  12. Status report on cyclotron operation

    CERN Document Server

    Kovács, P; Ander, I; Lakatos, T; Fenyvesi, A; Ditrói, F; Takács, S; Tarkanyi, F

    2003-01-01

    The operation of the cyclotron in 2002 was concentrated to 9 months; January, July and August were reserved for maintenance and holidays. The overall working time of the accelerator was 4084 hours, the breakdown periods amounted to 15 hours last year. In order to improve the circumstances of the irradiations, several following improvements were done. (R.P.)

  13. Organization of Control Units with Operational Addressing

    OpenAIRE

    Alexander A. Barkalov; Roman M. Babakov; Larysa A. Titarenko

    2012-01-01

    The using of operational addressing unit as the block of control unit is proposed. The new structure model of Moore finite-state machine with reduced hardware amount is developed. The generalized structure of operational addressing unit is suggested. An example of synthesis process for Moore finite-state machine with operational addressing unit is given. The analytical researches of proposed structure of control unit are executed.

  14. Status Report on Cyclotron Operation

    International Nuclear Information System (INIS)

    Kovacs, P.; Szuecs, I.; Ander, I.; Lakatos, T.; Tarkanyi, F.

    2004-01-01

    Complete text of publication follows. The operation of the cyclotron in 2004 was concentrated to the usual 9 months; January, July and August were reserved for maintenance and holidays. The overall working time of the accelerator was 3554 hours, the time used for systematic maintenance was 450 hours. The breakdown periods amounted to 70 hours last year, included in it a 50 hours repair of RF control module under guarantee. The cyclotron was available for users during 3034 hours. The effectively used beam-on-target time statistics is summarized in Table 1. Developments: A new measuring site with a HPGe detector based gamma spectrometer is under installation in the basement of the Cyclotron Laboratory. A two channel pneumatic rabbit system is also under development to enable fast transport of samples between the new measuring site and two irradiation sites (the low intensity fast neutron irradiation site and the beam line used for Thin Layer Activation). (author)

  15. Physical protection of nuclear operational units

    International Nuclear Information System (INIS)

    1981-07-01

    The general principles of and basic requirements for the physical protection of operational units in the nuclear field are established. They concern the operational units whose activities are related with production, utilization, processing, reprocessing, handling, transport or storage of materials of interest for the Brazilian Nuclear Program. (I.C.R.) [pt

  16. Junior Leader Training Development in Operational Units

    Science.gov (United States)

    2012-04-01

    UNITS Successful operational units do not arise without tough, realistic, and challenging training. Field Manual (FM) 7-0, Training Units and D...operations. The manual provides junior leaders with guidance on how to conduct training and training management. Of particular importance is the definition...1 Relation htp between ADDIE and the Anny Training Management Model. The Army Training Management Model and ADDIE process appear in TRADOC PAM 350

  17. Plant status control - with an operational focus

    International Nuclear Information System (INIS)

    Lane, L.A.

    2000-01-01

    In the Nuclear industry, we have done a very good job of designing, developing, constructing, and improving our nuclear facilities. We have, however, often been inconsistent in documenting the details of our facilities, clearly addressing the rules around facility operation, and controlling and tracking the temporary, or permanent changes to our facilities. The reality is, that once we build a facility, we then must operate the facility, for it to be viable. Further we must operate it safely and efficiently for the facility to produce its product, and be acceptable to the public. Unfortunately, when we design and build these large, complicated facilities, we cannot project all the nuances of facility operation, although we can recognize this potential gap, and prepare for it. In order to allow for the complexities of the real world, we must provide the individuals who are tasked with operating our nuclear facilities, with the tools and processes to deal with 'all the nuances' of facility operation. This discussion will focus on the concepts behind a key process for ensuring that we meet our design and operating needs for our facilities, as well as recognizing and dealing with the potential gaps. The key process is 'Plant Status Control', and the discussion will have a primary focus on the needs of the end users, that being the individuals that have the immediate and current accountability for control and safety of the facility, the equipment, the staff, and ultimately the public, that being our Operations staff, and the Shift Manager. (author)

  18. Operative training in otolaryngology in the United Kingdom: a specialist registrar survey

    NARCIS (Netherlands)

    Georgalas, Christos; Hadjihannas, Edward; Ghufoor, Khalid; Pracy, Paul; Papesch, Michael

    2005-01-01

    OBJECTIVE: To assess the current status of operative training for otolaryngology specialist registrars in the United Kingdom. DESIGN: Web-based questionnaire survey. PARTICIPANTS: All otolaryngology specialist registrars in the United Kingdom. MAIN OUTCOME MEASURES: The overall satisfaction with

  19. Safety status system for operating room devices.

    Science.gov (United States)

    Guédon, Annetje C P; Wauben, Linda S G L; Overvelde, Marlies; Blok, Joleen H; van der Elst, Maarten; Dankelman, Jenny; van den Dobbelsteen, John J

    2014-01-01

    Since the increase of the number of technological aids in the operating room (OR), equipment-related incidents have come to be a common kind of adverse events. This underlines the importance of adequate equipment management to improve the safety in the OR. A system was developed to monitor the safety status (periodic maintenance and registered malfunctions) of OR devices and to facilitate the notification of malfunctions. The objective was to assess whether the system is suitable for use in an busy OR setting and to analyse its effect on the notification of malfunctions. The system checks automatically the safety status of OR devices through constant communication with the technical facility management system, informs the OR staff real-time and facilitates notification of malfunctions. The system was tested for a pilot period of six months in four ORs of a Dutch teaching hospital and 17 users were interviewed on the usability of the system. The users provided positive feedback on the usability. For 86.6% of total time, the localisation of OR devices was accurate. 62 malfunctions of OR devices were reported, an increase of 12 notifications compared to the previous year. The safety status system was suitable for an OR complex, both from a usability and technical point of view, and an increase of reported malfunctions was observed. The system eases monitoring the safety status of equipment and is a promising tool to improve the safety related to OR devices.

  20. Operational safety experience reporting in the United States

    International Nuclear Information System (INIS)

    Hartfield, R.A.

    1978-01-01

    Licensees of nuclear power plants in the United States have many reporting requirements included in their technical specifications and the code of federal regulations, title 10. The Nuclear Regulatory Commisson receives these reports and utilizes them in its regulatory program. Part of this usage includes collecting and publishing this operating experience data in various reports and storing information in various data systems. This paper will discuss the data systems and reports on operating experience published and used by the NRC. In addition, some observations on operating experience will be made. Subjects included will be the Licensee Event Report (LER) Data File, the Operating Unit Status Report (Gray Book), Radiation Exposure Reports, Effluents Reports, the Nuclear Plant Reliability Data System, Current Events, Bulletin Wrapups and Annual Summaries. Some of the uses of the reports and systems will be discussed. The Abnormal Occurence Report to the US Congress will also be described and discussed. (author)

  1. Operation status and upgrading of HIRFL

    International Nuclear Information System (INIS)

    Tang, J.Y.; Wang, Y.F.; Wei, B.W.

    2001-01-01

    The operation status and the undergoing upgrading at HIRFL machine are presented. The accelerated ion species with the machine have been expanding, including metallic ions and higher energy with the new ECR ion source. The upgrading of HIRFL as the pre-accelerator of CSR storage ring has been processing steadily. The new 14.5 GHz ECR ion source has been put in operation in early 1999. A full-superconducting ECR ion source of 18 GHz is under design. The manufacture of the new vacuum chamber for SFC is just finished and the installation is to be started. The construction of the new B1 buncher is nearly to be finished, and the off-line test and the installation will be started soon. Another two identical bunchers will be ordered after the test. The beam distribution system is under upgrading to make all experiment stations separate from the others and the time-sharing mode possible, and a new cancer-therapy station is also under construction. The other upgrading items include the yoke enlarging of SFC, beam diagnostics, computer control and beam distribution system

  2. Unpacking Referent Units in Fraction Operations

    Science.gov (United States)

    Philipp, Randolph A.; Hawthorne, Casey

    2015-01-01

    Although fraction operations are procedurally straightforward, they are complex, because they require learners to conceptualize different units and view quantities in multiple ways. Prospective secondary school teachers sometimes provide an algebraic explanation for inverting and multiplying when dividing fractions. That authors of this article…

  3. Preparing nuclear power plant units for operation

    International Nuclear Information System (INIS)

    Hudcovic, R.; Telgarsky, K.; Kmosena, J.

    1984-01-01

    The factors are listed which have to be taken into consideration for planning the unit operation, i.e., the implementation of planned repairs, checks of equipment and refuellings. All basic input data were evaluated as the basic for drawing up the schedule of routine repairs and overhauls for the coming period. (E.S.)

  4. Operating performance of LWR nuclear generating units

    International Nuclear Information System (INIS)

    Pia, S.

    1984-01-01

    This work aims at reviewing, on the basis of historical data, the operational problem areas which explain the degree of availability and productivity achieved up to now by nuclear power plants in commercial operation in the world. The operating performance data of nuclear power plants area analysed with respect to plant type, size and other significant reference parameters and they are evaluated also by comparison with fossil generating unit data. Major performance indices data are presented for both nuclear and fossil units type and distribution of outage causes. Unplanned full outages caused by nuclear power plant equipment and components failure are particulary emphasized. The trend for unplanned full outages due to the failure of components shows decreasing numerical values in 1981 with respect to the previous years. But this result should be weighed with the increasing plant unavailability hours needed for maintenance and repair action (chiefly preventive maintenance on critical components). This means that the number and downtime of forced outage must be drastically reduced for economic reasons (production losses and problems associated with the unavailable unit unplanned replacement) as well as for plant safe and reliable operation (sudden unavailability of key components and frequency of transients associated with plant shutdown and routine startup operation)

  5. The status of podiatry in the United Kingdom.

    Science.gov (United States)

    Mandy, Phil

    2008-12-01

    This paper reviews the sources of professional status and analyses these in relation to the podiatry profession in the United Kingdom. It is argued that the nature and act of professional practice and the patient/professional relationship are of particular importance in defining the status of the profession. These effects are discussed in relation to podiatry and compared to a high status professional group, that of dentistry. Finally the effects of attempting to change professional status are discussed.

  6. 200-UP-2 operable unit radiological surveys

    International Nuclear Information System (INIS)

    Wendling, M.A.

    1994-01-01

    This report summarizes and documents the results of the radiological surveys conducted from August 17 through December 16, 1993 over a partial area of the 200-UP-2 Operable Unit, 200-W Area, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology of the Mobile Surface Contamination Monitor 11 (MSCM-II) and the Ultra Sonic Ranging And Data System (USRADS). The radiological survey of the 200-UP-2 Operable Unit was conducted by the Site Investigative Surveys/Environmental Restoration Health Physics Organization of the Westinghouse Hanford Company. The survey methodology for the majority of area was based on utilization of the MSCM-II or the USRADS for automated recording of the gross beta/gamma radiation levels at or near six (6) inches from the surface soil

  7. Status report on the accelerators operation

    International Nuclear Information System (INIS)

    Biri, S.; Kormany, Z.; Berzi, I.; Racz, R.

    2011-01-01

    vacuum measurement system that is based on two Pfeiffer MaxiGauge control units, has the following features: receiving and presenting data of 12 vacuum measurement heads, switching on/off the heads, writing continuous log of the vacuum data of VdG-5 accelerator tube. The hardware development of the quadrupole control system was finished in the first half of 2011. In September we started to collect data with Quadrupole- Control software to increase the efficiency of beam transport with recalling stored parameters. It has the following features: control of 1 electrostatic and 3 magnetic quadrupole dublet power supplies (Figure 1), storing/recalling of operating parameters, reading from two beamon- target current meters, VdG-5 beam energy versus analyzing magnet calculator. In 2011 the VdG-1 machine was working for only 84 hours. There were some test measurements with proton beam for a time-of-flight electron-spectrometer. (author)

  8. Licensed operating reactors: status summary report, data as of May 31, 1982

    International Nuclear Information System (INIS)

    1982-06-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  9. Licensed operating reactors: Status summary report, data as of 02-28-89

    International Nuclear Information System (INIS)

    1989-03-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactor Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  10. Licensed operating reactors status summary report data as of January 31, 1989

    International Nuclear Information System (INIS)

    Schwartz, I.

    1989-03-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information, such as spent fuel storage capability, reactor years of experience, and non-power reactors in the United States

  11. Licensed operating reactors. Status summary report, data as of 8-31-82

    International Nuclear Information System (INIS)

    1982-09-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  12. Licensed operating reactors: Status summary report data as of 9-30-86

    International Nuclear Information System (INIS)

    1987-03-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices. IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  13. Licensed operating reactors status summary report, data as of December 31, 1988

    International Nuclear Information System (INIS)

    1989-02-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  14. Licensed operating reactors status summary report data as of April 30, 1983. Vol. 7, No. 5

    International Nuclear Information System (INIS)

    1983-05-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  15. Licensed operating reactors. Status summary report data as of October 31, 1982

    International Nuclear Information System (INIS)

    1982-11-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  16. Licensed operating reactors: status summary report, data as of May 31, 1983. Volume 7, No. 6

    International Nuclear Information System (INIS)

    1983-06-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  17. Licensed operating reactors: Status summary report, data as of 11-30-88

    International Nuclear Information System (INIS)

    1989-01-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information, such as spent fuel storage capability, reactor years of experience, and non-power reactors in the United States

  18. Licensed operating reactors: Status summary report, Data as of 08-31-86

    International Nuclear Information System (INIS)

    1987-03-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  19. Status Report on the accelerators operation

    International Nuclear Information System (INIS)

    Biri, S.; Kormany, Z.; Berzi, I.; Racz, R.; Perduk, Z.; Vajda, I.

    2012-01-01

    In 2012 our particle accelerators operated as scheduled, safely and without major or long breakdowns. The utilization rates of the accelerators slightly increased in comparing to the preceding year (see Fig. 1). The cyclotron delivered 1900 hours and the 40-years old 5 MeV Van de Graaff generator supplied more than 2400 hours. The 1 MeV Van de Graaff accelerator was also operated for short basic physics experiments (160 hours). The plasma and beam on-target time at the ECR ion source was similar to the preceding years (410 hours). The isotope separator, as ion beam accelerator was utilized only for a few hours in 2012, since the research and development in this lab focused on other fields. Nevertheless it is continuously available for research requiring special deposition techniques and for isotope tracing studies. We developed the first version of an on-line accelerator status display software. Through our homepage anybody from anywhere can now check the current state of the cyclotron, VdG-5 and ECRIS accelerators. While in 2010 the cyclotron celebrated the 25 th anniversary of its regular starting-up, in 2012 two of our other accelerators had also anniversary. The ECR Ion Source project started 20 years ago, in 1992. To celebrate it, a scientific symposium was hold in September. In the symposium - beyond the high number of audience - the leaders of the Hungarian Academy of Sciences, the University of Debrecen and the City of Debrecen attended, as well. The local and national press reported about the event in many form. A short summary of the symposium is in our homepage (in Hungarian). We had the 40 th anniversary of the regular use of the 5 MeV Van de Graaff accelerator. Having obtained the final approval of the project the 'Electrostatic Accelerator Department' was organized in the Institute in July 1967 with the tasks to perform the planning and construction of the laboratory, to make all the preparations necessary for the intensive scientific use of the

  20. Status of the breeder fuel cycle in the United States

    International Nuclear Information System (INIS)

    Burch, W.D.

    1985-01-01

    This paper reviews the status and plans for the fast reactor fuel cycle in the United States. The United States is undertaking a complete reexamination of its entire breeder program strategy, and the direction of the new program is not yet clear. Studies in progress to examine the associated fuel cycle strategies as they relate to the overall emerging breeder strategy are described. The present status of and recent developments in the fuel cycle R and D programs are summarized

  1. HDS unit revamp and operating experience

    Energy Technology Data Exchange (ETDEWEB)

    Reinhardt, J. [Veba Oel Verarbeitungs-GmbH, Gelsenkirchen (Germany); Balfanz, U. [Aral Forschung, Gelsenkirchen (Germany); Dimmig, T. [TU Bergakademie Freiberg, Freiberg (Germany)

    2002-12-01

    Ruhr Oel GmbH, a joint venture between BP and PDVSA, operates a HDS unit at its Gelsenkirchen-Scholven site. The unit produces a major blend component for diesel fuel. Driven by ambitious German environmental policy and by an agreement between the German car and oil industries on the one hand and the government on the other, more stringent low sulphur fuel specifications will be enforced in Germany much earlier than in the rest of the European Union. In view of this situation a project was developed to fulfill the new product specifications with minimum investment. In a joint effort involving the refinery, the company research facilities and the catalyst supplier (AKZO NOBEL), pilot plant tests were performed to develop the best catalyst system and the new process conditions. Based on these results, an existing HDS unit was accordingly revamped. After the revamp, the unit produced diesel fuel with 50 ppm sulphur content and furthermore test runs at 10 ppm were carried out successfully. These results are displayed in this article. (orig.)

  2. Habitat Demonstration Unit Medical Operations Workstation Upgrades

    Science.gov (United States)

    Trageser, Katherine H.

    2011-01-01

    This paper provides an overview of the design and fabrication associated with upgrades for the Medical Operations Workstation in the Habitat Demonstration Unit. The work spanned a ten week period. The upgrades will be used during the 2011 Desert Research and Technology Studies (Desert RATS) field campaign. Upgrades include a deployable privacy curtain system, a deployable tray table, an easily accessible biological waste container, reorganization and labeling of the medical supplies, and installation of a retractable camera. All of the items were completed within the ten week period.

  3. Refugee Status Required for Resettlement in the United States

    Science.gov (United States)

    2017-06-09

    STATES REFUGEE ADMISSIONS PROGRAM FLOWCHART ...the American public’s concerns. 50 APPENDIX A UNITED STATES REFUGEE ADMISSIONS PROGRAM FLOWCHART Source: US Citizenship and Immigration...TITLE AND SUBTITLE Refugee Status Required for Resettlement in the United States 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT

  4. Operational status of nuclear facilities in Japan. 2012 edition

    International Nuclear Information System (INIS)

    2012-01-01

    This document is a compilation which provides an outline of the administration of nuclear facility safety regulations as well as various data including operational status, the status of periodical and safety inspections, the status of issues, and radiation management on nuclear power reactor facilities, reactor facilities in the research and development stage, and fabrication, reprocessing, disposal, and storage facilities in fiscal year 2011 (from April 2011 to March 2012). (J.P.N.)

  5. Status of the fluidized bed unit

    International Nuclear Information System (INIS)

    Williams, P.M.; Wade, J.F.

    1994-01-01

    Rocky Flats has a serious mixed waste problem. No technology or company has a license and available facilities to remedy this dilemma. One solution under study is to use a catalytic fluidized bed unit to destroy the combustible portion of the mixed waste. The fluidized bed thermal treatment program at Rocky Flats is building on knowledge gained over twenty years of successful development activity. The FBU has numerous technical advantages over other thermal technologies to treat Rocky Flats' mixed waste, the largest being the lower temperature (700 degrees C versus 1000 degrees C) which reduces acid corrosion and mechanical failures and obviates the need for ceramic lining. Successful demonstrations have taken place on bench, pilot, and full-scale tests using radioactive mixed wastes. The program is approaching implementation and licensing of a production-scale fluidized bed system for the safe treatment of mixed waste. The measure for success on this project is the ability to work closely with the community to jointly solve problems and respond to concerns of mixed waste treatment at Rocky Flats

  6. Operational and safety status of Krsko NPP

    International Nuclear Information System (INIS)

    Sirola, P.; Kavsek, D.

    1998-01-01

    Nuclear Power Plants Krsko (NEK) is producing electricity with the high level of reliability, safety and at acceptable price for 17 years. Energy is shared between both Slovenian and Croatian grid. The specifics of sharing the initial investment costs, later covering the operations costs and energy supply between Croatia and Slovenia is causing specific decision making problems about energy cost and future investments, however not influencing the plant safety, by now. NEK is continuously following the international nuclear technology practices, standards' changes and improvements and introducing them into the processes and equipment upgrades. As the member of the most important international integration, NEK is having the possibility of sharing its experience with others. Slovenian Energy Consumption and Supply Strategy is recognizing the NEK as a long term supply of energy in Slovenia being a strong decision making base for the future. According to the above mentioned Slovenian Energy Consumption and Supply Strategy the plant is obliged to keep all the radioactive waste, produced during the plant life, on site. The extensive efforts are taking place to reduce the radioactive waste production and save the area available for temporary waste deposition. The plant is licensed for the period of 40 years of commercial operation which started in 1983, so the Life Time Management is getting more and more important, including the performance tracing of the essential components, their maintenance and surveillance programs and also replacement plans of critical equipment. The major problems the NEK is confronted with at the moment are the Steam Generators which are reaching their and of life, and a very limited radioactive waste storage area. They are excerting influence on the plant availability and operations and maintenance costs. At the moment the process of Modernization is in progress, covering the Steam Generators replacement and a Plant Specific Simulators supply

  7. Overseas Contingency Operations Funding: Background and Status

    Science.gov (United States)

    2017-02-07

    provided for a wide range of recipient countries, including Yemen , Somalia, Kenya, and the Philippines. In addition to...nations engaged in counterterrorism and crisis response activities; 39  Commander’s Emergency Response Program, which generally supports infrastructure ...Percentage Equipment and Transportation $1.7 $0.7 $2.3 25% Infrastructure $0.2 $0.1 $0.3 3% Sustainment $4.0 $1.9 $6.0 64% Training and Operations $0.7

  8. Status of an operating reliability program

    International Nuclear Information System (INIS)

    Johnson, R.A.

    1985-01-01

    This paper deals with productivity improvement programs (PIP) for nuclear generating plants. The PIP was implemented in 1979 as a joint effort between Commonwealth Edison's (CECo's) operating nuclear stations and the Station Nuclear Engineering Department. Goals were set to reduce nonproductivity by 10% over a 5 year period. This goal was accomplished December 31, 1983. Topics of discussion are program method, problem analysis and resolution, program results, program improvements, and proposed additions to the PIP. The program is providing CECo with greater electrical generating productivity

  9. 200-BP-5 operable unit treatability test report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    The 200-BP-5 Operable Unit was established in response to recommendations presented in the 200 East Groundwater Aggregate Area Management Study Report (AAMSR) (DOE-RL 1993a). Recognizing different approaches to remediation, the groundwater AAMSR recommended separating groundwater from source and vadose zone operable units and subdividing 200 East Area groundwater into two operable units. The division between the 200-BP-5 and 200-PO-1 Operable Units was based principally on source operable unit boundaries and distribution of groundwater plumes derived from either B Plant or Plutonium/Uranium Extraction (PUREX) Plant liquid waste disposal sites.

  10. 200-BP-5 operable unit treatability test report

    International Nuclear Information System (INIS)

    1996-04-01

    The 200-BP-5 Operable Unit was established in response to recommendations presented in the 200 East Groundwater Aggregate Area Management Study Report (AAMSR) (DOE-RL 1993a). Recognizing different approaches to remediation, the groundwater AAMSR recommended separating groundwater from source and vadose zone operable units and subdividing 200 East Area groundwater into two operable units. The division between the 200-BP-5 and 200-PO-1 Operable Units was based principally on source operable unit boundaries and distribution of groundwater plumes derived from either B Plant or Plutonium/Uranium Extraction (PUREX) Plant liquid waste disposal sites

  11. Licensed operating reactors: Status summary report, data as of 11-30-86

    International Nuclear Information System (INIS)

    1987-06-01

    The operating units status report - licensed operating reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  12. Conservation status of crayfishes of the United States and Canada

    Science.gov (United States)

    Christopher A. Taylor; Melvin L. Warren; J. F. Fitzpatrick; Horton H. Hobbs; Raymond F. Jezerinac; William L. Pflieger; Henry W. Robinson

    1996-01-01

    The American Fisheries Society (AFS) Endangered Species Committee herein provides a list of all crayfishes (families and Cambaridae) in the United States and Canada that includes state provincial distributions; a comprehensive review of the conservation status of all taxa; and references on biology, conservation, and...

  13. Prototype equipment status monitor for plant operational configuration management

    International Nuclear Information System (INIS)

    DeVerno, M.; Trask, D.; Groom, S.

    1998-01-01

    CANDU plants, such as the Point Lepreau GS, have tens of thousands of operable devices. The status of each operable device must be immediately available to plan and execute future changes to the plant. Historically, changes to the plant's operational configuration have been controlled using manual and administrative methods where the status of each operable device is maintained on operational flowsheets located in the work control area of the main control room. The operational flowsheets are used to plan and develop Operating Orders (OOs) or Order-to-Operate (OTOs) and the control centre work processes are used to manage their execution. After performing each OO procedure, the operational flowsheets are updated to reflect the new plant configuration. This process can be very time consuming, and due to the manual processes, can lead to the potential for time lags and errors in the recording of the current plant configuration. Through a cooperative research and development program, Canadian CANDU utilities and Atomic Energy of Canada Limited, the design organization, have applied modern information technologies to develop a prototype Equipment Status Monitor (ESM) to address processes and information flow for efficient operational configuration management. The ESM integrates electronic operational flowsheets, equipment databases, engineering and work management systems, and computerized procedures to assess, plan, execute, track, and record changes to the plant's operational configuration. This directly leads to improved change control, more timely and accurate plant status information, fewer errors, and better decision making regarding future changes. These improvements to managing the plant's operational configuration are essential to increasing plant safety, achieving a high plant availability, and maintaining high capability and capacity factors. (author)

  14. Operating experience and construction status of ATLAS

    International Nuclear Information System (INIS)

    Pardo, R.C.; DenHartog, P.; Shepard, K.W.; Zinkann, G.

    1984-01-01

    The present Argonne Tandem-Linac accelerator has operated in a reliable manner during the past year. The accelerator system provided 4402 hours of experimental beam time with a wide variety of heavy-ions. Figure 1 shows the beams which have been provided during the past year. New beams accelerated by the linac include 300 MeV 82 Se and 390 MeV 109 Ag. In tests, the tandem accelerated 102 MeV 127 I. This is the heaviest beam ever accelerated by the Argonne tandem. The long-term performance of the niobium resonators appears to be good. No significant degradation of performance has been observed for most resonators over many years of use with the exceptions of problems caused by catastrophic vacuum accidents. Resonators whose performance has deteriorated after vacuum accidents have recently been restored to their original performance state by a simple technique. The technique used is to rinse the interior of the resonator with a sequence of baths of solvents and water

  15. Licensed operating reactors: status summary report, data as of 6-30-81

    International Nuclear Information System (INIS)

    1981-07-01

    The Operating Units Status Report - Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Management and Program Analysis from the Headquarters staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, IE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the U.S. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the U.S. energy situation as a whole

  16. Licensed operating reactors: Status summary report, data as of September 30, 1989

    International Nuclear Information System (INIS)

    1989-12-01

    THE OPERATING UNITS STATUS REPORT -- LICENSED OPERATING REACTORS provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  17. Licensed operating reactors: Status summary report, data as of 07-31-86

    International Nuclear Information System (INIS)

    1986-12-01

    The Operating Units Status Report - Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Resource Management from the Headquarters staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, IE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  18. Licensed operating reactors: Status summary report, Data as of July 31, 1987

    International Nuclear Information System (INIS)

    1987-10-01

    The Operating Units Status Report - Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  19. Licensed operating reactors: Status summary report, data as of August 31, 1987

    International Nuclear Information System (INIS)

    1987-12-01

    The Operating Units Status Report - Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  20. Licensed operating reactors: Status summary report, Data as of October 31, 1987

    International Nuclear Information System (INIS)

    Schwartz, I.

    1987-12-01

    The operating units status report - licensed operating reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  1. Licensed operating reactors: Status summary report, Data as of May 31, 1987

    International Nuclear Information System (INIS)

    1987-10-01

    The OPERATING UNITS STATUS REPORT - LICENSED OPERATING REACTORS provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  2. Licensed operating reactors: Status summary report, Data as of June 30, 1987

    International Nuclear Information System (INIS)

    1987-07-01

    The Operating Units Status Report - Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  3. Licensed operating reactors: Status summary report, data as of 12-31-89

    International Nuclear Information System (INIS)

    1990-02-01

    The Operating Units Status Report - Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  4. Licensed operating reactors: Status summary report, data as of 9-30-87

    International Nuclear Information System (INIS)

    1987-10-01

    The OPERATING UNITS STATUS REPORT - LICENSED OPERATING REACTORS provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  5. Licensed operating reactors: Status summary report, Data as of 2-28-87

    International Nuclear Information System (INIS)

    1987-10-01

    The Operating Units Status Report- Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US. It is hoped the report is helpful to all agencies and individuals interested in maintaining an awareness of the US energy situation as a whole

  6. Status of long term operation of nuclear power plants in the US

    Energy Technology Data Exchange (ETDEWEB)

    Young, G., E-mail: gyoung4@entergy.com [Entergy Nuclear, License Renewal, New Orleans, LA (United States)

    2014-07-01

    As of early-2014, the U.S. Nuclear Regulatory Commission (NRC) has renewed the operating licenses for 73 of the 100 U.S. operating nuclear units, allowing for up to 60 years of safe operation. In addition, the NRC has license renewal applications under review for 18 more units and up to 8 additional units have announced plans to submit applications by 2018. This brings the total of renewed licenses and announced plans for renewal to 99% of the operating nuclear units in the U.S. In addition, by the end of 2014, there will be 38 nuclear plants that will have operated for more than 40 years and will be eligible to seek a subsequent license renewal to allow operation up to 80 years. Although some of the operating nuclear units are expected to shutdown due to economic issues, most of the remaining operating plant owners are keeping the option open for long term operation beyond 60 years. NRC and the U.S. nuclear industry have made significant progress in preparing the way for subsequent license renewal applications. This presentation covers the status of the U.S. license renewal process and issues being addressed for possible applications for subsequent renewals for up to 80 years of operation. (author)

  7. Licensed operating reactors: Status summary report data as of June 30, 1988

    International Nuclear Information System (INIS)

    1988-07-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  8. Licensed operating reactors: Status summary report: Data as of February 29, 1988

    International Nuclear Information System (INIS)

    1988-04-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  9. Licensed operating reactors. Status summary report, data as of April 30, 1982

    International Nuclear Information System (INIS)

    1982-05-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Management and Program Analysis, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  10. Licensed operating reactors. Status summary report as of February 29, 1984. Volume 8, No. 3

    International Nuclear Information System (INIS)

    1984-04-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Resource Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement (IE), from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  11. 2014 Highlights of Ferry Operations in the United States

    Science.gov (United States)

    2016-05-01

    Based on information provided by operators who responded to the 2014 National Census of Ferry Operators (NCFO), the Bureau of Transportation Statistics (BTS) conservatively estimates that ferries in the United States carried just over 115 million pas...

  12. Operational status of the transverse multibunch feedback system at Diamond

    International Nuclear Information System (INIS)

    Uzun, I.; Abbott, M.; Heron, M.T.; Morgan, A.F.D.; Rehm, G.

    2012-01-01

    A transverse multibunch feedback (TMBF) system is in operation at Diamond Light Source to damp coupled-bunch instabilities up to 250 MHz in both the vertical and horizontal planes. It comprises an in-house designed and built analogue front end combined with a Libera Bunch-by-Bunch feedback processor and output stripline kickers. FPGA-based feedback electronics is used to implement several diagnostic features in addition to the basic feedback functionality. This paper reports on the current operational status of the TMBF system along with its characteristics. Also discussed are operational diagnostic functionalities including continuous measurement of the betatron tune and chromaticity. (authors)

  13. Analysis of Serbian Military Riverine Units Capability for Participation in the United Nations Peacekeeping Operations

    Directory of Open Access Journals (Sweden)

    Slobodan Radojevic

    2017-06-01

    Full Text Available This paper analyses required personnel, training capacities and equipment for participation in the United Nations peacekeeping operations with the riverine elements. In order to meet necessary capabilities for engagement in United Nations peacekeeping operations, Serbian military riverine units have to be compatible with the issued UN requirements. Serbian Armed Forces have the potential to reach such requirements with the River Flotilla as a pivot for the participation in UN missions. Serbian Military Academy adopted and developed educational and training program in accordance with the provisions and recommendations of the IMO conventions and IMO model courses. Serbian Military Academy has opportunities for education and training military riverine units for participation in the United Nations peacekeeping operations. Moreover, Serbia has Multinational Operations Training Center and Peacekeeping Operations Center certified to provide selection, training, equipping and preparations of individuals and units to the United Nations multinational operations.

  14. UNITED STATES SPECIAL OPERATIONS FORCES IN AFRICA

    Science.gov (United States)

    2016-02-16

    hundreds of traditional African religions associated with the plethora of tribal groups as well as large populations of Muslims, primarily in the...engagement, and the complexities of the African continent, Special Operations Forces (SOF) are uniquely suited to further those interests. Additionally...protecting access to abundant strategic resources, fostering integration into the global economy, and empowering Africans and their partners to deal

  15. Operation status display and monitoring system for BWR nuclear power plant

    International Nuclear Information System (INIS)

    Wakabayashi, Yasuo; Hayakawa, Hiroyasu; Kawamura, Atsuo; Kaneda, Mitsunori.

    1982-01-01

    Lately, the development of the system has been made for BWR plants, which monitors the operating status not only in normal operation but also in abnormal state and also for plant safety. Recently, the improvement of man-machine interface has been tried through the practical use of technique which displays data collectively on a CRT screen relating them mutually. As one of those results, the practical use of an electronic computer and color CRT display for No. 1 unit in the Fukushima No. 2 Nuclear Power Station (2F-1), Tokyo Electric Power Co., is described. Also, new centralized control panels containing such systems were used for the 1100 MWe BWR nuclear power plants now under construction, No. 3 unit of the Fukushima No. 2 Power Station and No. 1 unit of Kashiwazaki-Kariwa Nuclear Power Station (2F-3 and K-1, respectively). The display and monitoring system in 2F-1 plant is the first one in which a computer and color CRTs were practically employed for a BWR plant in Japan, and already in commercial operation. The advanced operating status monitoring system, to which the result of evaluation of the above system was added, was incorporated in the new centralized control panels presently under production for 2F-3 and K-1 plants. The outline of the system, the functions of an electronic computer, plant operating status monitor, surveillance test guide, the automation of plant operation and auxiliary operation guide are reported for these advanced monitoring system. It was confirmed that these systems are useful means to improve the man-machine communication for plant operation minitoring. (Wakatsuki, Y.)

  16. Operational experience in the United Kingdom

    International Nuclear Information System (INIS)

    Gronow, W.S.

    1977-01-01

    In the UK there are 26 Magnox reactors and 4 AGRs operating on 11 licensed sites; a further 6 AGRs are under construction on 2 additional and one of the existing sites. The arrangements by which the Nuclear Installations Inspectorate, on behalf of the Health and Safety Executive, carries out its regulatory functions at operating nuclear power plants are described. The range of activities undertaken is described with special reference being made to the biennial shutdowns for approved maintenance and inspections which are required by conditions attached to the site licence. The other means by which the continuing safety of these power reactors is assured are explained and include the relationship with the licensee's own Nuclear Safety Committee, approved arrangements for modifications to plant systems or components which have importance for safety and long term reviews of safety aspects. (author)

  17. KSC facilities status and planned management operations. [for Shuttle launches

    Science.gov (United States)

    Gray, R. H.; Omalley, T. J.

    1979-01-01

    A status report is presented on facilities and planned operations at the Kennedy Space Center with reference to Space Shuttle launch activities. The facilities are essentially complete, with all new construction and modifications to existing buildings almost finished. Some activity is still in progress at Pad A and on the Mobile Launcher due to changes in requirements but is not expected to affect the launch schedule. The installation and testing of the ground checkout equipment that will be used to test the flight hardware is now in operation. The Launch Processing System is currently supporting the development of the applications software that will perform the testing of this flight hardware.

  18. Organizing for low cost space operations - Status and plans

    Science.gov (United States)

    Lee, C.

    1976-01-01

    Design features of the Space Transportation System (vehicle reuse, low cost expendable components, simple payload interfaces, standard support systems) must be matched by economical operational methods to achieve low operating and payload costs. Users will be responsible for their own payloads and will be charged according to the services they require. Efficient use of manpower, simple documentation, simplified test, checkout, and flight planning are firm goals, together with flexibility for quick response to varying user needs. Status of the Shuttle hardware, plans for establishing low cost procedures, and the policy for user charges are discussed.

  19. Licensed operating reactors: Status summary report, data as of October 31, 1988

    International Nuclear Information System (INIS)

    1988-12-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the Errata page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  20. Licensed operating reactors: Status summary report, data as of 07-31-88

    International Nuclear Information System (INIS)

    1988-09-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  1. Licensed operating reactors: Status summary report, data as of August 31, 1988

    International Nuclear Information System (INIS)

    1988-10-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  2. Licensed operating reactors: Status summary report, data as of May 31, 1988

    International Nuclear Information System (INIS)

    Schwartz, I.

    1988-07-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resource Management from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operation units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by the NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  3. Licensed operating reactors. Status summary report, data as of 3-31-82

    International Nuclear Information System (INIS)

    1982-04-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Management and Program Analysis, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the Errata page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  4. Licensed operating reactors status summary report, data as of April 30, 1989

    International Nuclear Information System (INIS)

    1989-06-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  5. Licensed operating reactors status summary report, data as of December 31, 1985. Volume 10, No. 1

    International Nuclear Information System (INIS)

    1986-01-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Resource Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the Errata page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  6. Unit costs of waste management operations

    International Nuclear Information System (INIS)

    Kisieleski, W.E.; Folga, S.M.; Gillette, J.L.; Buehring, W.A.

    1994-04-01

    This report provides estimates of generic costs for the management, disposal, and surveillance of various waste types, from the time they are generated to the end of their institutional control. Costs include monitoring and surveillance costs required after waste disposal. Available data on costs for the treatment, storage, disposal, and transportation of spent nuclear fuel and high-level radioactive, low-level radioactive, transuranic radioactive, hazardous, mixed (low-level radioactive plus hazardous), and sanitary wastes are presented. The costs cover all major elements that contribute to the total system life-cycle (i.e., ''cradle to grave'') cost for each waste type. This total cost is the sum of fixed and variable cost components. Variable costs are affected by operating rates and throughput capacities and vary in direct proportion to changes in the level of activity. Fixed costs remain constant regardless of changes in the amount of waste, operating rates, or throughput capacities. Key factors that influence cost, such as the size and throughput capacity of facilities, are identified. In many cases, ranges of values for the key variables are presented. For some waste types, the planned or estimated costs for storage and disposal, projected to the year 2000, are presented as graphics

  7. Fast reactor operation in the United States

    International Nuclear Information System (INIS)

    Smith, R.R.; Cissel, D.W.

    1978-01-01

    Of the many American facilities dedicated to fast reactor technology, six qualify as liquid-metal-cooled fast reactors. All of these satisfy the following criteria: an unmoderated neutron spectrum, highly enriched fuel material, substantial heat production, and the use of a liquid metal coolant. These include the following: EBR-I Clementine, LAMPRE, EBR-II, EFFBR, and SEFOR. Collectively, these facilities encompassed all of the more important features of liquid-metal-cooled fast reactor technology. Coolant types ranged from mercury in Clementine, to NaK in EBR-I, and sodium in the others. Fuels included enriched-uranium metallic alloys in EBR-I, EBR-II, and EFFBR; metallic plutonium in Clementine; molten plutonium alloy in LAMPRE; and a mixed UO 2 -PuO 2 ceramic in SEFOR. Heat removal techniques ranged from air-blast cooling in LAMPRE and SEFOR; steam-electrical generation in EBR-I, EBR-II, and EFFBR; to a mercury-to-water heat dump in Clementine. Operational experience with such diverse systems has contributed heavily to the U.S. Each of the six systems is described from the viewpoints of purpose, history, design, and operation. Attempts are made to limit descriptive material to the most important features and to refer the reader to a few select references if additional information is needed

  8. Licensed operating reactors. Status summary report data as of March 31, 1986. Volume 10, No. 4

    International Nuclear Information System (INIS)

    1986-05-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Resource Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States. The percentage computations, Items 20 through 24 in Section 2, the vendor capacity factors on page 1-7, and actual vs potential energy production on page 1-2 are computed using actual data for the period of consideration. The percentages listed in power generation on page 1-2 are computed as a arithmetic average. The factors for the life-span of each unit (the ''Cumulative'' column) are reported by the utility and are not entirely recomputed by NRC. Utility power production data is checked for consistency with previously submitted statistics. It is hoped this status report proves informative and helpful to all agencies and individuals interested in analyzing trends in the nuclear industry which might have safety implications, or in maintaining an awareness of the US energy situation as a whole

  9. Interim Status Closure Plan Open Burning Treatment Unit Technical Area 16-399 Burn Tray

    Energy Technology Data Exchange (ETDEWEB)

    Vigil-Holterman, Luciana R. [Los Alamos National Laboratory

    2012-05-07

    This closure plan describes the activities necessary to close one of the interim status hazardous waste open burning treatment units at Technical Area (TA) 16 at the Los Alamos National Laboratory (LANL or the Facility), hereinafter referred to as the 'TA-16-399 Burn Tray' or 'the unit'. The information provided in this closure plan addresses the closure requirements specified in the Code of Federal Regulations (CFR), Title 40, Part 265, Subparts G and P for the thermal treatment units operated at the Facility under the Resource Conservation and Recovery Act (RCRA) and the New Mexico Hazardous Waste Act. Closure of the open burning treatment unit will be completed in accordance with Section 4.1 of this closure plan.

  10. Analysis of operating reliability of WWER-1000 unit

    International Nuclear Information System (INIS)

    Bortlik, J.

    1985-01-01

    The nuclear power unit was divided into 33 technological units. Input data for reliability analysis were surveys of operating results obtained from the IAEA information system and certain indexes of the reliability of technological equipment determined using the Bayes formula. The missing reliability data for technological equipment were used from the basic variant. The fault tree of the WWER-1000 unit was determined for the peak event defined as the impossibility of reaching 100%, 75% and 50% of rated power. The period was observed of the nuclear power plant operation with reduced output owing to defect and the respective time needed for a repair of the equipment. The calculation of the availability of the WWER-1000 unit was made for different variant situations. Certain indexes of the operating reliability of the WWER-1000 unit which are the result of a detailed reliability analysis are tabulated for selected variants. (E.S.)

  11. Evaluation of risk management status for Croatian logistic operators

    Directory of Open Access Journals (Sweden)

    Diana BOŽIĆ

    2010-01-01

    Full Text Available Understanding organisational risks makes possible to control them and to change them into organisational strengths. Being known as “measure of uncertainty” in the business process, the risk is the uncertainty of achieving the organizational objectives. It may involve positive or negative consequences. There is a level of uncertainty in every supply chain while operating transportation and warehousing, positioning on the market, developing customer support, reducing cycle times or cutting costs. Therefore, the risk assessment should be one of the main tasks for any supply chain management team. It is required to develop formal risk assessment procedures, to identify the potential impacts to the supply chain operations and to develop a set of contingency plans to mitigate risks. This paper deals with supply chain risk assessment methodology, outlining the present risk management status of Croatian logistic operators.

  12. An Appraisal Of The Operation And Management Of Unit Trust ...

    African Journals Online (AJOL)

    An Appraisal Of The Operation And Management Of Unit Trust Schemes In Nigeria. ... Open Access DOWNLOAD FULL TEXT ... instead of being invested in shares or in money market instruments as a result of widespread financial illiteracy.

  13. Initial startup and operations of Yonggwang Units 3 and 4

    International Nuclear Information System (INIS)

    Collier, T.J.; Chari, D.R.; Kiraly, F.

    1996-01-01

    A significant milestone in the nuclear power industry was achieved in 1995, when Yonggwang (YGN) Units 3 and 4 were accepted into in commercial operation by Korea Electric Power Corporation (KEPCO). YGN Unit 3 was accepted into commercial operation on March 31, 1995, the original date established during project initiation. YGN Unit 4 was accepted into operation on January 1, 1996, 3 months ahead of schedule. Each YGN unit produces approximately 1,050 Mwe and supplies approximately ten percent of the total electric power demand in the Republic of Korea (ROK). The overall plant efficiency is approximately 37% which is at least 1% higher than most nuclear units. Since achieving commercial operation, YGN Unit 3 has operated at essentially full power which has resulted in an annual performance rate in excess of 85%. YGN Unit 3 is the first of six pressurized water reactors which are currently under design and construction in the ROK and serves as the reference design for the Korean Standard Nuclear Power Plant program. Both YGN Units 3 and 4 include a System 800 Nuclear Steam Supply System (NSSS). The NSSS is rated at 2,815 Mwth and is the ABB-CE standard design. The design includes numerous advanced design features which enhance plant safety, performance and operability. A well executed startup test program was successfully completed on both units prior to commercial operation. A summary of the YGN NSSS design features, the startup test program and selected test results demonstrating the performance of those features are presented in this paper

  14. Stability Analysis for Operation of DG Units in Smart Grids

    DEFF Research Database (Denmark)

    Pouresmaeil, Edris; Shaker, Hamid Reza; Mehrasa, Majid

    2015-01-01

    This paper presents a multifunction control strategy for the stable operation of Distributed Generation (DG) units during grid integration. The proposed control model is based on Direct Lyapunov Control (DLC) theory and provides a stable region for the appropriate operation of DG units during grid....... Application of this concept can guarantee to reduce the stress on the grid during the energy demand peak. Simulation results are presented to demonstrate the proficiency and performance of the proposed DLC technique in DG technology....

  15. The status of contractors workers operating in US nuclear power plants

    International Nuclear Information System (INIS)

    Lochard, J.

    1985-01-01

    The status of contractors operating in PWRs in the United States is described. The statistics concerning the trends of both the individual and collective exposures of these workers were analysed as well as their main demographic and sociological features. The data relative to the particular group of ''transient'' workers, i.e. those operating in several different power plants during the same year were also examined. The results presented show that the dosimetric and sociological profiles of contractors' workers, in US power plants, do not differ fundamentally from that of permanent workers [fr

  16. Eielson Air Force Base Operable Unit 2 baseline risk assessment

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, R.E.; Jarvis, T.T.; Jarvis, M.R.; Whelan, G.

    1994-10-01

    Operable Unit 2 at Eielson Air Force Base (AFB) near Fairbanks, is one of several operable units characterized by petroleum, oil, and lubricant contamination, and by the presence of organic products floating at the water table, as a result of Air Force operations since the 1940s. The base is approximately 19,270 acres in size, and comprises the areas for military operations and a residential neighborhood for military dependents. Within Operable Unit 2, there are seven source areas. These source areas were grouped together primarily because of the contaminants released and hence are not necessarily in geographical proximity. Source area ST10 includes a surface water body (Hardfill Lake) next to a fuel spill area. The primary constituents of concern for human health include benzene, toluene, ethylbenzene, and xylenes (BTEX). Monitored data showed these volatile constituents to be present in groundwater wells. The data also showed an elevated level of trace metals in groundwater.

  17. Preliminary study on psychosomatic status of nuclear power plant operators

    International Nuclear Information System (INIS)

    Bi Jinling; Liu Yulong; Li Yuan; Bian Huahui; Sun Yiling; Qiu Mengyue; Liu Chunfeng

    2011-01-01

    Objective: To understand the operators' psychosomatic health status in nuclear power plant; and provide the scientific basis of measures for preventing and reducing mental disorders in operators. Methods: The Psychosomatic Health Battery (PSHB) was used to assess the psychosomatic health status in 109 operators who were random selected from Qinshan nuclear power plant, etc. They were tested from lie, emotional stability, liveliness, tension, apprehension, mental health, such as psychopathic deviatesuch 7 personality traits. Results: Lie < 8, all inspected groups were normal. Psychopathic deviate: 98.2% for normal group 0.9% for both of groups occurred possible mental health problems and confirmed mental health problems; Mental health: 80.7% (88/109) for fine mental health ones, 29.4% (32/109) for those with excellent mental health, 51.4% (56/109) for good mental health ones, 13.8% (15/109) for general mental health ones, 5.5% (6/109) for poor mental health ones. Age factor could influence the mean values of the factors of apprehension, tension, mental health and psychopathic deviate. Correlation analysis showed that there was a correlation between tension and psychopathic deviate (r=0.664, P<0.01), and the other correlation coefficient was between apprehension and mental health (r=-0.789, P<0.01). Conclusions: There is an excellent condition of psychosomatic health in most of the operators, however, there are still a very small percentage of psychosomatic disorders among these operators, to improve the quality of their psychosomatic health, psychological counseling should be particularly strengthened to those with problems of psychosomatic health. (authors)

  18. Operational safety analysis status of Novi Han repository

    International Nuclear Information System (INIS)

    Boiadjiev, A.

    2000-01-01

    This article presents the status of the safety studies and activities related to Novi Han repository. The case of this facility is such that no clear boundary exists between post-closure safety assessment and operational safety assessment. The major findings of these activities are given. The Safety Analysis Report (SAR) for Novi Han repository is developed by Risk Engineering Ltd. under a contract with the Committee on the Use of Atomic Energy for Peaceful Purposes. The general structure and main conclusions and recommendations of the SAR are presented. (author)

  19. Current Status of Operation and Management of Dental School Clinics.

    Science.gov (United States)

    Reinhardt, John W

    2017-08-01

    This article summarizes the current status of the operation and management of dental school clinics as schools strive to provide excellent patient-centered care in an environment that is educationally sound, efficient, and financially strong. Clinical education is a large component of dental education and an area in which many dental schools have an opportunity to enhance revenue. Clinical efficiencies and alternative models of clinical education are evolving in U.S. dental schools, and this article describes some of those evolutionary changes. This article was written as part of the project "Advancing Dental Education in the 21 st Century."

  20. Feasibility study report for the 200-BP-1 operable unit

    International Nuclear Information System (INIS)

    1993-06-01

    This feasibility study examines a range of alternatives and provides recommendations for selecting a preferred alternative for remediating contamination at the 200-BP-1 operable unit. The 200-BP-1 operable unit is located in the center of the Hanford Site along the northern boundary of the 200 East Area. The 241-BY Tank Farm is located immediately to the south of the operable unit. 200-BP-1 is a source operable unit with contaminated soils associated primarily with nine inactive cribs (known as the 216-B cribs). These cribs were used for disposal of low-level radioactive liquid waste from U Plant uranium recovery operations, and waste storage tank condensate from the adjacent 241-BY Tank Farm. The cribs used for disposal of U Plant waste were in operation from 1955--1965, and the cribs used for disposal of tank condensate were in operation from 1965--1975. In addition to the cribs, four unplanned releases of radioactive materials have occurred within the operable unit. Contaminated surface soils associated with the unplanned releases have been consolidated over the cribs and covered with clean soil to reduce contaminant migration and exposure. Discharge of wastes to the cribs has resulted in soil and groundwater contamination. The groundwater is being addressed as part of the 200 East Aggregate Area, groundwater operable unit. Contaminated soils at the site can be categorized by the types of contaminants, their distribution in the soil column, and the risk posed by the various potential exposure pathways. Below the clean soil cover, the near surface soils contain low-levels of contamination with cesium-137, radium-226, strontium-90, thorium-228, and uranium. The lifetime incremental cancer risk associated with these soils if they were exposed at the surface is 9x10 -5

  1. Feasibility study report for the 200-BP-1 operable unit

    International Nuclear Information System (INIS)

    1994-01-01

    This feasibility study (FS) examines a range of alternatives and provides recommendations for selecting a preferred altemative for remediating contamination at the 200-BP-1 operable unit. The 200-BP-1 operable unit is located in the center of the Hanford Site along the northern boundary of the 200 East Area. The 241-BY Tank Farm is located immediately to the south of the operable unit. 200-BP-1 is a source operable unit with contaminated soils associated primarily with nine inactive cribs (known as the 216-B cribs). These cribs were used for disposal of low-level radioactive liquid waste from U Plant uranium recovery operations, and waste storage tank condensate from the adjacent 241-BY Tank Farm. The cribs used for disposal of U Plant waste were in operation from 1955--1965, and the cribs used for disposal of tank condensate were in operation from 1965-1975. In addition to the cribs, four unplanned releases of radioactive materials have occurred within the operable unit. Contaminated surface soils associated with the unplanned releases have been consolidated over the cribs and covered with clean soil to reduce contaminant migration and exposure. Discharge of wastes to the cribs has resulted in soil and groundwater contamination. The groundwater is being addressed as part of the 200 East Aggregate Area groundwater operable unit. Contaminated soils at the site can be categorized by the types of contaminants, their distribution in the soil column, and the risk posed by the various potential exposure pathways. Below the clean soil cover, the near surface soils contain low-:levels of contamination with cesium-137, radium-226, strontium-90, thorium-228 and uranium. The lifetime incremental cancer risk associated with these soils if they were exposed at the surface is 9 x 10 5

  2. Feasibility study report for the 200-BP-1 operable unit

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    This feasibility study examines a range of alternatives and provides recommendations for selecting a preferred alternative for remediating contamination at the 200-BP-1 operable unit. The 200-BP-1 operable unit is located in the center of the Hanford Site along the northern boundary of the 200 East Area. The 241-BY Tank Farm is located immediately to the south of the operable unit. 200-BP-1 is a source operable unit with contaminated soils associated primarily with nine inactive cribs (known as the 216-B cribs). These cribs were used for disposal of low-level radioactive liquid waste from U Plant uranium recovery operations, and waste storage tank condensate from the adjacent 241-BY Tank Farm. The cribs used for disposal of U Plant waste were in operation from 1955--1965, and the cribs used for disposal of tank condensate were in operation from 1965--1975. In addition to the cribs, four unplanned releases of radioactive materials have occurred within the operable unit. Contaminated surface soils associated with the unplanned releases have been consolidated over the cribs and covered with clean soil to reduce contaminant migration and exposure. Discharge of wastes to the cribs has resulted in soil and groundwater contamination. The groundwater is being addressed as part of the 200 East Aggregate Area, groundwater operable unit. Contaminated soils at the site can be categorized by the types of contaminants, their distribution in the soil column, and the risk posed by the various potential exposure pathways. Below the clean soil cover, the near surface soils contain low-levels of contamination with cesium-137, radium-226, strontium-90, thorium-228, and uranium. The lifetime incremental cancer risk associated with these soils if they were exposed at the surface is 9{times}10{sup {minus}5}.

  3. Automating ATLAS Computing Operations using the Site Status Board

    CERN Document Server

    Andreeva, J; The ATLAS collaboration; Campana, S; Di Girolamo, A; Espinal Curull, X; Gayazov, S; Magradze, E; Nowotka, MM; Rinaldi, L; Saiz, P; Schovancova, J; Stewart, GA; Wright, M

    2012-01-01

    The automation of operations is essential to reduce manpower costs and improve the reliability of the system. The Site Status Board (SSB) is a framework which allows Virtual Organizations to monitor their computing activities at distributed sites and to evaluate site performance. The ATLAS experiment intensively uses SSB for the distributed computing shifts, for estimating data processing and data transfer efficiencies at a particular site, and for implementing automatic exclusion of sites from computing activities, in case of potential problems. ATLAS SSB provides a real-time aggregated monitoring view and keeps the history of the monitoring metrics. Based on this history, usability of a site from the perspective of ATLAS is calculated. The presentation will describe how SSB is integrated in the ATLAS operations and computing infrastructure and will cover implementation details of the ATLAS SSB sensors and alarm system, based on the information in SSB. It will demonstrate the positive impact of the use of SS...

  4. STS operations planning - Current status and outlook for the future

    Science.gov (United States)

    Lee, C. M.

    1981-01-01

    Consideration is given to the status of Space Shuttle operations planning and outlook for the period 1982-94, with some speculations on Shuttle-related space operations early in the next century. Attention is given to the evolution of Shuttle payload capabilities over the next five years. The following list of near-earth environment factors to be exploited by the Space Shuttle is given: (1) easy control of gravity; (2) absence of atmosphere; (3) a comprehensive view of the earth's surface and atmosphere; (4) isolation of hazardous processes from earth biosphere; (5) freely available light, heat and photovoltaic power; (6) an infinite natural reservoir for the disposal of radioactive waste products; and (7) a super-cold heat sink.

  5. 200-UP-2 Operable Unit technical baseline report

    International Nuclear Information System (INIS)

    Deford, D.H.

    1991-02-01

    This report is prepared in support of the development of a Remedial Investigation/Feasibility Study (RI/FS) Work Plan for the 200-UP-2 Operable Unit by EBASCO Environmental, Incorporated. It provides a technical baseline of the 200-UP-2 Operable Unit and results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (Westinghouse Hanford). The 200-UP-2 Operable Unit Technical Baseline Report is based on review and evaluation of numerous Hanford Site current and historical reports, Hanford Site drawings and photographs and is supplemented with Hanford Site inspections and employee interviews. No field investigations or sampling were conducted. Each waste site in the 200-UP-2 Operable Unit is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. The 200-UP-2 Operable Unit consists of liquid-waste disposal sites in the vicinity of, and related to, U Plant operations in the 200 West Area of the Hanford Site. The ''U Plant'' refers to the 221-U Process Canyon Building, a chemical separations facility constructed during World War 2. It also includes the Uranium Oxide (UO 3 ) Plant, which was constructed at the same time and, like the 221-U Process Canyon Building, was later converted for other missions. Waste sites in the 200-UP-2 Operable Unit are associated with the U Plant Uranium Metal Recovery Program mission that occurred between 1952 and 1958 and the UO 3 Plant's ongoing uranium oxide mission and include one or more cribs, reverse wells, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, waste vaults, and the lines and encasements that connect them. 11 refs., 1 tab

  6. Operation and Maintenance Plan for the 300-FF-5 Operable Unit

    International Nuclear Information System (INIS)

    Singleton, K.M.

    1996-09-01

    This document is the operation and maintenance plan for the 300-FF-5 groundwater operable unit. The purpose of this plan is to identify tasks necessary to verify the effectiveness of the selected alternative. This plan also describes the monitoring program and administrative tasks that will be used as the preferred alternative for the remediation of groundwater in the 300-FF-5 Operable Unit. The preferred alternative selected for remediation of groundwater consists of institutional controls

  7. Status of reactor shielding research in the United States

    International Nuclear Information System (INIS)

    Bartine, D.E.

    1983-01-01

    Shielding research in the United States continues to place emphasis on: (1) the development and refinement of shielding design calculational methods and nuclear data; and (2) the performance of confirmation experiments, both to evaluate specific design concepts and to verify specific calculational techniques and input data. The successful prediction of the radiation levels observed within the now-operating Fast Flux Test Facility (FFTF) has demonstrated the validity of this two-pronged approach, which has since been applied to US fast breeder reactor programs and is now being used to determine radiation levels and possible further shielding needs at operating light water reactors, especially under accident conditions. A similar approach is being applied to the back end of the fission fuel cycle to verify that radiation doses at fuel element storage and transportation facilities and within fuel reprocessing plants are kept at acceptable levels without undue economic penalties

  8. Holistic approach to multi-unit site risk assessment: Status and Issues

    International Nuclear Information System (INIS)

    Kim, Inn Seock; Jang, Mi Suk; Kim, Seoung Rae

    2017-01-01

    The events at the Fukushima Daiichi Nuclear Power Station in March 2011 point out, among other matters, that concurrent accidents at multiple units of a site can occur in reality. Although site risk has been deterministically considered to some extent in nuclear power plant siting and design, potential occurrence of multi-unit accident sequences at a site was not investigated in sufficient detail thus far in the nuclear power community. Therefore, there is considerable worldwide interest and research effort directed toward multi-unit site risk assessment, especially in the countries with high-density nuclear-power-plant sites such as Korea. As the technique of probabilistic safety assessment (PSA) has been successfully applied to evaluate the risk associated with operation of nuclear power plants in the past several decades, the PSA having primarily focused on single-unit risks is now being extended to the multi-unit PSA. In this paper we first characterize the site risk with explicit consideration of the risk associated with spent fuel pools as well as the reactor risks. The status of multi-unit risk assessment is discussed next, followed by a description of the emerging issues relevant to the multi-unit risk evaluation from a practical standpoint

  9. Holistic approach to multi-unit site risk assessment: Status and Issues

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Inn Seock; Jang, Mi Suk; Kim, Seoung Rae [Nuclear Engineering Service and Solution Company (NESS), Daejeon Business Agency, Daejeon (Korea, Republic of)

    2017-03-15

    The events at the Fukushima Daiichi Nuclear Power Station in March 2011 point out, among other matters, that concurrent accidents at multiple units of a site can occur in reality. Although site risk has been deterministically considered to some extent in nuclear power plant siting and design, potential occurrence of multi-unit accident sequences at a site was not investigated in sufficient detail thus far in the nuclear power community. Therefore, there is considerable worldwide interest and research effort directed toward multi-unit site risk assessment, especially in the countries with high-density nuclear-power-plant sites such as Korea. As the technique of probabilistic safety assessment (PSA) has been successfully applied to evaluate the risk associated with operation of nuclear power plants in the past several decades, the PSA having primarily focused on single-unit risks is now being extended to the multi-unit PSA. In this paper we first characterize the site risk with explicit consideration of the risk associated with spent fuel pools as well as the reactor risks. The status of multi-unit risk assessment is discussed next, followed by a description of the emerging issues relevant to the multi-unit risk evaluation from a practical standpoint.

  10. Licensed operating reactors. Status summary report, data as of October 31, 1985. Volume 9, No. 11

    International Nuclear Information System (INIS)

    1985-12-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Resource Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the errata page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States. The percentage computations, Items 20 through 24 in Section 2, the vendor capacity factors on page 1-7, and actual vs potential energy production on page 1-2 are computed using actual data for the period of consideration. The percentages listed in power generation on page 1-2 are computed as an arithmetic average. The factors for the life-span of each unit (the ''Cumulative'' column) are reported by the utility and are not entirely re-computed by NRC. Utility power production data is checked for consistency with previously submitted statistics

  11. Present status of Tomari No.3 unit construction and efforts for preventing global warming

    International Nuclear Information System (INIS)

    Ouchi, Tamotsu; Sakai, Ichiro; Makino, Takeshi

    2009-01-01

    Hokkaido Electric Power Company, Inc. (HEPCO) supplies electricity to almost all area of Hokkaido. Its service area accounts for about one-fifth of Japan's area, on the other hand, the population of the service area only accounts for 4.4% of the nation. This means Hokkaido's nature is precious, and one of HEPCO's missions is to protect such environment, with providing stable electricity. Therefore, nuclear power, which does not emit greenhouse effect gas for generation, is becoming more important. HEPCO's operating nuclear power stations are Tomari No.1 unit and No.2 unit. Their generation capacity is 579 MW respectively. Now, No.3 unit is under construction. Its generation capacity is 912 MW and it will be operational in December 2009. In Hokkaido, about one fourth of electricity is now produced by nuclear power, however, after Tomari No.3 is completed, more than 40% of electricity will be produced by nuclear. So, Tomari No.3 unit will contribute stable supply of electricity in the first half of 21st century and prevent global warming in Hokkaido. This paper describes the present status of Tomari No.3 unit construction with major specifications and our efforts to prevent global warming. (author)

  12. Present status of Tomari No.3 unit construction and efforts for preventing global warming

    International Nuclear Information System (INIS)

    Ouchi, Tamotsu

    2008-01-01

    Hokkaido Electric Power Company, Inc. (HEPCO) supplies electricity to almost all area of Hokkaido. Its service area accounts for about one-fifth of Japan's area, on the other hand, the population of the service area only accounts for 4.4% of the nation. This means Hokkaido's nature is precious, and one of HEPCO's missions is to protect such environment, with providing stable electricity. Therefore, nuclear power, which does not emit greenhouse effect gas for generation, is becoming more important. HEPCO's operating nuclear power stations are Tomari No.1 unit and No.2 unit. Their generation capacity is 579 MW respectively. Now, No.3 unit is under construction. Its generation capacity is 912 MW and it will be operational in December 2009. In Hokkaido, about one fourth of electricity is now produced by nuclear power, however, after Tomari No.3 is completed, about 40% of electricity will be produced by nuclear. So, Tomari No.3 unit will contribute stable supply of electricity in the first half of 21st century and prevent global warming in Hokkaido. This paper describes the present status of Tomari No.3 unit construction with major specifications and our efforts to prevent global warming. (author)

  13. Status of nuclear engineering education in the United States

    International Nuclear Information System (INIS)

    Brown, G.J.

    2000-01-01

    Nuclear engineering education in the United States is reflective of the perceived health of the nuclear electric power industry within the country. Just as new commercial reactor orders have vanished and some power plants have shut down, so too have university enrollments shrunk and research reactors closed. This decline in nuclear trained specialists and the disappearance of the nuclear infrastructure is a trend that must be arrested and reversed if the United States is to have a workforce capable of caring for a nuclear power industry to not only meet future electric demand but to ensure that the over 100 existing plants, their supporting facilities and their legacy in the form of high level waste and facility clean-up are addressed. Additionally, the United States has an obligation to support and maintain its nuclear navy and other defence needs. And, lastly, if the United States is to have a meaningful role in the international use of nuclear power with regard to safety, non-proliferation and the environment, then it is imperative that the country continues to produce world-class nuclear engineers and scientists by supporting nuclear engineering education at its universities. The continued support of the federal government. and industry for university nuclear engineering and nuclear energy research and development is essential to sustain the nuclear infrastructure in the United States. Even with this support, and the continued excellent operation of the existing fleet of nuclear electric power plants, it is conceivable that nuclear engineering as an academic discipline may fall victim to poor communications and a tarnished public image. What is needed is a combination of federal and industrial support along with the creativity of the universities to expand their offerings to include more than power production. The objective is a positive message on careers in nuclear related fields, and recognition of the important role of nuclear energy in meeting the country

  14. Analysis on Isolation Condenser Operation by Fukushima Daiichi Unit 1 Operators

    International Nuclear Information System (INIS)

    Kim, Man Cheol

    2014-01-01

    Fukushima Daiichi nuclear accident resulted in the core damage in three reactors and the release of considerable amount of radioactive material to the environment, not to mention significant social impact and anti-nuclear atmosphere all around the world. This paper provides a review of the findings related to shift operators' operation of the isolation condenser in Unit 1 to examine shift operators' response to the situation. Based on the review of the findings, a situation assessment model was developed to analyze shift operators' understanding on whether core cooling was successfully performed in Unit 1 through the operation of isolation condenser. It was found that lack of information could be one of the main causes for the failure in core cooling by the IC in Unit 1. It is also recommended that the differences in the mathematical model for the situation assessment and that of the real operator need to be further investigated

  15. Analysis on Isolation Condenser Operation by Fukushima Daiichi Unit 1 Operators

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Man Cheol [Chungang University, Seoul (Korea, Republic of)

    2014-08-15

    Fukushima Daiichi nuclear accident resulted in the core damage in three reactors and the release of considerable amount of radioactive material to the environment, not to mention significant social impact and anti-nuclear atmosphere all around the world. This paper provides a review of the findings related to shift operators' operation of the isolation condenser in Unit 1 to examine shift operators' response to the situation. Based on the review of the findings, a situation assessment model was developed to analyze shift operators' understanding on whether core cooling was successfully performed in Unit 1 through the operation of isolation condenser. It was found that lack of information could be one of the main causes for the failure in core cooling by the IC in Unit 1. It is also recommended that the differences in the mathematical model for the situation assessment and that of the real operator need to be further investigated.

  16. Status of United States civilian waste management program

    International Nuclear Information System (INIS)

    Lawrence, M.J.

    1984-01-01

    The Nuclear Waste Policy Act of 1982 confirms the Federal responsibility for nuclear waste management and provides for unprecedented involvement by States, Indian tribes and the public. The Act provides a comprehensive framework for disposing of spent nuclear fuel and high-level radioactive wastes of domestic origin generated by civilian nuclear power reactors. It establishes detailed schedules and procedures for selecting and developing geologic repositories; provides a mechanism for financing the cost of disposal; and sets forth other provisions relating to nuclear waste disposal. The other provisions of the Act include provision for a user-financed federal interim storage facility with time and quantity limitations, as well as strict Nuclear Regulatory Commission-prescribed eligibility criteria; a proposal for a Federally-owned and operated monitored retrievable storage (MRS) facility for the interim period prior to operation of a permanent repository; and provision for a Test and Evaluation Facility (TEF). This paper centers on the schedule and current status and siting of the first two geologic repositories

  17. Operational behaviour of WWER nuclear power units after Chernobyl accident

    International Nuclear Information System (INIS)

    Milivojevic, S.; Spasojevic, D.

    2000-01-01

    The indicators of effectiveness of WWER operation, in 1987-1998 were analyzed. For three groups of nuclear units (WWER, NPP Kozloduy, NPP Paks), the trends of Indicators flow were established. The comparative analysis of forced outage rate, and load factor of WWERs and nuclear units all in the world was carried out; it gives the general picture of accident influence on the states and the relations of these indicators in considered period (author)

  18. On Point: The United States Army in Operation Iraqi Freedom

    Science.gov (United States)

    2004-01-01

    to retain operational context. Moreover, times noted in the text have been adjusted from Greenwich Mean Time (“ Zulu ”) to local Kuwait time (+ 3...TF 1-64 AR unit history is composed of short narratives for each subordinate unit. Most cite times in zulu . 34. Ibid. 35. Ibid. Numbers of enemy...places in the world. Inside the city cemetery is the Tomb of Ali, son-in-law and cousin to Mohammed and founder of the Shiite sect. Coalition leaders

  19. 200-BP-5 operable unit Technical Baseline report

    International Nuclear Information System (INIS)

    Jacques, I.D.; Kent, S.K.

    1991-10-01

    This report supports development of a remedial investigation/feasibility study work plan for the 200-BP-5 operable unit. The report summarizes baseline information for waste sites and unplanned release sites located in the 200-BP-5 operable unit. The sites were investigated by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (Westinghouse Hanford). The investigation consisted of review and evaluation of current and historical Hanford Site reports, drawings, and photographs, and was supplemented with recent inspections of the Hanford Site and employee interviews. No field investigations or sampling were conducted

  20. Implementation of Active Learning Method in Unit Operations II Subject

    OpenAIRE

    Ma'mun, Sholeh

    2018-01-01

    ABSTRACT: Active Learning Method which requires students to take an active role in the process of learning in the classroom has been applied in Department of Chemical Engineering, Faculty of Industrial Technology, Islamic University of Indonesia for Unit Operations II subject in the Even Semester of Academic Year 2015/2016. The purpose of implementation of the learning method is to assist students in achieving competencies associated with the Unit Operations II subject and to help in creating...

  1. PROCESS OF CHANGES OF MAINTENANCE-FREE ONBOARD SYSTEM OPERATIONAL STATUS BETWEEN SCHEDULED MAINTENANCES

    Directory of Open Access Journals (Sweden)

    Andrey Mikhaylovich Bronnikov

    2017-01-01

    Full Text Available In this article the authors consider the problem of simulating the process of a maintenance-free between scheduled maintenance aircraft system operational status changes, which failure during the flight leads to the disaster. On-board equipment with automatic self-repair between routine maintenance in the event the components fail is called maintenance-free. During operation, onboard equipment accumulates failures maintaining its functions with a safety level not lower than the required minimum. Trouble shooting is carried out either at the end of between-maintenance period (as a rule, or after the failure, which led to the functions disorder or to the decrease below the target level of flight safety (as an exception. The system contains both redundant and nonredundant units and elements with the known failure rates. The system can be in one of the three states: operable, extreme, failed. The excessive redundant elements allow the system to accumulate failures which are repaired during the routine maintenance. The process of system operational status changes is described with the discrete-continuous model in the flight time. Basing on the information about the probabilities of the on-board equipment being in an operable, extreme or failed state, it is possible to calculate such complex efficiency indicators as the average loss of sorties, the average operating costs, the expected number of emergency recovery operations and others. Numerical studies have been conducted to validate the proposed model. It is believed that maintenance work completely updates the system. The analysis of these indicators will allow to evaluate the maintenance-free aircraft equipment operation efficiency, as well as to make an effectiveness comparison with other methods of technical operation. The model can be also used to assess the technical operation systems performance. The model can be used to optimize the period between maintenance.

  2. Status of fast breeder reactor development in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Rosen, S

    1979-07-01

    This document was prepared by the Office of the Program Director for Nuclear Energy, U.S. Department of Energy (USDOE). It sets forth the status and current activities for the development of fast breeder technology in the United States. In April 1977 the United States announced a change in its nuclear energy policy. Concern about the potential for the proliferation of nuclear weapons capability emerged as a major issue in considering whether to proceed with the development, demonstration and eventual deployment of breeder reactor energy systems. Plutonium recycle and the commercialization of the fast breeder were deferred indefinitely. This led to a reorientation of the nuclear fuel cycle program which was previously directed toward the commercialization of fuel reprocessing and plutonium recycle to the investigation of a full range of alternative fuel cycle technologies. Two major system evaluation programs, the Nonproliferation Alternative Systems Assessment Program (NASAP), which is domestic, and the International Nuclear Fuel Cycle Evaluation (INFCE), which is international, are assessing the nonproliferation advantages and other characteristics of advanced reactor concepts and fuel cycles. These evaluations will allow a decision in 1981 on the future direction of the breeder program. In the interim, the technologies of two fast breeder reactor concepts are being developed: the Liquid Metal Fast Breeder Reactor (LMFBR) and the Gas Cooled Fast Reactor (CFR). The principal goals of the fast breeder program are: LMFBR - through a strong R and D program, consistent with US nonproliferation objectives and anticipated national electric energy requirements, maintain the capability to commit to a breeder option; investigate alternative fuels and fuel cycles that might offer nonproliferation advantages; GCFR - provide a viable alternative to the LMFBR that will be consistent with the developing U.S. nonproliferation policy; provide GCFR technology and other needed

  3. Adaptation of Professional Skills in the Unit Operations Laboratory

    Science.gov (United States)

    Rende, Deniz; Rende, Sevinc; Baysal, Nihat

    2012-01-01

    We introduce the design of three consecutive unit operations laboratory (UOL) courses that retain the academic rigor of the course while incorporating skills essential for professional careers, such as ability to propose ideas, develop practical solutions, participate in teamwork, meet deadlines, establish communication between technical support…

  4. Pressure Swing Adsorption in the Unit Operations Laboratory

    Science.gov (United States)

    Ganley, Jason

    2018-01-01

    This paper describes a student laboratory in the Unit Operations Laboratory at the Colorado School of Mines: air separation by pressure swing adsorption. The flexibility of the system enables students to study the production of enriched nitrogen or oxygen streams. Automatic data acquisition permits the study of cycle steps and performance.…

  5. Basewide Groundwater Operable Unit. Groundwater Operable Unit Remedial Investigation/Feasibility Study Report. Volume 1

    Science.gov (United States)

    1994-06-01

    units would be reused in the remedy. Contingency measures to be included in the remedy are potential metals removal prior to water end use, potential...onbase reuse of a portion of the water, and wellhead treatment on offbase supply wells. The contingency measures will only be implemented if necessary...94 LEGEND Ouatmar aluvi dposts agua Frmaion(cosoldatd aluval epoits W iead rdetilnsMhte omtin(neitccnlmeae ansoe9ndkeca F 70 Quvatei-lernayalvu e pk

  6. Thunderstorm Algorithm for Determining Unit Commitment in Power System Operation

    Directory of Open Access Journals (Sweden)

    Arif Nur Afandi

    2016-12-01

    Full Text Available Solving the unit commitment problem is an important task in power system operation for deciding a balanced power production between various types of generating units under technical constraints and environmental limitations. This paper presents a new intelligent computation method, called the Thunderstorm Algorithm (TA, for searching the optimal solution of the integrated economic and emission dispatch (IEED problem as the operational assessment for determining unit commitment. A simulation using the IEEE-62 bus system showed that TA has smooth convergence and is applicable for solving the IEED problem. The IEED’s solution is associated with the total fuel consumption and pollutant emission. The proposed TA method seems to be a viable new approach for finding the optimal solution of the IEED problem.

  7. Optimal operation of cogeneration units. State of art and perspective

    International Nuclear Information System (INIS)

    Polimeni, S.

    2001-01-01

    Optimal operation of cogeneration plants and of power plant fueling waste products is a complex challenge as they have to fulfill, beyond the contractual obligation of electric power supply, the constraints of supplying the required thermal energy to the user (for cogeneration units) or to burn completely the by-products of the industrial complex where they are integrated. Electrical power market evolution is pushing such units to a more and more volatile operation caused by uncertain selling price levels. This work intends to pinpoint the state of art in the optimization of these units outlining the important differences among the different size and cycles. The effect of the market liberalization on the automation systems and the optimization algorithms will be discussed [it

  8. Centrifugal microfluidic platforms: advanced unit operations and applications.

    Science.gov (United States)

    Strohmeier, O; Keller, M; Schwemmer, F; Zehnle, S; Mark, D; von Stetten, F; Zengerle, R; Paust, N

    2015-10-07

    Centrifugal microfluidics has evolved into a mature technology. Several major diagnostic companies either have products on the market or are currently evaluating centrifugal microfluidics for product development. The fields of application are widespread and include clinical chemistry, immunodiagnostics and protein analysis, cell handling, molecular diagnostics, as well as food, water, and soil analysis. Nevertheless, new fluidic functions and applications that expand the possibilities of centrifugal microfluidics are being introduced at a high pace. In this review, we first present an up-to-date comprehensive overview of centrifugal microfluidic unit operations. Then, we introduce the term "process chain" to review how these unit operations can be combined for the automation of laboratory workflows. Such aggregation of basic functionalities enables efficient fluidic design at a higher level of integration. Furthermore, we analyze how novel, ground-breaking unit operations may foster the integration of more complex applications. Among these are the storage of pneumatic energy to realize complex switching sequences or to pump liquids radially inward, as well as the complete pre-storage and release of reagents. In this context, centrifugal microfluidics provides major advantages over other microfluidic actuation principles: the pulse-free inertial liquid propulsion provided by centrifugal microfluidics allows for closed fluidic systems that are free of any interfaces to external pumps. Processed volumes are easily scalable from nanoliters to milliliters. Volume forces can be adjusted by rotation and thus, even for very small volumes, surface forces may easily be overcome in the centrifugal gravity field which enables the efficient separation of nanoliter volumes from channels, chambers or sensor matrixes as well as the removal of any disturbing bubbles. In summary, centrifugal microfluidics takes advantage of a comprehensive set of fluidic unit operations such as

  9. Operational status display and automation tools for FERMI-Elettra

    International Nuclear Information System (INIS)

    Scafuri, C.

    2012-01-01

    Detecting and locating faults and malfunctions of an accelerator is a difficult and time consuming task. The situation is even more difficult during the commissioning phase of a new accelerator, when the plants are not yet well known. Faults involving single devices are easy to detect, however a fault free machine does not imply that it is ready to run: the definition of malfunction depends on what is the expected behavior of the plant. In the case of FERMI-Elettra, in which the electron beam goes to different branches of the machine depending on the programmed activity, the configuration of the plant determines the rules for detecting malfunctions. In order to help the detection of faults and malfunctions and to display the status of the plant, a tool, known as the 'Matrix', has been developed. It is composed by a graphical front-end which displays a synthetic view of the plant status grouped by subsystem and location along the accelerator, and by a back-end calculation engine. The graphical front-end gives also the possibility, once a problem is detected, to focus on its details. The calculation engine is composed by a set of objects known as Sequencers. The calculation rules have been determined by analyzing the various subsystems and global working of the accelerator with plant and operations experts. The Sequencer is designed so that it can also issue commands to the plant. This will be used in the next releases of the Matrix for actively switching from one accelerator configuration to another. (author)

  10. Expert system for operational personnel support during power unit operation control in regulation range

    International Nuclear Information System (INIS)

    Yanitskij, V.A.

    1992-01-01

    The problems met when developing the systems for NPP operator support in the process of power unit operation are considered. The expert system for NPP personnel intelligent support combining the properties belonging to the artificial intelligence systems including selection of the analysis method taking into account the concrete technological situation and capability of application of algothmic calculations of the equipment characteristics using the information accumulated during the system development, erection and operation is described

  11. Status of neonatal intensive care units in India.

    Directory of Open Access Journals (Sweden)

    Fernandez A

    1993-04-01

    Full Text Available Neonatal mortality in India accounts for 50% of infant mortality, which has declined to 84/1000 live births. There is no prenatal care for over 50% of pregnant women, and over 80% deliver at home in unsafe and unsanitary conditions. Those women who do deliver in health facilities are unable to receive intensive neonatal care when necessary. Level I and Level II neonatal care is unavailable in most health facilities in India, and in most developing countries. There is a need in India for Level III care units also. The establishment of neonatal intensive care units (NICUs in India and developing countries would require space and location, finances, equipment, staff, protocols of care, and infection control measures. Neonatal mortality could be reduced by initially adding NICUs at a few key hospitals. The recommendation is for 30 NICU beds per million population. Each bed would require 50 square feet per cradle and proper climate control. Funds would have to be diverted from adult care. The largest expenses would be in equipment purchase, maintenance, and repair. Trained technicians would be required to operate and monitor the sophisticated ventilators and incubators. The nurse-patient ratio should be 1:1 and 1:2 for other infants. Training mothers to work in the NICUs would help ease the problems of trained nursing staff shortages. Protocols need not be highly technical; they could include the substitution of radiant warmers and room heaters for expensive incubators, the provision of breast milk, and the reduction of invasive procedures such as venipuncture and intubation. Nocosomial infections should be reduced by vacuum cleaning and wet mopping with a disinfectant twice a day, changing disinfectants periodically, maintaining mops to avoid infection, decontamination of linen, daily changing of tubing, and cleaning and sterilizing oxygen hoods and resuscitation equipment, and maintaining an iatrogenic infection record book, which could be used to

  12. Status of fast breeder reactor development in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Horton, K [U.S. Department of Energy, Washington, DC (United States)

    1981-05-01

    The energy policy of the United States is aimed at shifting as rapidly as practicable from an oil dependent economy to one that relies heavily on other fuels and energy sources. Nuclear power Is now and is expected to continue to be an important factor in achieving this goal. If nuclear power is to contribute to a solution of future energy needs, demonstration of the breeder reactor as a viable source of essentially inexhaustible energy supply is essential. The US DOE program for development of the fast breeder reactor has witnessed some notable events in the past year. Foremost among these Is the successful operational testing of the Fast Flux Test Facility (FFTF), located at.the Hanford Engineering Development Laboratory. The reactor reached full design power of 400 MW(t) on December 21, 1980, and has performed remarkably close to design specifications. Design of the Clinch River Breeder Reactor Plant (CRBRP), a 375 MW(e) LMFBR, is now over 80 percent complete. About $530 million in components have been ordered; component deliveries total approximately $124 million; work-in-process totals another $204 million. Construction of the plant, however, has been suspended since 1977. With the concurrence of the U.S. Congress and approvals from the appropriate authorities work on the safety review and site clearing for construction can resume. The Conceptual Design Study for a large, 1000 MW(e) LMFBR Large Developmental Plant was recently completed on a schedule commensurate with submission of a full report to the Congress at the end of March, 1981. This report is the culmination of a study which began in October, 1978 and involved contributions from U.S. reactor manufacturers and US DOE laboratories. The US DOE is carrying forward a comprehensive technology development program. This effort provides direct support to the FFTF and CRBRP projects and to the LDP. It also supports technology development which is generic to the overall LMFBR program. Funding for breeder

  13. Status of fast breeder reactor development in the United States

    International Nuclear Information System (INIS)

    Horton, K.

    1981-01-01

    The energy policy of the United States is aimed at shifting as rapidly as practicable from an oil dependent economy to one that relies heavily on other fuels and energy sources. Nuclear power Is now and is expected to continue to be an important factor in achieving this goal. If nuclear power is to contribute to a solution of future energy needs, demonstration of the breeder reactor as a viable source of essentially inexhaustible energy supply is essential. The US DOE program for development of the fast breeder reactor has witnessed some notable events in the past year. Foremost among these Is the successful operational testing of the Fast Flux Test Facility (FFTF), located at.the Hanford Engineering Development Laboratory. The reactor reached full design power of 400 MW(t) on December 21, 1980, and has performed remarkably close to design specifications. Design of the Clinch River Breeder Reactor Plant (CRBRP), a 375 MW(e) LMFBR, is now over 80 percent complete. About $530 million in components have been ordered; component deliveries total approximately $124 million; work-in-process totals another $204 million. Construction of the plant, however, has been suspended since 1977. With the concurrence of the U.S. Congress and approvals from the appropriate authorities work on the safety review and site clearing for construction can resume. The Conceptual Design Study for a large, 1000 MW(e) LMFBR Large Developmental Plant was recently completed on a schedule commensurate with submission of a full report to the Congress at the end of March, 1981. This report is the culmination of a study which began in October, 1978 and involved contributions from U.S. reactor manufacturers and US DOE laboratories. The US DOE is carrying forward a comprehensive technology development program. This effort provides direct support to the FFTF and CRBRP projects and to the LDP. It also supports technology development which is generic to the overall LMFBR program. Funding for breeder

  14. Radioactive acid digestion test unit nonradioactive startup operations

    International Nuclear Information System (INIS)

    Allen, C.R.; Cowan, R.G.; Crippen, M.D.; Divine, J.R.

    1978-05-01

    The Radioactive Acid Digestion Test Unit (RADTU) will process 5 kg/hour of combustible solid waste and is designed to handle almost all solid combustible waste found in plutonium processing with plutonium contamination levels up to scrap. The RADTU is designed with special safety features to safely contain high masses of fissile materials and to safely handle unusual materials and reactive chemicals which may find their way into the waste. Nonradioactive operating experience to date has been very satisfactory. RADTU has been operated for extended runs on both a 24-hour per day basis as well as on a one shift per day basis. Some minor operating problems have been encountered as expected in a shakedown operation. In general, solutions to these have been readily found. 12 figures

  15. Nonconvulsive status epilepticus after cessation of convulsive status epilepticus in pediatric intensive care unit patients.

    Science.gov (United States)

    Chen, Jin; Xie, Lingling; Hu, Yue; Lan, Xinghui; Jiang, Li

    2018-05-01

    Little is known about pediatric patients suffering from nonconvulsive status epilepticus (NCSE) after convulsive status epilepticus (CSE) cessation. The aim of this study was to identify in pediatric patients the clinical characteristics of NCSE after CSE cessation and the factors that contribute to patient outcomes. Data from clinical features, electroencephalography (EEG) characteristics, neuroimaging findings, treatments, and prognosis were systematically summarized, and the associations between clinical characteristics and prognosis were quantified. Thirty-eight children aged 51days-14years, 2months were identified in the Chongqing Medical University pediatric intensive care unit as having experienced NCSE after CSE cessation between October 1, 2014 and April 1, 2017. All patients were comatose, 15 of whom presented subtle motor signs. The most common underlying etiology was acute central nervous system (CNS) infection. Electroencephalography (EEG) data showed that, during the NCSE period, all patients had several discrete episodes (lasting from 30s to 6h long), and the most common duration was 1-5min. The ictal onset locations were classified as focal (16 patients, 42.1%), multiregional independent (10 patients, 26.3%), and generalized (12 patients, 31.6%). Wave morphologies varied during the ictal and interictal periods. Neuroimaging detected signal abnormalities in the cerebral cortex or subcortex of 33 patients with NCSE (87%), which were classified as either multifocal and consistent with extensive cortical edema (21 patients, 55.3%) or focal (12 patients, 31.6%). Twelve patients were on continuous intravenous phenobarbital, and 31 were on continuous infusion of either midazolam (27 patients) or propofol (4 patients). At least one other antiepileptic drug was prescribed for 32 patients. Three patients were on mild hypothermia therapy. The duration of NCSE lasted 24h for 18 patients. The mortality rate was 21.1%, and half of the surviving patients had

  16. Advanced Transport Operating System (ATOPS) control display unit software description

    Science.gov (United States)

    Slominski, Christopher J.; Parks, Mark A.; Debure, Kelly R.; Heaphy, William J.

    1992-01-01

    The software created for the Control Display Units (CDUs), used for the Advanced Transport Operating Systems (ATOPS) project, on the Transport Systems Research Vehicle (TSRV) is described. Module descriptions are presented in a standardized format which contains module purpose, calling sequence, a detailed description, and global references. The global reference section includes subroutines, functions, and common variables referenced by a particular module. The CDUs, one for the pilot and one for the copilot, are used for flight management purposes. Operations performed with the CDU affects the aircraft's guidance, navigation, and display software.

  17. SCOPING SUMMARY FOR THE P-AREA OPERABLE UNIT

    International Nuclear Information System (INIS)

    Kupar, J; Sadika Baladi, S; Mark Amidon, M

    2007-01-01

    This scoping summary supports development of the combined Remedial Investigation (RI)/Baseline Risk Assessment (BRA)/Feasibility Study (FS) for the P-Area Operable Unit (PAOU), or Combined document, which will be submitted on or before 09/28/2007. The objective of this Feasibility Study scoping summary meeting is to agree on the likely response actions to be evaluated and developed as alternatives in the combined document and agree on the uncertainties identified and whether they have been adequately managed

  18. SCOPING SUMMARY FOR THE P-AREA OPERABLE UNIT

    Energy Technology Data Exchange (ETDEWEB)

    Kupar, J; Sadika Baladi, S; Mark Amidon, M

    2007-05-22

    This scoping summary supports development of the combined Remedial Investigation (RI)/Baseline Risk Assessment (BRA)/Feasibility Study (FS) for the P-Area Operable Unit (PAOU), or Combined document, which will be submitted on or before 09/28/2007. The objective of this Feasibility Study scoping summary meeting is to agree on the likely response actions to be evaluated and developed as alternatives in the combined document and agree on the uncertainties identified and whether they have been adequately managed.

  19. 100-KR-1 Operable Unit focused feasibility study report

    International Nuclear Information System (INIS)

    1994-11-01

    The standard Comprehensive Environmental Response, Compensation, and Liability Act of 1980 Feasibility Study (FS) includes development and screening of alternatives and the detailed analysis of alternatives. This focused feasibility study (FFS) was conducted for the 100-KR-1 Operable Unit at the Hanford Site in southeastern Washington. The objective of this operable unit-specific FFS is to provide decision makers with sufficient information to allow appropriate and timely selection of interim remedial measures (IRM) for the five sites (116-K-1 crib, 116-K-2 trench, 116-KE-4 and 116-KW-3 retention basins, and process effluent pipelines) associated with the 100-KR-1 Operable Unit. The IRM candidate waste sites are determined in the limited field investigation. Site profiles are developed for each of these waste site. The site profiles are used in the application of the plug-in approach. The waste site either plugs into the analysis of the alternatives for the group, or deviations from the developed group alternatives are described and documented

  20. Operating experience gained during the copper oxide plugging incident in Koeberg unit 1 generator stator

    Energy Technology Data Exchange (ETDEWEB)

    Mellor, S.P.; Matthee, F.W. [ESKOM, Koeberg Nuclear Power Station (South Africa)

    2002-07-01

    In June 1999 Koeberg's unit 1 started to experience adverse operating conditions which were later ascribed to blockages in the hollow conductors of the generator stator. These blockages were attributed to copper oxide plugs which developed progressively during the following year and culminated in reduced power operation. Many attempts were made to address the plugging by implementing various off-line and on-line cleaning processes. Subsequent to a successful on-line cleaning operation, the unit was returned to full power and the chemistry regime for the stator cooling water system was changed to allow for operation at an elevated pH. This paper discusses Koeberg's experience with copper oxide blockages, describes the initial indications of the problem and the impact on the operating parameters. The remainder of the paper focuses on the actions taken to address the deteriorating situation and the different cleaning methods implemented to remove the copper oxide deposits. The paper concludes with the current status of the unit 1 generator stator and the lessons learned during the resolution of this problem. (authors)

  1. Operating experience gained during the copper oxide plugging incident in Koeberg unit 1 generator stator

    International Nuclear Information System (INIS)

    Mellor, S.P.; Matthee, F.W.

    2002-01-01

    In June 1999 Koeberg's unit 1 started to experience adverse operating conditions which were later ascribed to blockages in the hollow conductors of the generator stator. These blockages were attributed to copper oxide plugs which developed progressively during the following year and culminated in reduced power operation. Many attempts were made to address the plugging by implementing various off-line and on-line cleaning processes. Subsequent to a successful on-line cleaning operation, the unit was returned to full power and the chemistry regime for the stator cooling water system was changed to allow for operation at an elevated pH. This paper discusses Koeberg's experience with copper oxide blockages, describes the initial indications of the problem and the impact on the operating parameters. The remainder of the paper focuses on the actions taken to address the deteriorating situation and the different cleaning methods implemented to remove the copper oxide deposits. The paper concludes with the current status of the unit 1 generator stator and the lessons learned during the resolution of this problem. (authors)

  2. Treatability test plan for the 200-ZP-1 operable unit

    International Nuclear Information System (INIS)

    1994-07-01

    This document presents the treatability test plan for pilot-scale pump and treat testing at the 200-ZP-1 Operable Unit. The approach discussed in this treatability test plan is to conduct a pilot-scale pump and treat test for the contaminant plume associated with the 200-ZP-1 Operable Unit. The primary contaminants of concern are carbon tetrachloride, chloroform, and trichloroethylene (TCE). The pilot-scale treatability testing has as its primary purpose to assess the performance of aboveground treatment systems with respect to the ability to remove the primary contaminants present in groundwater withdrawn from the contaminant plume. The overall scope of this test plan includes: description of the pump and treat system to be tested, as well as the test performance objectives and data quality objectives (DQOs) that will be used to evaluate the effectiveness of the pilot-scale treatment system; discussion of the treatment technology to be tested and supporting development activities, including process flow and conceptual design descriptions and equipment, fabrication, utility, and system startup needs; description of pilot-scale treatment system performance, operating procedures, and operational controls, as well as anticipated monitoring activities, analytes, parameters, analytical procedures, and quality assurance protocols; summaries of other related treatability testing elements, including personnel and environmental health and safety controls, process and secondary waste management and disposition, schedule, and program organization

  3. Steam generator tube integrity requirements and operating experience in the United States

    International Nuclear Information System (INIS)

    Karwoski, K.J.

    2009-01-01

    Steam generator tube integrity is important to the safe operation of pressurized-water reactors. For ensuring tube integrity, the U.S. Nuclear Regulatory Commission uses a regulatory framework that is largely performance based. This performance-based framework is supplemented with some prescriptive requirements. The framework recognizes that there are three combinations of tube materials and heat treatments currently used in the United States and that the operating experience depends, in part, on the type of material used. This paper summarizes the regulatory framework for ensuring steam generator tube integrity, it highlights the current status of steam generators, and it highlights some of the steam generator issues and challenges that exist in the United States. (author)

  4. Groundwater Monitoring Plan for the Reactor Technology Complex Operable Unit 2-13

    International Nuclear Information System (INIS)

    Richard P. Wells

    2007-01-01

    This Groundwater Monitoring Plan describes the objectives, activities, and assessments that will be performed to support the on-going groundwater monitoring requirements at the Reactor Technology Complex, formerly the Test Reactor Area (TRA). The requirements for groundwater monitoring were stipulated in the Final Record of Decision for Test Reactor Area, Operable Unit 2-13, signed in December 1997. The monitoring requirements were modified by the First Five-Year Review Report for the Test Reactor Area, Operable Unit 2-13, at the Idaho National Engineering and Environmental Laboratory to focus on those contaminants of concern that warrant continued surveillance, including chromium, tritium, strontium-90, and cobalt-60. Based upon recommendations provided in the Annual Groundwater Monitoring Status Report for 2006, the groundwater monitoring frequency was reduced to annually from twice a year

  5. Heat recovery unit operation of HVAC system in IMEF

    International Nuclear Information System (INIS)

    Paek, S. R.; Oh, Y. W.; Song, E. S.; Park, D. K.; Joo, Y. S.; Hong, K. P.

    2003-01-01

    HVAC system including a supply and exhaust air system in IMEF(Irradiated Materials Examination Facility) is an essential facility for preventing a leakage of radioactive materials and for a preservation of a working environment. It costs a lot to operate the HVAC system in IMEF because our ventilation type is once-through system, and an air flow is maintained from low level contamination area to high level and maintained high turns of ventilation air under certain conditions. As HRU(Heat Recovery Unit) at HVAC system based on PIEF(Post Irradiation Examination Facility) operation experiences is designed and adopted, it prevents from a heating coil freezing destruction in winter and makes much energy saving etc.. Heat pipe type HRU is adopted in IMEF, and a construction and operation result of HRU is examined

  6. Chapter 16. Conservation status of great gray owls in the United States

    Science.gov (United States)

    Gregory D. Hayward

    1994-01-01

    Previous chapters outlined the biology and ecology of great gray owls as well as the ecology of this species in the western United States. That technical review provides the basis to assess the current conservation status of great gray owls in the United States. Are populations of great gray owls in the United States currently threatened? Are current land management...

  7. Diversity, distribution, and conservation status of the native freshwater fishes of the Southern United States

    Science.gov (United States)

    Melvin L. Warren; Brooks M. Burr; Stephen J. Walsh; Henry L. Bart; Robert C. Cashner; David A. Etnier; Byron J. Freeman; Bernard R. Kuhajda; Richard L. Mayden; Henry W. Robison; Stephen T. Ross; Wayne C. Starnes

    2000-01-01

    The Southeastern Fishes Council Technical Advisory Committee reviewed the diversity, distribution, and status of all native freshwater and diadromous fishes across 51 major drainage units of the Southern United States. The Southern United States supports more native fishes than any area of comparable size on the North American continent north of Mexico, but also has a...

  8. USA/FBR program status FFTF operations startup experience

    International Nuclear Information System (INIS)

    Moffitt, W.C.; Izatt, R.D.

    1981-06-01

    This paper gives highlights of the major Operations evaluations and operational results of the startup acceptance testing program and initiation of normal operating cycles for experiment irradiation in the FFTF. 33 figures

  9. Licensed operating reactors: Status summary report data as of 04-30-88

    International Nuclear Information System (INIS)

    1988-05-01

    This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States. The percentage computations, Items 20 through 24 in Section 2, the vendor capacity factors on page 1-7, and actual vs. potential energy production on page 1-2 are computed using actual data for the period of consideration. The percentages listed in power generation on Page 1-2 are computed as an arithmetic average. The factors for the life-span of each unit (the ''Cumulative'' column) are reported by the utility and are not entirely re-computed by NRC. Utility power production data is checked for consistency with previously submitted statistics. It is hoped this status report proves informative and helpful to all agencies and individuals interested in analyzing trends in the nuclear industry which might have safety implications, or in maintaining an awareness of the US energy situation as a whole

  10. WTP Waste Feed Qualification: Glass Fabrication Unit Operation Testing Report

    Energy Technology Data Exchange (ETDEWEB)

    Stone, M. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Hanford Missions Programs; Newell, J. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Process Technology Programs; Johnson, F. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Engineering Process Development; Edwards, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Engineering Process Development

    2016-07-14

    The waste feed qualification program is being developed to protect the Hanford Tank Waste Treatment and Immobilization Plant (WTP) design, safety basis, and technical basis by assuring waste acceptance requirements are met for each staged waste feed campaign prior to transfer from the Tank Operations Contractor to the feed receipt vessels inside the Pretreatment Facility. The Waste Feed Qualification Program Plan describes the three components of waste feed qualification: 1. Demonstrate compliance with the waste acceptance criteria 2. Determine waste processability 3. Test unit operations at laboratory scale. The glass fabrication unit operation is the final step in the process demonstration portion of the waste feed qualification process. This unit operation generally consists of combining each of the waste feed streams (high-level waste (HLW) and low-activity waste (LAW)) with Glass Forming Chemicals (GFCs), fabricating glass coupons, performing chemical composition analysis before and after glass fabrication, measuring hydrogen generation rate either before or after glass former addition, measuring rheological properties before and after glass former addition, and visual observation of the resulting glass coupons. Critical aspects of this unit operation are mixing and sampling of the waste and melter feeds to ensure representative samples are obtained as well as ensuring the fabrication process for the glass coupon is adequate. Testing was performed using a range of simulants (LAW and HLW simulants), and these simulants were mixed with high and low bounding amounts of GFCs to evaluate the mixing, sampling, and glass preparation steps in shielded cells using laboratory techniques. The tests were performed with off-the-shelf equipment at the Savannah River National Laboratory (SRNL) that is similar to equipment used in the SRNL work during qualification of waste feed for the Defense Waste Processing Facility (DWPF) and other waste treatment facilities at the

  11. The quality of operative notes at a general surgery unit.

    Science.gov (United States)

    Rogers, A; Bunting, M; Atherstone, A

    2008-09-01

    With the increasingly litigious nature of medical practice, accurate documentation is critical. This is particularly true for operative procedures, and medical councils have identified this and published guidelines to aid surgeons. However, these remain a frequently cited weakness in their defence in medico-legal cases. This study assessed the accuracy of operative notes in a general surgery unit in order to improve our practice. An audit of 100 consecutive operative notes was performed, and notes were assessed using the Royal College of Surgeons guidelines. The quality of note-taking of trainees was compared with that of consultant surgeons. A series of operation note pro formas was designed in response to the findings. Of the notes, 66% were completed by trainees. The vast majority of notes had no diagram to demonstrate the surgical findings or illustrate the actions. Specialist surgeons were more likely to describe the actions accurately, but less likely to describe wound closure methods or dressings used. They were also less likely to complete adequate postoperative orders. This study identifies key areas of weakness in our operative note-keeping. Pro formas should be introduced and made available for commonly performed procedures, and diagrams should be used wherever possible.

  12. Feasibility study report for Operable Unit 4: Volume 1

    International Nuclear Information System (INIS)

    1994-02-01

    This report documents the Feasibility Study (FS) phase of the Fernald Environmental Management Project (FEMP) Operable Unit 4 Remedial Investigation/Feasibility Study (RI/FS) Program. The FEMP, formerly known as the Feed Materials Production Center (FMPC), is a US Department of Energy (DOE) facility that operated from 1952 to 1989. The facility's primarily function was to provide high purity uranium metal products to support United States defense programs. Production operations were suspended in 1989 to focus on environmental restoration and waste management activities at the facility. The RI/FS is being conducted pursuant to the terms of a Consent Agreement between DOE and the US Environmental Protection Agency (EPA) under Sections 120 and 106(a) of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. The Ohio Environmental Protection Agency (OEPA) is also participating in the RI/FS process at the FEMP through direct involvement in program review meetings and technical review of project documentation. The objective of the RI/FS process is to gather information to support an informed risk management decision regarding which remedy appears to be the most appropriate action for addressing the environmental concerns identified at the FEMP

  13. Feasibility study report for Operable Unit 4: Volume 2

    International Nuclear Information System (INIS)

    1994-02-01

    This report documents the Feasibility Study (FS) phase of the Fernald Environmental Management Project (FEMP) Operable Unit 4 Remedial Investigation/Feasibility Study (RI/FS) Program. The FEMP, formerly known as the Feed Materials Production Center (FMPC), is a US Department of Energy (DOE) facility that operated from 1952 to 1989. The facility's primarily function was to provide high purity uranium metal products to support United States defense programs. Production operations were suspended in 1989 to focus on environmental restoration and waste management activities at the facility. The RI/FS is being conducted pursuant to the terms of a Consent Agreement between DOE and the US Environmental Protection Agency (EPA) under Sections 120 and 106(a) of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. The Ohio Environmental Protection Agency (OEPA) is also participating in the RI/FS process at the FEMP through direct involvement in program review meetings and technical review of project documentation. The objective of the RI/FS process is to gather information to support an informed risk management decision regarding which remedy appears to be the most appropriate action for addressing the environmental concerns identified at the FEMP. This volume contains appendices A--E

  14. Training operators of VVER-1000 units in Eastern Europe

    International Nuclear Information System (INIS)

    Normand, X.; Nabet, E.; Hauesberger, P.

    1996-01-01

    The VVER 1000 is the most recent nuclear reactor designed in the former Soviet Union. Its design and operation principles are close to Western four-loop reactors in the 1000- to 1500-MW class; therefore, the Western simulation technology is usually directly applicable to the simulation of these units. Moreover, the current number of state-of-the-art training simulators in operation is very limited. A total of 19 units are in operation, while only 2 modern simulators are available (full-scope type) in Balakovo and Zaporozhe. Access to these simulators is practically limited to the respective plants' trainees, which means that the other units have to be satisfied with hands-on training. Facing this situation and taking into account the predicted lifetime of these plants (15 to 25 yr to go, maybe more), a lot of effort has been made in recent years to provide the plants with modern simulators. The major hurdles to this action were obviously financial and technical (availability of codes, computers, software tools). Today, one full-scope project (Kalinin) is almost complete, and three have been announced (Novovoronezh, Khmelnitsky, Kozloduy). Full-scope simulators are clearly the ultimate target of a concerned power plants. However, all users do realize the advantages of the complementary approach with compact simulators: 1. They can be available quickly for starting the training process. 2. They cover a training field that is not (or partly) addressed by full-scope simulators, i.e., the demonstration of physical phenomena in normal and accidental situations

  15. The role of heat pipes in intensified unit operations

    International Nuclear Information System (INIS)

    Reay, David; Harvey, Adam

    2013-01-01

    Heat pipes are heat transfer devices that rely, most commonly, on the evaporation and condensation of a working fluid contained within them, with passive pumping of the condensate back to the evaporator. They are sometimes referred to as ‘thermal superconductors’ because of their exceptionally high effective thermal conductivity (substantially higher than any metal). This, together with several other characteristics make them attractive to a range of intensified unit operations, particularly reactors. The majority of modern computers deploy heat pipes for cooling of the CPU. The application areas of heat pipes come within a number of broad groups, each of which describes a property of the heat pipe. The ones particularly relevant to chemical reactors are: i. Separation of heat source and sink. ii. Temperature flattening, or isothermalisation. iii. Temperature control. Chemical reactors, as a heat pipe application area, highlight the benefits of the heat pipe based on isothermalisation/temperature flattening device and on being a highly effective heat transfer unit. Temperature control, done passively, is also of relevance. Heat pipe technology offers a number of potential benefits to reactor performance and operation. The aim of increased yield of high purity, high added value chemicals means less waste and higher profitability. Other intensified unit operations, such as those employing sorption processes, can also profit from heat pipe technology. This paper describes several variants of heat pipe and the opportunities for their use in intensified plant, and will give some current examples. -- Highlights: ► Heat pipes – thermal superconductors – can lead to improved chemical reactor performance. ► Isothermalisation within a reactor vessel is an ideal application. ► The variable conductance heat pipe can control reaction temperatures within close limits. ► Heat pipes can be beneficial in intensified reactors

  16. Vitamin D Status: United States, 2001-2006

    Science.gov (United States)

    ... sufficient vitamin D, defined by the Institute of Medicine as a serum 25-hydroxyvitamin D (25OHD) value of 50–125 nmol/L. About one-quarter ... the vitamin D status of the U.S. population based on the IOM thresholds for serum ... 25OHD values considered sufficient ( Figure 1 ). Roughly one quarter of ...

  17. Feasibility Study for Operable Unit 7-13/14

    International Nuclear Information System (INIS)

    K. Jean Holdren Thomas E. Bechtold Brian D. Preussner

    2007-01-01

    The Subsurface Disposal Area is a radioactive waste landfill located within the Radioactive Waste Management Complex at the Idaho National Laboratory Site in southeastern Idaho. This Feasibility Study for Operable Unit 7-13/14 analyzes options for mitigating risks to human health and the environment associated with the landfill. Analysis is conducted in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act, using nine evaluation criteria to develop detailed and comparative analysis of five assembled alternatives. Assembled alternatives are composed of discrete modules. Ultimately, decision-makers will select, recombine, and sum various modules into an optimized preferred alternative and final remedial decision

  18. Feasibility Study for Operable Unit 7-13/14

    Energy Technology Data Exchange (ETDEWEB)

    K. Jean Holdren

    2007-05-29

    The Subsurface Disposal Area is a radioactive waste landfill located within the Radioactive Waste Management Complex at the Idaho National Laboratory Site in southeastern Idaho. This Feasibility Study for Operable Unit 7-13/14 analyzes options for mitigating risks to human health and the environment associated with the landfill. Analysis is conducted in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act, using nine evaluation criteria to develop detailed and comparative analysis of five assembled alternatives. Assembled alternatives are composed of discrete modules. Ultimately, decision-makers will select, recombine, and sum various modules into an optimized preferred alternative and final remedial decision.

  19. Article separation apparatus and method for unit operations

    Science.gov (United States)

    Pardini, Allan F.; Gervais, Kevin L.; Mathews, Royce A.; Hockey, Ronald L.

    2010-06-22

    An apparatus and method are disclosed for separating articles from a group of articles. The apparatus includes a container for containing one or more articles coupled to a suitable fluidizer for suspending articles within the container and transporting articles to an induction tube. A portal in the induction tube introduces articles singly into the induction tube. A vacuum pulls articles through the induction tube separating the articles from the group of articles in the container. The apparatus and method can be combined with one or more unit operations or modules, e.g., for inspecting articles, assessing quality of articles, or ascertaining material properties and/or parameters of articles, including layers thereof.

  20. Risk-based decision analysis for groundwater operable units

    International Nuclear Information System (INIS)

    Chiaramonte, G.R.

    1995-01-01

    This document proposes a streamlined approach and methodology for performing risk assessment in support of interim remedial measure (IRM) decisions involving the remediation of contaminated groundwater on the Hanford Site. This methodology, referred to as ''risk-based decision analysis,'' also supports the specification of target cleanup volumes and provides a basis for design and operation of the groundwater remedies. The risk-based decision analysis can be completed within a short time frame and concisely documented. The risk-based decision analysis is more versatile than the qualitative risk assessment (QRA), because it not only supports the need for IRMs, but also provides criteria for defining the success of the IRMs and provides the risk-basis for decisions on final remedies. For these reasons, it is proposed that, for groundwater operable units, the risk-based decision analysis should replace the more elaborate, costly, and time-consuming QRA

  1. Operational benchmark for VVER-1000, unit 6, Kozloduy NPP

    International Nuclear Information System (INIS)

    Apostolov, T.; Petrov, B.

    1999-01-01

    Benchmark calculations have been carried out using the 3D nodal code TRAPEZ. Global neutron-physics characteristics of the VVER-1000 core, Kozloduy NPP Unit 6, have been determined taking into account the real loading patterns and operational history of the first three cycles. The code TRLOAD has been used to perform the fuel reloading between any two cycles. The reactor and components descriptions as well as material compositions are given. The results presented include the critical boric acid concentration, the radial power distribution, the axial power distribution for the maximum overload assembly, and the burnup distribution at three different moments during each cycle. Calculated values have been compared with measured data. It is shown that the results obtained by the TRAPEZ code are in good agreement with the experimental data. The information presented could serve as a test case for validation of code packages designed for analyzing the steady-state operation of VVERs. (author)

  2. Operational aerial snow surveying in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Peck, E L; Carroll, T R; Vandemark, S C

    1980-03-01

    An airborne gamma radiation detector and data acquisition system has been designed for rapid measurement of the snow cover water equivalent over large open areas. Research and field tests conducted prior to the implementation of an operational snow measurement system in the United States are reviewed. Extensive research test flights were conducted over large river basins of the north-central plains and in the high mountain valleys of the inter-mountain West. Problems encountered during development include: (1) error in the gross gamma flux produced by atmospheric radon gas daughters; (2) spatial and temporal variability in soil moisture; and (3) errors in gamma radiation count rate introduced by aircraft and cosmic background radiation. Network design of operational flight line and ground observation data used in a river forecasting system are discussed. 22 references, 4 figures, 2 tables.

  3. A Database Design for a Unit Status Reporting System.

    Science.gov (United States)

    1987-03-01

    s wl. h i l be co~ivlywnsidered a, __) Do a. &ca tcmh W111111 winng 940r determining a aes training and overall porn " GROW. ’~.*.. .21W ISfsota i Ql...field in which arabic unit~s will not be organized or used solely for A six-position numeric code that signifi nmrls0(eo)esuh a anb e non wartime

  4. Assessment of Soil Nutrient Status of Identified Soil Units in Selected ...

    African Journals Online (AJOL)

    Journal of Technology and Education in Nigeria ... Assessment of Soil Nutrient Status of Identified Soil Units in Selected Communities in Three Local Government Areas ... Available phosphorus content in the soils is generally high with values ...

  5. Chapter 11. Conservation status of boreal owls in the United States

    Science.gov (United States)

    Gregory D. Hayward

    1994-01-01

    Previous chapters outlined the biology and ecology of boreal owls as well as the ecology of important vegetation communities based on literature from North America and Europe. That technical review provides the basis to assess the current conservation status of boreal owls in the United States. By conservation status, we mean the demographic condition of the species as...

  6. 100-BC-1 Operable Unit focused feasibility study

    International Nuclear Information System (INIS)

    Day, R.E.

    1994-01-01

    The standard Comprehensive Environmental Response, Compensation, and Liability Act feasibility study includes development and screening of alternatives (Phases 1 and 2) and the detailed analysis of alternatives (Phase 3). This focused feasibility study constitutes the Phase 3 portion of the feasibility study process for the remedial alternatives initially developed and screened in the 100 Area Feasibility Study Phases 1 and 2 (DOE-RL 1993a). The focused feasibility study process is conducted in two stages, a Process Document (DOE-RL 1994a) and an operable unit-specific focused feasibility study document, such as this one. The focused feasibility study process is performed by implementing a ''plug-in'' style approach; as defined in greater detail in the Process Document, which is a companion to this document. The objective of this focused feasibility study is to provide decision makers with sufficient information to allow appropriate and timely selection of interim remedial measures for candidate waste sites associated with the 100-BC-1 Operable Unit which is located in the north-central part of the Hanford Site. The interim remedial measure candidate waste sites are determined in the Limited Field Investigation (DOE-RL 1993b). Site profiles are developed for each of these waste sites. The site profiles are used in the application of the plug-in approach. The waste site either plugs into the analysis of the alternatives for the group, or deviations from the developed group alternatives are described and documented

  7. Neural Networks in Modelling Maintenance Unit Load Status

    Directory of Open Access Journals (Sweden)

    Anđelko Vojvoda

    2002-03-01

    Full Text Available This paper deals with a way of applying a neural networkfor describing se1vice station load in a maintenance unit. Dataacquired by measuring the workload of single stations in amaintenance unit were used in the process of training the neuralnetwork in order to create a model of the obse1ved system.The model developed in this way enables us to make more accuratepredictions over critical overload. Modelling was realisedby developing and using m-functions of the Matlab software.

  8. Status of commercial food irradiation in the United States

    International Nuclear Information System (INIS)

    Welt, M.A.

    1983-01-01

    It may be difficult for some to realize, but the United States is now starting its fourth decade in food irradiation research. This vast storehouse of research data now makes the ultimate task of bringing the technology to the consumer marketplace that much easier. Radiation Technology, Inc. of Rockaway, New Jersey has pioneered the use of radiation processing for the commercial preservation of food and has established the first food irradiation facility in the United States in West Memphis, Arkansas. The facility, designed by Radiation Technology, Inc., provides the necessary versatility to meet the needs of the food industry. (author)

  9. Status of commercial food irradiation in the United States

    Science.gov (United States)

    Welt, Martin A.

    It may be difficult for some to realize, but the United States is now starting its fourth decade in food irradiation research. This vast storehouse of research data now makes the ultimate task of bringing the technology to the consumer marketplace that much easier. Radiation Technology, Inc. of Rockaway, New Jersey has pioneered the use of radiation processing for the commercial preservation of food and has established the first food irradiation facility in the United States in West Memphis, Arkansas. The facility, designed by Radiation Technology, Inc., provides the necessary versatility to meet the needs of the food industry.

  10. Kozloduy nuclear power plant. Units 1-4. Status of safety improvements. Rev. 2

    International Nuclear Information System (INIS)

    1999-01-01

    operation of the units. The plant current safety level analysis has been performed using IAEA analytical methodology according to 50-SG-O12 standard 'Periodic safety review of operational nuclear power plants'. The approach and criteria for acceptable safety level definition, developed by IAEA and presented in INSAG-8 ' was used for analysis performance. Based on this analysis a set of activities was developed, to ensures further plant operation with the necessary safety level. The measures were combined in a program called Complex program for modernization of units 1-4. The implementation of the program is foreseen for a period of four next fuel cycles and started at the beginning of 1998. In respond to the requirements for the content of this paper a detailed description of the current status of resolving of the safety issues, classified by IAEA in TECDOC 640 is presented. The whole process of safety evaluation, short and long term safety improvements presents in a systematical manner the efforts of the Government of Bulgaria, NEK Ltd and KNPP to operate these units with due respect of their nuclear safety responsibility according to Nuclear Safety Convention signed at Vienna in 1994 and ratified by Bulgarian Parliament in 1995

  11. Operational status of the Brookhaven National Laboratory Accelerator Test Facility

    International Nuclear Information System (INIS)

    Batchelor, K.; Ben-Zvi, I.; Chou, T.S.; Los Alamos National Lab., NM; Princeton Univ., NJ

    1989-01-01

    Design and operation of a 50 MeV Electron Linear Accelerator utilizing a low emittance (γ var epsilon = 5 to 10 mm-mrad) radio frequency gun operating at an output energy of 5 MeV and a charge of 1 nC is described. Design calculations and early radio frequency measurements and operational experience with the electron gun utilizing a dummy copper cathode in place of the proposed photocathode emitter are given. 6 refs., 9 figs., 1 tab

  12. Operational validation - current status and opportunities for improvement

    International Nuclear Information System (INIS)

    Davey, E.

    2002-01-01

    The design of nuclear plant systems and operational practices is based on the application of multiple defenses to minimize the risk of occurrence of safety and production challenges and upsets. With such an approach, the effectiveness of individual or combinations of design and operational features in preventing upset challenges should be known. A longstanding industry concern is the adverse impact errors in human performance can have on plant safety and production. To minimize the risk of error occurrence, designers and operations staff routinely employ multiple design and operational defenses. However, the effectiveness of individual or combinations of defensive features in minimizing error occurrence are generally only known in a qualitative sense. More importantly, the margins to error or upset occurrence provided by combinations of design or operational features are generally not characterized during design or operational validation. This paper provides some observations and comments on current validation practice as it relates to operational human performance concerns. The paper also discusses opportunities for future improvement in validation practice in terms of the resilience of validation results to operating changes and characterization of margins to safety or production challenge. (author)

  13. Nuclear engineering education in the United States: a status report

    International Nuclear Information System (INIS)

    Miller, D.W.; Spinrad, B.I.

    1986-01-01

    The executive summary of the White Paper entitled The Revitalization of Nuclear Energy Education in the United States is the major component of this paper. The White Paper was completed under the auspices of the Nuclear Engineering Department Heads Organization (NEDHO). The presentation highlights events and program changes that have occurred in 1985-1986 following publication of the NEDHO White Paper. Many of these events provide optimism for the revitalization of nuclear engineering education

  14. Operational status of the JAEA-Mutsu tandetron AMS

    International Nuclear Information System (INIS)

    Kabuto, Shoji; Kinoshita, Naoki; Amano, Hikaru; Watanabe, Yukiya; Baba, Masami

    2008-01-01

    A Tandetron AMS (Accelerator Mass Spectrometer) had been set up at the Japan Atomic Energy Agency (formerly the Japan Atomic Energy Research Institute), Mutsu in 1997. The AMS features 3MV Tandetron accelerator and two independent beamlines for 14 C and 129 I measurement. In this paper, we describe the current status and troubles for the Tandetron AMS with the showing of examples from the last year. (author)

  15. Kozloduy nuclear power plant. Units 1-4. Status of safety assessment activities. Rev. 2

    International Nuclear Information System (INIS)

    1999-01-01

    This paper presents the results of the status of safety assessment activities carried out by the Kozloduy Nuclear Power Plant (KNPP) in order to evaluate the current status of the safety of its reactor units 1-4. The steam supply system of this units is based of the reactor WWER-440/ B-230, which is a PWR of Russian design developed according to the safety standards in force in USSR in late 60-s. Now a days 10 reactor units of this type are in operation in four NPPs. Despite of efforts of the different plants to implement safety improvements measures during first 10-15 years of operation of this type of reactor its major safety problems were not eliminated and were a subject of international concern. The systematic evaluation of the deficiencies of the original design of this type of reactors have been initiated by IAEA in the beginning of 1990 and brought to developing a comprehensive list of safety problems which required urgent implementation of safety measures in all plants. To solve this problems in 1991 KNPP initiated implementation of so called 'short term' safety improvement program, developed with the help of WANO under agreement with Bulgarian Nuclear Safety Authority (BNSA) and consortium RISKAUDIT. The program was based on a stage approach and was foreseen to be implemented by tree stages in very tight time schedule in order to achieve significant and rapid improvements of the level of safety in operation of the units. The Short Tenn Program was implemented between the years 1991 and 1997 thanks of the strong safety commitment of NEK and KNPP staff and the broad international cooperation and financial support. Important part of resources were supplied under PHARE program of CEC, EBRD grant agreement and EDF support. The plant current safety level analysis has been performed using IAEA analytical methodology according to 50-SG-O12 standard 'Periodic safety review of operational nuclear power plants'. The approach and criteria for acceptable safety level

  16. Explanation of significant differences for the TNX groundwater operable unit

    International Nuclear Information System (INIS)

    Palmer, E.R.

    1997-01-01

    This Explanation of Significant Differences (ESD) is being issued by the Department of Energy (DOE), the lead agency for the Savannah River Site (SRS), with concurrence by the Environmental Protection Agency-Region IV (EPA) and South Carolina Department of Health and Environmental Control (SCDHEC) to announce changes in the interim remediation strategy selected for the TNX Groundwater Operable Unit. The TNX Area is located adjacent to the Savannah River in the southwestern portion of SRS. The remedy selected in the Interim Record of Decision (IROD) to achieve the interim action goals was the Hybrid Groundwater Corrective Action (HGCA). The HGCA consisted of a recirculation well system and an air stripper with a series of groundwater extraction wells. The original remediation strategy needs to be modified because the recirculation well system was determined to be ineffective in this area due to geological factors and the nature of the contamination

  17. Water quality status and trends in the United States

    Science.gov (United States)

    Larsen, Matthew C.; Hamilton, Pixie A.; Werkheiser, William H.; Ahuja, Satinder

    2013-01-01

    Information about water quality is vital to ensure long-term availability and sustainability of water that is safe for drinking and recreation and suitable for industry, irrigation, fish, and wildlife. Protecting and enhancing water quality is a national priority, requiring information on water-quality status and trends, progress toward clean water standards, continuing problems, and emerging challenges. In this brief review, we discuss U.S. Geological Survey assessments of nutrient pollution, pesticides, mixtures of organic wastewater compounds (known as emerging contaminants), sediment-bound contaminants (like lead and DDT), and mercury, among other contaminants. Additionally, aspects of land use and current and emerging challenges associated with climate change are presented. Climate change must be considered, as water managers continue their efforts to maintain sufficient water of good quality for humans and for the ecosystem.

  18. Environmental Control Plan for the 300-FF-1 Operable Unit Remedial Action

    International Nuclear Information System (INIS)

    Carlson, R.A.

    2000-01-01

    This environmental control plan is for the 300-FF-1 Operable Unit Remedial Action Project. The purpose of this plan is to identify environmental requirements for the 300-FF-1 operable unit Remedial Action/Waste Disposal Project

  19. Operation of the radioactive acid digestion test unit

    International Nuclear Information System (INIS)

    Blasewitz, A.G.; Allen, C.R.; Lerch, R.E.; Ely, P.C.; Richardson, G.L.

    1980-01-01

    The Radioactive Acid Digestion Test Unit (RADTU) has been constructed at Hanford to demonstrate the application of the Acid Digestion Process for treating combustible transuranic wastes and scrap materials. The RADTU with its original tray digestion vessel has recently completed a six-month campaign processing potentially contaminated nonglovebox wastes from a Hanford plutonium facility. During this campaign, it processed 2100 kg of largely cellulosic wastes at an average sustained processing rate of 3 kg/h as limited by the water boiloff rate from the acid feeds. The on-line operating efficiency was nearly 50% on a twelve hour/day, five day/week basis. Following this campaign, a new annular high rate digester has been installed for testing. In preliminary tests with simulated wastes, the new digester demonstrated a sustained capacity of 10 kg/h with greatly improved intimacy of contact between the digestion acid and the waste. The new design also doubles the heat transfer surface, which with reduced heat loss area, is expected to provide at least three times the water boiloff rate of the previous tray digester design. Following shakedown testing with simulated and low-level wastes, the new unit will be used to process combustible plutonium scrap and waste from Hanford plutonium facilities for the purposes of volume reduction, plutonium recovery, and stabilization of the final waste form

  20. Status and plans of the united states ICF program

    Science.gov (United States)

    Matzen, M. K.

    2008-05-01

    Inertial confinement fusion research in the United States focuses on demonstrating ignition on the NIF at the beginning of the next decade and on broad high energy density science (HEDS) research. Three facilities (OMEGA EP, the refurbished Z, and NIF) will be completed in the next two years. The US approach emphasizes lasers and pulsed power and both direct and indirect drive. Since IFSA 2005 in Biarritz, France significant advances have been made towards demonstrating ignition in a joint effort by LLNL, LLE, LANL, SNL, and GA. An active HEDS research program will also be pursued on these new facilities.

  1. Status and plans of the united states ICF program

    International Nuclear Information System (INIS)

    Matzen, M K

    2008-01-01

    Inertial confinement fusion research in the United States focuses on demonstrating ignition on the NIF at the beginning of the next decade and on broad high energy density science (HEDS) research. Three facilities (OMEGA EP, the refurbished Z, and NIF) will be completed in the next two years. The US approach emphasizes lasers and pulsed power and both direct and indirect drive. Since IFSA 2005 in Biarritz, France significant advances have been made towards demonstrating ignition in a joint effort by LLNL, LLE, LANL, SNL, and GA. An active HEDS research program will also be pursued on these new facilities

  2. Status and perspective of the HANARO operation and utilization

    International Nuclear Information System (INIS)

    Kim, Bong Goo; Lee, Chang-Hee; Lee, Chung Young

    2005-01-01

    Since the commencement of HANARO operations in 1995, some parts of the reactor systems have been gradually improved for a stable operation of the reactor, while the operation mode has been flexibly adjusted to meet users and customers' demands. During the same period, a significant number of experimental facilities have been developed and installed for the use of the 32 vertical holes and the 7 horizontal beam ports. Owing to a stable operation of the reactor and a rapid proliferation in the utilization fields, more experimental facilities are continuously being added to satisfy the increasing and new research needs arising. As a nation-wide neutron research facility, HANARO is now successfully utilized in various fields including neutron beam research, fuel and material tests, radioisotope production, neutron activation analysis, and neutron transmutation doping, etc. (Author)

  3. Enterprise Level Status and Control of Multi-Satellite Operations

    Data.gov (United States)

    National Aeronautics and Space Administration — Single-satellite mission operation centers are used for nearly all Goddard Space Flight Center (GSFC) mission ground data systems, with a focus on localized data...

  4. 1980 Annual status report: operation of the high flux reactor

    International Nuclear Information System (INIS)

    1981-01-01

    HFR Petten has been operated in 1980 in fulfilment of the 1980/83 JRC Programme Decision. Both reactor operation and utilization data have been met within a few percent of the goals set out in the annual working schedule, in support of a large variety of research programmes. Major improvements to experimental facilities have been introduced during the year and future modernization has been prepared

  5. 77 FR 62247 - Dynamic Positioning Operations Guidance for Vessels Other Than Mobile Offshore Drilling Units...

    Science.gov (United States)

    2012-10-12

    ... Operations Guidance for Vessels Other Than Mobile Offshore Drilling Units Operating on the U.S. Outer... ``Mobile Offshore Drilling Unit Dynamic Positioning Guidance''. The notice recommended owners and operators of Mobile Offshore Drilling Units (MODUs) follow Marine Technology Society (MTS) Dynamic Positioning...

  6. Status of Advanced Stitched Unitized Composite Aircraft Structures

    Science.gov (United States)

    Jegley, Dawn C.; Velicki, Alex

    2013-01-01

    NASA has created the Environmentally Responsible Aviation (ERA) Project to explore and document the feasibility, benefits and technical risk of advanced vehicle configurations and enabling technologies that will reduce the impact of aviation on the environment. A critical aspect of this pursuit is the development of a lighter, more robust airframe that will enable the introduction of unconventional aircraft configurations that have higher lift-to-drag ratios, reduced drag, and lower community noise levels. The primary structural concept being developed under the ERA project in the Airframe Technology element is the Pultruded Rod Stitched Efficient Unitized Structure (PRSEUS) concept. This paper describes how researchers at NASA and The Boeing Company are working together to develop fundamental PRSEUS technologies that could someday be implemented on a transport size aircraft with high aspect ratio wings or unconventional shapes such as a hybrid wing body airplane design.

  7. Status of electricity trading in the United States

    International Nuclear Information System (INIS)

    McMillan, P.H.

    1999-01-01

    The evolution of the energy marketplace in the United States is presented in a series of overhead viewgraphs. The influencing factors of energy trading are described as being supply concentration, rate cross subsidization, price volatility, physics, stranded investment, market structure and value drivers. A map depicting trading hubs and market structures is included, along with an outline of the key characteristics of a successful market hub. Gas-electric interface issues are also discussed. It was stated that contrary to conventional wisdom that as gas and electricity markets converge, traders will routinely cross-hedge gas and power, the practical reality is that volatility of the gas to electricity basis spread actually limits hedging opportunities. A winning strategy should include thorough fundamental and technical analysis; every trade or position should have a well thought-out exit strategy; get closer to physical assets; and be careful across regional hubs and commodities. 2 tabs., 7 figs

  8. Operational status of the Brookhaven National Laboratory Accelerator Test Facility

    International Nuclear Information System (INIS)

    Batchelor, K.; Ben-Zvi, I.; Fernow, R.C.; Fischer, A.S.; Gallardo, J.; Jialin, Xie; Kirk, H.G.; Malone, R.G.; Parsa, Z.; Palmer, R.B.; Rao, T.; Rogers, J.; Sheehan, J.; Tsang, T.Y.F.; Ulc, S.; van Steenbergen, A.; Woodle, M.; Zhang, R.S.; Bigio, I.; Kurnit, N.; Shimada, T.; McDonald, K.T.; Russel, D.P.; Jiang, Z.Y.; Pellegrini, C.; Wang, X.J.

    1990-01-01

    Initial design parameters and early operational results of a 50 MeV high brightness electron linear accelerator are described. The system utilizes a radio frequency electron gun operating at a frequency of 2.856 GHz and a nominal output energy of 4.5 MeV followed by two, 2π/3 mode, disc loaded, traveling wave accelerating sections. The gun cathode is photo excited with short (6 psec) laser pulses giving design peak currents of a few hundred amperes. The system will be utilized to carry out infra-red FEL studies and investigation of new high gradient accelerating structures

  9. Human Immunodeficiency Viral Infection and Status Epilepticus in United States (2002-2009).

    Science.gov (United States)

    Chaudhry, Saqib A; Afzal, Mohammad Rauf; Rodriguez, Gustavo J; Majidi, Shahram; Bundlie, Scott; Hassan, Ameer E; Suri, M Fareed K; Qureshi, Adnan I

    2015-07-01

    To determine the association between human immunodeficiency virus (HIV) infection and status epilepticus and compare the outcomes of patients with status epilepticus with or without underlying HIV infection. Patients with primary diagnosis of status epilepticus (cases) and status asthmaticus (controls) were identified from the 2002-2009 Nationwide Inpatient Sample (NIS) which is representative of all admissions in the United States. We performed logistic regression analysis adjusting for age, gender, co-morbid conditions, including hypertension, diabetes mellitus (DM), renal failure, alcohol use, and opportunistic infections. We compared the in hospital outcomes among patients admitted with status epilepticus in strata defined by underlying HIV infection. The rate of concurrent status epilepticus and HIV has increased over the last 7 years in hospitalized patients with status epilepticus in United States (0.14%-0.27% pstatus epilepticus (odds ratio [OR]: 2.2; 95% confidence interval [CI]: 1.8-2.6; pstatus epilepticus patients with underlying HIV infection (17.5% vs. 9.9%, pstatus epilepticus. The proportion of patients admitted with concurrent status epilepticus and HIV infections is increasing and such patients have higher rates of poor discharge outcomes.

  10. 1982 Annual status report: operation of the high flux reactor

    International Nuclear Information System (INIS)

    1983-01-01

    The high flux materials testing reactor has been operated in 1982 within a few percent of the pre-set schedule, attaining 73% overall availability. Its utilization reached another record figure in 20 years: 81% without, 92% with, the low enrichment test elements irradiated during the year

  11. Greater Confinement Disposal trench and borehole operations status

    International Nuclear Information System (INIS)

    Harley, J.P. Jr.; Wilhite, E.L.; Jaegge, W.J.

    1987-01-01

    Greater Confinement Disposal (GCD) facilities have been constructed within the operating burial ground at the Savannah River Plant (SRP) to dispose of the higher activity fraction of SRP low-level waste. GCD practices of waste segregation, packaging, emplacement below the root zone, and waste stabilization are being used in the demonstration. 2 refs., 2 figs., 2 tabs

  12. International Students: A Comparison of Health Status and Physical Health before and after Coming to the United States

    Science.gov (United States)

    Msengi, Clementine M.; Msengi, Israel G.; Harris, Sandra; Hopson, Michael

    2011-01-01

    The purpose of this study was to assess the health status and physical health of international students at five American universities. International students in the United States were asked to compare the status of their health before and after coming to the United States. Findings suggested that health status of international students declined…

  13. Subjective social status and trajectories of self-rated health status: a comparative analysis of Japan and the United States.

    Science.gov (United States)

    Takahashi, Yoshimitsu; Fujiwara, Takeo; Nakayama, Takeo; Kawachi, Ichiro

    2017-11-28

    Japanese society is more egalitarian than the United States as is reflected by the lower degree of prevalence of social inequalities in health. We examined whether subjective socioeconomic status is associated with different trajectories of self-rated health (SRH), and whether this relationship differs between the United States and Japan. We analyzed the responses of 3968 Americans from the survey Midlife in the United States, 2004-06, and the responses of 989 Japanese from the survey Midlife in Japan, 2008. We conducted a multilevel analysis with three self-ratings of health (10 years ago, current and 10 years in the future) nested within individuals and nested within 10 levels of subjective social status. Age, sex, educational level and subjective financial situation were adjusted. After making statistical adjustments for confounding variables, respondents in Japan continued to report lower average levels of health. However, the rate of expected decline in SRH over the next decade was strongly socially patterned in the United States, whereas it was not in Japan. The Japanese showed no disparity in the anticipated trajectory of SRH over time, whereas the Americans showed a strong social class gradient in future trajectories of SRH. © The Author 2017. Published by Oxford University Press on behalf of Faculty of Public Health. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com

  14. Status of spent fuel management in the United Kingdom

    International Nuclear Information System (INIS)

    Dodds, R.

    1996-01-01

    Nuclear generating capacity in the UK is static with no units currently under construction following the completion of the Sizewell B PWR. The Government's reviews of nuclear energy policy and radioactive waste management policy have been published following a public consultation procedure, largely with an endorsement of current policies. Nuclear Electric plc (NE) and Scottish Nuclear Limited's (SNL) AGR and PWR stations are to be privatised as two subsidiaries of a holding company, and it is planned that the Magnox stations and their liabilities will be kept in the public sector, initially in a stand alone company but ultimately integrated with BNFL. Prompt reprocessing of all Magnox fuel will continue. NE and SNL have signed contracts for extensive reprocessing of AGR fuel. In addition, SNL has agreed contractual arrangements with BNFL for long term storage of its remaining overlife arisings of AGR fuel and has therefore on commercial ground opted not to dry store their fuel at the reactor site. NE have not yet made a decision on the fate of their AGR fuel not covered by existing reprocessing contracts. No option selection has taken place for PWR fuel. Following the closure of the Dounreay PFR and the withdrawal from the EFR project, the option of recycle of plutonium in fast reactors has been suspended. (author)

  15. Human Immunodeficiency Viral Infection and Status Epilepticus in United States (2002–2009)

    Science.gov (United States)

    Chaudhry, Saqib A.; Afzal, Mohammad Rauf; Rodriguez, Gustavo J.; Majidi, Shahram; Bundlie, Scott; Hassan, Ameer E.; Suri, M. Fareed K.; Qureshi, Adnan I.

    2015-01-01

    Objective To determine the association between human immunodeficiency virus (HIV) infection and status epilepticus and compare the outcomes of patients with status epilepticus with or without underlying HIV infection. Methods Patients with primary diagnosis of status epilepticus (cases) and status asthmaticus (controls) were identified from the 2002–2009 Nationwide Inpatient Sample (NIS) which is representative of all admissions in the United States. We performed logistic regression analysis adjusting for age, gender, co-morbid conditions, including hypertension, diabetes mellitus (DM), renal failure, alcohol use, and opportunistic infections. We compared the in hospital outcomes among patients admitted with status epilepticus in strata defined by underlying HIV infection. Results The rate of concurrent status epilepticus and HIV has increased over the last 7 years in hospitalized patients with status epilepticus in United States (0.14%–0.27% p<0.0001). The HIV infection was significantly associated with status epilepticus (odds ratio [OR]: 2.2; 95% confidence interval [CI]: 1.8–2.6; p<0.0001)) after adjusting for age, gender, opportunistic infections, and cardiovascular risk factors. The in-hospital mortality was significantly higher while discharge with none or minimal disability was significantly lower in status epilepticus patients with underlying HIV infection (17.5% vs. 9.9%, p<0.0001) and (50.4% vs. 63.3%, p<0.0001), respectively. Conclusions Our study suggests that there is a direct association between HIV infection and status epilepticus. The proportion of patients admitted with concurrent status epilepticus and HIV infections is increasing and such patients have higher rates of poor discharge outcomes. PMID:26301033

  16. Status of operation and utilization of JRR-4

    International Nuclear Information System (INIS)

    Tsuruta, H.; Niiho, T.; Matsuura, H.; Iida, K.; Ikeda, Y.; Funayama, Y.

    1988-01-01

    Japan Research Reactor No.4 (JRR-4) is a swimming pool type research reactor, 93% enriched uranium ETR-type fuel used, light water moderated and cooled. It was initially constructed to pursue mainly shielding experiments for nuclear ship. Today, it is widely utilized for many researches and experiments and reactor operation training of Nuclear Engineering School students. The construction of JRR-4 started in June 1962 and the initial criticality reached on January 28, 1965. The maximum power of JRR-4 was raised to 3500 kW in October 1976. The reactor has been operated satisfactorily for about 23 years since the initial criticality. In this paper, a general description is given on the JRR-4 including future plans. (author)

  17. The ICF Status and Plans in the United States

    International Nuclear Information System (INIS)

    Moses, E; Miller, G; Kauffman, R

    2005-01-01

    The United States continues to maintain its leadership in ICF as it moves toward the goal of ignition. The flagship of the program is the National Ignition Facility (NIF) presently under construction at LLNL. Experiments had begun on the first four beams of the National Ignition Facility just at the time of the last IFSA Conference. Several new successful campaigns have been conducted since then in planar hydrodynamics and hohlraums as well as activating the VISAR diagnostic for equation of state experiments. Highlights of these results will be reviewed. Presently, the four beam experimental capability has been suspended while the first eight beams are being installed as the first step in building out the project. Meanwhile, much progress has been made in developing ignition designs for using NIF. An array of designs having several ablator materials have been shown computationally to ignite with energies ranging from the design energy to as low as 1 MJ of laser energy. Alternative direct drive designs in the NIF indirect drive configuration have been developed by LLE. This wide array of design choices has increased the chance of achieving ignition sooner on the facility. Plans are now being developed to begin an ignition experimental campaign on NIF in 2010, a little over a year after completion of the facility. Other US facilities are also implementing improved capabilities. Petawatt lasers are now under construction at the University of Rochester and Sandia National Laboratory. The Z pulsed power machine at Sandia National Laboratory is being refurbished to improve its performance. The ongoing research program at the OMEGA laser at the University of Rochester and the Z machine at Sandia National Laboratory as well as at the Nike, Trident and Janus lasers remain strong, performing experiments supporting the NIF ignition plan and direct drive ignition. There also is an active program in the broader field of high energy density science on these facilities. These

  18. Cultural framework, anger expression, and health status in Russian immigrant women in the United States.

    Science.gov (United States)

    Bagdasarov, Zhanna; Edmondson, Christine B

    2013-01-01

    We investigated the role of anger expression and cultural framework in predicting Russian immigrant women's physical and psychological health status. One hundred Russian immigrant women between the ages of 30 and 65 completed questionnaires assessing anger expression, cultural framework, and health status. All research questions were addressed using hierarchical regression procedures. The results are discussed in terms of implications for understanding immigration experiences of Russian women who migrate from countries that are more collectivistic and less individualistic than the United States.

  19. JWST Wavefront Sensing and Control: Operations Plans, Demonstrations, and Status

    Science.gov (United States)

    Perrin, Marshall; Acton, D. Scott; Lajoie, Charles-Philippe; Knight, J. Scott; Myers, Carey; Stark, Chris; JWST Wavefront Sensing & Control Team

    2018-01-01

    After JWST launches and unfolds in space, its telescope optics will be aligned through a complex series of wavefront sensing and control (WFSC) steps to achieve diffraction-limited performance. This iterative process will comprise about half of the observatory commissioning time (~ 3 out of 6 months). We summarize the JWST WFSC process, schedule, and expectations for achieved performance, and discuss our team’s activities to prepare for an effective & efficient telescope commissioning. During the recently-completed OTIS cryo test at NASA JSC, WFSC demonstrations showed the flight-like operation of the entire JWST active optics and WFSC system from end to end, including all hardware and software components. In parallel, the same test data were processed through the JWST Mission Operations Center at STScI to demonstrate the readiness of ground system components there (such as the flight operations system, data pipelines, archives, etc). Moreover, using the Astronomer’s Proposal Tool (APT), the entire telescope commissioning program has been implemented, reviewed, and is ready for execution. Between now and launch our teams will continue preparations for JWST commissioning, including further rehearsals and testing, to ensure a successful alignment of JWST’s telescope optics.

  20. Licensed operating reactors. Status summary report, data as of August 31, 1983. Volume 8, No. 9

    International Nuclear Information System (INIS)

    1984-10-01

    This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  1. Safety evaluation report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    1987-03-01

    This report, Supplement No. 4 to the Safety Evaluation Report for the application filed by the Duquesne Light Company et al. (the applicant) for a license to operate the Beaver Valley Power Station, Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved when the Safety Evaluation Report and its Supplements 1, 2, and 3 were published

  2. Safety evaluation report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    1986-05-01

    This report, Supplement No. 1 to the Safety Evaluation Report for the application filed by the Duquesne Light Company et al. (the applicant) for a license to operate the Beaver valley Power Station, Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time the Safety Evaluation Report was published

  3. The ICF status and plans in the United States

    International Nuclear Information System (INIS)

    Moses, E.I.; Miller, G.H.; Kauffman, R.L.

    2006-01-01

    The United States continues to maintain its leadership in inertial confinement fusion as it moves toward the goal of ignition. The flagship of the program is the National Ignition Facility (NIF) presently under construction at Lawrence Livermore National Laboratory. Experiments had begun on the first four beams of the National Ignition Facility just at the time of the last IFSA Conference. Several new successful campaigns have been conducted since then in planar hydrodynamics and hohlraums as well as activating the VISAR diagnostic for equation of state experiments. Highlights of these results will be reviewed. Presently, the four beam experimental capability has been suspended while the first eight beams are being installed as the first step in building out the project. Meanwhile, much progress has been made in developing ignition designs for using NIF. An array of designs having several ablator materials have been shown computationally to ignite with energies ranging from the design energy to as low as 1 MJ of laser energy. Alternative direct drive designs in the NIF indirect drive configuration have been developed by LLE. This wide array of design choices has increased the chance of achieving ignition sooner on the facility. Plans are now being developed to begin an ignition experimental campaign on NIF in 2010, a little over a year after completion of the facility. Other US facilities are also implementing improved capabilities. Peta-watt lasers are now under construction at the University of Rochester and Sandia National Laboratory. The Z pulsed power machine at Sandia National Laboratory is being refurbished to improve its performance. The ongoing research program at the OMEGA laser at the University of Rochester and the Z machine at Sandia National Laboratory as well as at the Nike, Trident and Janus lasers remain strong, performing experiments supporting the NIF ignition plan and direct drive ignition. There also is an active program in the broader field of

  4. The ICF status and plans in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Moses, E.I.; Miller, G.H.; Kauffman, R.L. [Lawrence Livermore National Laboratory, Livermore, CA (United States)

    2006-06-15

    The United States continues to maintain its leadership in inertial confinement fusion as it moves toward the goal of ignition. The flagship of the program is the National Ignition Facility (NIF) presently under construction at Lawrence Livermore National Laboratory. Experiments had begun on the first four beams of the National Ignition Facility just at the time of the last IFSA Conference. Several new successful campaigns have been conducted since then in planar hydrodynamics and hohlraums as well as activating the VISAR diagnostic for equation of state experiments. Highlights of these results will be reviewed. Presently, the four beam experimental capability has been suspended while the first eight beams are being installed as the first step in building out the project. Meanwhile, much progress has been made in developing ignition designs for using NIF. An array of designs having several ablator materials have been shown computationally to ignite with energies ranging from the design energy to as low as 1 MJ of laser energy. Alternative direct drive designs in the NIF indirect drive configuration have been developed by LLE. This wide array of design choices has increased the chance of achieving ignition sooner on the facility. Plans are now being developed to begin an ignition experimental campaign on NIF in 2010, a little over a year after completion of the facility. Other US facilities are also implementing improved capabilities. Peta-watt lasers are now under construction at the University of Rochester and Sandia National Laboratory. The Z pulsed power machine at Sandia National Laboratory is being refurbished to improve its performance. The ongoing research program at the OMEGA laser at the University of Rochester and the Z machine at Sandia National Laboratory as well as at the Nike, Trident and Janus lasers remain strong, performing experiments supporting the NIF ignition plan and direct drive ignition. There also is an active program in the broader field of

  5. Aquifer test plan for the 100-HR-3 Operable Unit

    International Nuclear Information System (INIS)

    Swanson, L.C.; Hartman, M.J.

    1994-01-01

    This test plan directs hydrologic testing activities planned at three existing Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) wells in the 100-HR-3 Operable Unit of the Hanford Site. Three additional wells will be installed near these existing wells and used as additional testing arid observation points during the field activities. Figure 1 shows the locations of the three test sites. A primary objective of the testing program is to provide more detailed hydraulic characterization information for the unconfined aquifer and targeted test sites than provided by the initial reconnaissance-level slug testing of Vukelich. A second objective is to evaluate the applicability of slug interference and dipole flow tests for detailed hydraulic characterization in an unconfined aquifer. This aquifer testing program will also be useful for substantiating hydraulic conductivities reported from previous slug tests and evaluating the effects of filter pack volume/configuration on slug test data. Vukelich recommended additional testing to address the latter two issues

  6. Observation-status patients in children's hospitals with and without dedicated observation units in 2011.

    Science.gov (United States)

    Macy, Michelle L; Hall, Matthew; Alpern, Elizabeth R; Fieldston, Evan S; Shanley, Leticia A; Hronek, Carla; Hain, Paul D; Shah, Samir S

    2015-06-01

    Pediatric observation units (OUs) have demonstrated reductions in lengths of stay (LOS) and costs of care. Hospital-level outcomes across all observation-status stays have not been evaluated in relation to the presence of a dedicated OU in the hospital. To compare observation-status stay outcomes in hospitals with and without a dedicated OU. Cross-sectional analysis of hospital administrative data. Observation-status stay outcomes were compared in hospitals with and without a dedicated OU across 4 categories: (1) LOS, (2) standardized costs, (3) conversion to inpatient status, and (4) return care. Observation-status stays in 31 free-standing children's hospitals contributing observation patient data to the Pediatric Health Information System database, 2011. Fifty-one percent of the 136,239 observation-status stays in 2011 occurred in 14 hospitals with a dedicated OU; the remainder were in 17 hospitals without. The percentage of observation-status same-day discharges was higher in hospitals with a dedicated OU compared with hospitals without (23.8 vs 22.1, P hospitals with a dedicated OU (11.06%) compared with hospitals without (9.63%, P hospital-level outcomes. Inclusion of location of care (eg, dedicated OU, inpatient unit, emergency department) in hospital administrative datasets would allow for more meaningful comparisons of models of hospital care. © 2015 Society of Hospital Medicine.

  7. Present status of operation of the ETE spherical tokamak

    International Nuclear Information System (INIS)

    Bosco, E. del; Berni, L.A.; Ferreira, J.G.; Oliveira, R.M.; Ludwig, G.O.; Shibata, C.S.

    2005-01-01

    The ETE is a spherical tokamak with aspect ratio A = 1.5 (major radius of 0.3m and minor radius of 0.2m) under development at LAP/INPE. The ETE incorporates some innovative features that resulted in a compact and light weighted device with good plasma accessibility. Since the first plasma obtained at the very end of 2000 (Ip = 12kA, duration of 2ms, B o = 0.1T), the machine is operational and improvements are being done in order to achieve the planned final parameter values for the first phase of operation (Ip = 220kA, duration 15ms, B o = 0.4T), which are limited by the available capacitors. The efforts are being focused on incrementing the energy of the capacitor banks, lessening the stray magnetic fields in the plasma region, conditioning the vacuum vessel wall, implementing diagnostics and optimizing the discharge parameters. Presently, plasma currents in the range of 40-60kA (duration of 6-12 ms) are routinely obtained. Electron temperatures up to 160eV and plasma densities up to 3.0x10 19 m -3 are being reached. (author)

  8. Operational status of the Los Alamos neutron science center (LANSCE)

    Energy Technology Data Exchange (ETDEWEB)

    Jones, Kevin W [Los Alamos National Laboratory; Erickson, John L [Los Alamos National Laboratory; Schoenberg, Kurt F [Los Alamos National Laboratory

    2010-01-01

    The Los Alamos Neutron Science Center (LANSCE) accelerator and beam delivery complex generates the proton beams that serve three neutron production sources; the thermal and cold source for the Manuel Lujan Jr. Neutron Scattering Center, the Weapons Neutron Research (WNR) high-energy neutron source, and a pulsed Ultra-Cold Neutron Source. These three sources are the foundation of strong and productive multi-disciplinary research programs that serve a diverse and robust user community. The facility also provides multiplexed beams for the production of medical radioisotopes and proton radiography of dynamic events. The recent operating history of these sources will be reviewed and plans for performance improvement will be discussed, together with the underlying drivers for the proposed LANSCE Refurbishment project. The details of this latter project are presented in a separate contribution.

  9. Actual status of project Mochovce NPP units 3 and 4 completion

    International Nuclear Information System (INIS)

    Niznan, S.

    2005-01-01

    In this presentation author deals with actual status of project Mochovce NPP units 3 and 4 completion. Present state of Mochovce NPP, Units 3 and 4 enables real assumption to completion. It is expected that such supplier companies can be used which are experienced in field of nuclear projects. Based on budget of 2002, it seems that completion costs of 45 billions SKK are real. These figures were confirmed by study performed by TRACTEBEL in 2004. Based on experience from Bohunice NPP completion as well as from Mochovce NPP, Units 1 and 2 completion and if decision milestone and project start up deadlines will be observed according to modified preliminary schedule of Mochovce NPP Units 3 and 4 completion, it seems as real that Unit 3 will be completed till 06/2011 and Unit 4 - till 12/2011.

  10. The current status of geothermal direct use development in the United States

    International Nuclear Information System (INIS)

    Lund, J.W.; Lienau, P.J.; Culver, G.G.

    1990-01-01

    In this paper information is provided on the status of geothermal direct heat utilization in the United States, with emphasis on developments from 1985 to 1990. A total of 452 sites, which include approximately 130,000 individual installations, have been identified with an annual energy use of 19.7 x 10 12 kJ. Approximately 44% of this use is due to enhanced oil recovery in four midwestern states, and 30% is due to geothermal heat pumps. Since 1985, 25 new projects, which include approximately 200 individual installations, and representing a thermal capacity of 106.7 MWt and annual energy utilization of 1.1 x 10 12 kJ, have become operational or are under construction. Earth-coupled and groundwater heat pumps, representing the largest growth sector during this period, add an additional 400 MWt and 1.2 x 10 12 kJ to these figures. Geothermal heat pumps have extended geothermal direct heat use into almost every state in the nation. Slightly over 200 direct heat geothermal wells, averaging 150 m in depth, along with approximately 30,000 heat pump wells, have been drilled for these projects. Between 20 and 25 professional man-years of effort are estimated to have been allocated to geothermal direct heat projects during each of the five years

  11. Status and Operation of the Linac4 Ion Source Prototypes

    CERN Document Server

    Lettry, J; Andersson, P; Bertolo, S; Butterworth, A; Coutron, Y; Dallocchio, A; Chaudet, E; Gil-Flores, J; Guida, R; Hansen, J; Hatayama, A; Koszar, I; Mahner, E; Mastrostefano, C; Mathot, S; Mattei, S; Midttun, O; Moyret, P; Nisbet, D; Nishida, K; O’Neil, M; Ohta, M; Paoluzzi, M; Pasquino, C; Pereira, H; Rochez, J; Sanchez Alvarez, J; Sanchez Arias, J; Scrivens, R; Shibata, T; Steyaert, D; Thaus, N; Yamamoto, T

    2014-01-01

    CERN’s Linac4 45 kV H- ion sources prototypes are installed at a dedicated ion source test stand and in the Linac4 tunnel. The operation of the pulsed hydrogen injection, RF sustained plasma and pulsed high voltages are described. The first experimental results of two prototypes relying on 2MHz RF- plasma heating are presented. The plasma is ignited via capacitive coupling, and sustained by inductive coupling. The light emitted from the plasma is collected by viewports pointing to the plasma chamber wall in the middle of the RF solenoid and to the plasma chamber axis. Preliminary measurements of optical emission spectroscopy and photometry of the plasma have been performed. The design of a cesiated ion source is presented. The volume source has produced a 45 keV H- beam of 16-22 mA which has successfully been used for the commissioning of the Low Energy Beam Transport (LEBT), Radio Frequency Quadrupole (RFQ) accelerator and chopper of Linac4.

  12. Status of the TESS Science Processing Operations Center

    Science.gov (United States)

    Jenkins, Jon M.; Twicken, Joseph D.; Campbell, Jennifer; Tenebaum, Peter; Sanderfer, Dwight; Davies, Misty D.; Smith, Jeffrey C.; Morris, Rob; Mansouri-Samani, Masoud; Girouardi, Forrest; hide

    2017-01-01

    The Transiting Exoplanet Survey Satellite (TESS) science pipeline is being developed by the Science Processing Operations Center (SPOC) at NASA Ames Research Center based on the highly successful Kepler Mission science pipeline. Like the Kepler pipeline, the TESS science pipeline will provide calibrated pixels, simple and systematic error-corrected aperture photometry, and centroid locations for all 200,000+ target stars, observed over the 2-year mission, along with associated uncertainties. The pixel and light curve products are modeled on the Kepler archive products and will be archived to the Mikulski Archive for Space Telescopes (MAST). In addition to the nominal science data, the 30-minute Full Frame Images (FFIs) simultaneously collected by TESS will also be calibrated by the SPOC and archived at MAST. The TESS pipeline will search through all light curves for evidence of transits that occur when a planet crosses the disk of its host star. The Data Validation pipeline will generate a suite of diagnostic metrics for each transit-like signature discovered, and extract planetary parameters by fitting a limb-darkened transit model to each potential planetary signature. The results of the transit search will be modeled on the Kepler transit search products (tabulated numerical results, time series products, and pdf reports) all of which will be archived to MAST.

  13. 100-HR-2 Operable Unit Focused Feasibility study report

    International Nuclear Information System (INIS)

    1995-01-01

    The standard Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) Feasibility Study (FS) includes development and screening of alternatives (Phases 1 and 2) and the detailed analysis of alternatives (Phase 3). This focused feasibility study (FFS) was conducted for the 100-HR-2 Operable Unit (OU) at the Hanford Site in southeastern Washington. This FFS constitutes the Phase 3 portion of the FS process for the remedial alternatives initially developed and screened in the 100 Area Feasibility Study Phases 1 and 2 (DOE-RL 1993a). The objective of this OU-specific FFS is to provide decision makers with sufficient information to allow appropriate and timely selection of interim remedial measures (IRM) for the seven IRM candidate sites associated with the 100-HR-2 OU. The IRM candidate waste sites identified in Table ES-1 are determined in the limited field investigation (DOE-RL 1994b). Site profiles are developed for each of these waste sites. The site profiles are used in the application of the plug-in approach. The waste site either plugs into the analysis of the alternatives for the group, or deviations from the developed group alternatives are described and documented. A summary for the 100-HR-2 IRM candidate waste site is as follows: none of the waste sites require additional alternative development. six of the seven waste sites directly plug into the waste site group alternatives. The site-specific detailed analysis is conducted, referencing the waste site group analysis as appropriate. A waste site detailed analysis summary is presented in Table ES-1.A comparative analysis of remedial alternatives is presented for each waste site. A summary of the comparative analysis is presented in Table ES-2

  14. Factors Associated With Perceived Health Status of Multiracial/Ethnic Midlife Women in the United States.

    Science.gov (United States)

    Ko, Young; Chee, Wonshik; Im, Eun-Ok

    2016-01-01

    To identify racial/ethnic differences in perceived health status and differences in the factors associated with perceived health status of midlife women in four broad racial/ethnic groups in the United States. A secondary analysis of Web-based survey data. Internet communities/groups among midlife women and Internet communities/groups of racial/ethnic minorities. Participants included 491 women 40 to 60 years of age who self-identified into four broad racial/ethnic categories (Hispanic, non-Hispanic [N-H] Asian American, N-H African American, or N-H White). Data related to participants' sociodemographic, behavioral, situational, and individual health factors and their coping resources were selected based on the Comprehensive Health Seeking and Coping Paradigm. Multiple logistic regression analyses were used to identify racial/ethnic differences in perceived health status and race/ethnicity-specific factors associated with perceived health status among midlife women. Perceived health status did not differ by race/ethnicity; however, factors that were associated with perceived health status did vary by race/ethnicity. Among N-H White women, educational level, level of family income, obesity, and menopausal symptoms were significantly associated with perceived not healthy status. In Hispanic women, perceived level of physical activity and obesity were significantly associated with not healthy status. Perceived level of physical activity was the only factor significantly associated with not healthy status in N-H Asian American women, and the level of family income was the only factor associated with not healthy status in N-H African American women. In future intervention development, researchers need to consider differences among racial/ethnic groups in the factors associated with women's perceived health status. Copyright © 2016 AWHONN, the Association of Women’s Health, Obstetric and Neonatal Nurses. Published by Elsevier Inc. All rights reserved.

  15. Sex Differences in Mortality Based on United Network for Organ Sharing Status While Awaiting Heart Transplantation.

    Science.gov (United States)

    Hsich, Eileen M; Blackstone, Eugene H; Thuita, Lucy; McNamara, Dennis M; Rogers, Joseph G; Ishwaran, Hemant; Schold, Jesse D

    2017-06-01

    There are sex differences in mortality while awaiting heart transplantation, and the reason remains unclear. We included all adults in the Scientific Registry of Transplant Recipients placed on the heart transplant active waitlist from 2004 to 2015. The primary end point was all-cause mortality. Multivariable Cox proportional hazards models were performed to evaluate survival by United Network for Organ Sharing (UNOS) status at the time of listing. Random survival forest was used to identify sex interactions for the competing risk of death and transplantation. There were 33 069 patients (25% women) awaiting heart transplantation. This cohort included 7681 UNOS status 1A (26% women), 13 027 UNOS status 1B (25% women), and 12 361 UNOS status 2 (26% women). During a median follow-up of 4.3 months, 1351 women and 4052 men died. After adjusting for >20 risk factors, female sex was associated with a significant risk of death among UNOS status 1A (adjusted hazard ratio, 1.14; 95% confidence interval, 1.01-1.29) and UNOS status 1B (adjusted hazard ratio, 1.17; 95% confidence interval, 1.05-1.30). In contrast, female sex was significantly protective for time to death among UNOS status 2 (adjusted hazard ratio, 0.85; 95% confidence interval, 0.76-0.95). Sex differences in probability of transplantation were present for every UNOS status, and >20 sex interactions were identified for mortality and transplantation. When stratified by initial UNOS status, women had a higher mortality than men as UNOS status 1 and a lower mortality as UNOS status 2. With >20 sex interactions for mortality and transplantation, further evaluation is warranted to form a more equitable allocation system. © 2017 American Heart Association, Inc.

  16. Licensing Status of New and Expanding In-Situ Recovery Uranium Projects in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Catchpole, G.; Thomas, M., E-mail: gccatchpole@uranerz.com [Uranerz Energy Corporation (URZ), Casper, WY (United States)

    2014-05-15

    The authors investigated the licensing status of new in-situ recovery (“ISR”) uranium projects, as well as the expansion of existing projects, within the United States (“US”). Specific emphasis and analysis is placed on those projects within the states of Texas and Wyoming. Of note, information used to prepare this paper was obtained from public sources that included company web sites, the US Securities and Exchange Commission, the US Nuclear Regulatory Commission (“NRC”), the US Energy Information Agency (“EIA”), and the relevant state regulatory agencies. The renewed interest in the production of natural uranium has been motivated, in part, by the increased sale price of yellowcake beginning around 2003 resulting in numerous new and existing natural resources companies acquiring mineral rights in the United States. Because of the economic favorability in terms of both operating and capital costs of ISR mines versus conventional mines in the US (with its relatively low grade of uranium ore), the model for most companies was to acquire mineral properties that had the potential for being mined using the ISR method. There were, however, exceptions to this model. The Uravan mineral district in southwest Colorado and southeast Utah, where relatively high-grade, shallow uranium deposits have the potential to be mined using underground methods, is one such exception. However, the focus of this paper will be on ISR projects. In Wyoming, which has been the top producer of natural uranium among the 50 states for the past seven years, there is one producing ISR mine (Bill Smith — Highland), one ISR mine on standby (Christensen Ranch), and two ISR uranium projects licensed but not yet built (Gas Hills and North Butte). Cameco Resources is planning to develop two ISR projects in Wyoming that have been licensed but not yet constructed. Additionally, three new uranium companies (Ur-Energy, Uranerz and Uranium One) have filed applications with the federal and

  17. Operating status of TARN vacuum system and future tasks

    International Nuclear Information System (INIS)

    Chida, Katsuhisa; Tsujikawa, Hiroshi; Mizobuchi, Akira

    1981-01-01

    TARN (Test Accumulation Ring for Numatron) was constructed for the purpose of obtaining the fundamental data for high energy heavy ion accelerator (Numatron) project, which accelerates heavy ions up to uranium to 1 GeV/nucleon. Its vacuum is required to be 1 x 10 - 10 Torr or less on beam. In February, 1972, only the vacuum system was temporarily assembled, and the vacuum of 2 x 10 - 11 Torr was realized by baking at 300 deg C alone. In July, 1972, the assembling of the vacuum chamber into magnets was completed, and several test experiments were performed using the H 2+ beam from the SF cyclotron. In this report, first, the outline of the vacuum system, and next, its operation are described. For the reason of the purpose of the ring, the vacuum system is required to be atmospheric pressure to attach beam monitors and other measuring instruments just before the machine time. Therefore, it is an important task to make the evacuation time as short as possible. As future tasks, the examination on the material and shape of the chamber, the investigation of pump system (appropriate combination of ion pump, titanium sublimation pump, cryo-pump, molecular pump, etc.), the study on the measuring and control systems (accurate measurement of total pressure and partial pressure and the feedback to the protecting system), the studies of problems on the vacuum wall surface (surface treatment prior to assembling the chamber into the ring and the methods and the effects of baking and electric discharge cleaning) are included. (Wakatsuki, Y.)

  18. Status of the TESS Science Processing Operations Center

    Science.gov (United States)

    Jenkins, Jon Michael; Caldwell, Douglas A.; Davies, Misty; Li, Jie; Morris, Robert L.; Rose, Mark; Smith, Jeffrey C.; Tenenbaum, Peter; Ting, Eric; Twicken, Joseph D.; Wohler, Bill

    2018-06-01

    The Transiting Exoplanet Survey Satellite (TESS) was selected by NASA’s Explorer Program to conduct a search for Earth’s closest cousins starting in 2018. TESS will conduct an all-sky transit survey of F, G and K dwarf stars between 4 and 12 magnitudes and M dwarf stars within 200 light years. TESS is expected to discover 1,000 small planets less than twice the size of Earth, and to measure the masses of at least 50 of these small worlds. The TESS science pipeline is being developed by the Science Processing Operations Center (SPOC) at NASA Ames Research Center based on the highly successful Kepler science pipeline. Like the Kepler pipeline, the TESS pipeline provides calibrated pixels, simple and systematic error-corrected aperture photometry, and centroid locations for all 200,000+ target stars observed over the 2-year mission, along with associated uncertainties. The pixel and light curve products are modeled on the Kepler archive products and will be archived to the Mikulski Archive for Space Telescopes (MAST). In addition to the nominal science data, the 30-minute Full Frame Images (FFIs) simultaneously collected by TESS will also be calibrated by the SPOC and archived at MAST. The TESS pipeline searches through all light curves for evidence of transits that occur when a planet crosses the disk of its host star. The Data Validation pipeline generates a suite of diagnostic metrics for each transit-like signature, and then extracts planetary parameters by fitting a limb-darkened transit model to each potential planetary signature. The results of the transit search are modeled on the Kepler transit search products (tabulated numerical results, time series products, and pdf reports) all of which will be archived to MAST. Synthetic sample data products are available at https://archive.stsci.edu/tess/ete-6.html.Funding for the TESS Mission has been provided by the NASA Science Mission Directorate.

  19. Chapter 6. Conservation status of flammulated owls in the United States

    Science.gov (United States)

    D. Archibald McCallum

    1994-01-01

    The status of the flammulated owl will be evaluated in this chapter by asking a series of critical questions about the species and its habitat. Answers to these questions will be used to reach one of the following conclusions: (1) populations in the United States are secure and will likely remain so given current land management practices; (2) populations are in peril...

  20. The Status of High School Online Physical Education in the United States

    Science.gov (United States)

    Daum, David Newman; Buschner, Craig

    2012-01-01

    Online learning is changing the educational landscape despite the limited empirical research and conflicting results about its effectiveness to produce student learning. The purpose of this study was to describe the status of online physical education (OLPE) in the United States. Surveys were sent to forty-five high school online physical…

  1. Status of networking for high energy physics in the United States

    International Nuclear Information System (INIS)

    Kunz, P.F.

    1985-06-01

    Networks are used extensively for High Energy Physics in the United States. Although the networks have grown in an ad hoc manner with connections typically being made to satisfy the needs of one detector group, they now encompass to large fraction of the US HEP community in one form or another. This paper summarizes the current status and experience with networks

  2. Conservation status of the freshwater mussels of the United States and Canada

    Science.gov (United States)

    James D. Williams; Melvin L. Warren; Kevin S. Cummings; John L. Harris; Richard J. Neves

    1992-01-01

    The American Fisheries Society (AFS) herein provides a list of all native freshwater mussels (families Margaritiferidae and Unionidae) in the United States and Canada. This report also provides state and provincial distributions; a comprehensive review of the conservation status of all taxa; and references on biology, conservation, and distribution of freshwater...

  3. Early Childhood Inclusion in the United States: Goals, Current Status, and Future Directions

    Science.gov (United States)

    Guralnick, Michael J.; Bruder, Mary Beth

    2016-01-01

    The current status and future directions of early childhood inclusion in the United States are discussed from the perspective of 4 key goals: access, accommodations and feasibility, developmental progress, and social integration. Recommendations are put forward to promote inclusion goals emphasizing administrative structures, personnel…

  4. Operator support system for power unit control in abnormal modes of operation

    International Nuclear Information System (INIS)

    Kurka, J.

    1993-01-01

    I and C system technology, partly Soviet and partly Czechoslovakian, used on the NPP Dukovany units represents the control technology standard of late 70-ties and it becomes the weak part of the whole system. The modernization of the system, therefore, is necessary and it is already in preparation. The specification of both the scope and the depth of upgrading/replacement is being carried out within the framework of the PHARE program. The second phase of the program aimed at the final specifications of requirements on new I and C system is in progress. The output will serve as detailed specification for bid invitation for control system supplier. Parallely, the preparation of specification for WWER-440 full-scope plant simulator for operator training is in progress as well. In the case of two units with WWER-1000 MW reactors, the completion of construction of which was even threaten for a certain period of time, essential changes have taken place in the design of both the I and C systems and the reactor core. 7 figs

  5. 40 CFR 60.105a - Monitoring of emissions and operations for fluid catalytic cracking units (FCCU) and fluid coking...

    Science.gov (United States)

    2010-07-01

    ..., Catalytic Reforming Units, and Sulfur Recovery Units. (iii) The owner or operator shall install, operate... for fluid catalytic cracking units (FCCU) and fluid coking units (FCU). 60.105a Section 60.105a... and operations for fluid catalytic cracking units (FCCU) and fluid coking units (FCU). (a) FCCU and...

  6. 77 FR 29701 - Impact of Construction (Under a Combined License) of New Nuclear Power Plant Units on Operating...

    Science.gov (United States)

    2012-05-18

    ... New Nuclear Power Plant Units on Operating Units at Multi-Unit Sites AGENCY: Nuclear Regulatory... construct and operate new nuclear power plants (NPPs) on multi-unit sites to provide an evaluation of the... License) of New Nuclear Power Plants on Operating Units at Multi-Unit Sites (Package). ML112630039 Federal...

  7. 2016 Highlights of Ferry Operations in the United States

    Science.gov (United States)

    2017-10-01

    This publication highlights data collected by the 2016 NCFO. The Bureau of Transportation Statistics (BTS) conducted the NCFO from April through November 2016, collecting the operational characteristics of the 2015 calendar year ferry operations.

  8. Ergonomic relationship during work in nursing staff of intensive care unit with operating room

    Directory of Open Access Journals (Sweden)

    Yousef Mahmoudifar

    2017-01-01

    Full Text Available Background and Objectives: High prevalence of work-related musculoskeletal disorders, especially in jobs such as nursing which covers tasks like patients' repositioning, has attracted great attentions from occupational healthcare experts to necessitate the knowledge of ergonomic science. Therefore, this study was performed aiming at ergonomic relationship during work in nursing staff of Intensive Care Unit (ICU with operating room. Materials and Methods: In this descriptive-analytical study (cohort, fifty personnel of ICU staff and fifty of operating room staff were selected through a census method and were assessed using tools such as Nordic questionnaire and Rapid Entire Body Assessment (REBA standards in terms of body posture ergonomics. The obtained data were analyzed by SPSS software and Chi-Square test after collection. Results: The most complaints were from the operating room group (68% and ICU staff (60% for the lumbar musculoskeletal system. There was a significant relationship between the total REBA scores of body, legs, neck, arm, force status, load fitting with hands and static or dynamic activities in the operating room and ICU staff groups (P < 0.05. In operating room and ICU groups, most subjects obtained score 11–15 and very high-risk level. Conclusion: Nurses working at operating room and ICU ward are subjected to high-risk levels and occupational injuries which is dramatically resulted from inappropriate body posture or particular conditions of their works. As a result, taking corrective actions along with planning and identifying ways will help prohibiting the prevalence of disorders in the future.

  9. Unit information system operational displays for VVER-1000 reactors

    International Nuclear Information System (INIS)

    Anikanov, S.S.; Carrera, J.P.; Gordon, P.

    1997-01-01

    The role of high level operational displays is explained as well as the principles of the design of such displays. The tasks of WWER operating personnel are described and the support provided by operational displays is highlighted. The architecture of the displays is also dealt with. (A.K.)

  10. United States Military in Central Asia: Beyond Operation Enduring Freedom

    Science.gov (United States)

    2009-10-23

    Malinowski , advocacy director for Human Rights Watch, stated, “the United States is most effective in promoting liberty around the world when people...26 U.S. President, The National Security Strategy of the United States of America, page? 27 Thomas Malinowski , “Testimony

  11. Impact of County-Level Socioeconomic Status on Oropharyngeal Cancer Survival in the United States.

    Science.gov (United States)

    Megwalu, Uchechukwu C

    2017-04-01

    Objective To evaluate the impact of county-level socioeconomic status on survival in patients with oropharyngeal cancer in the United States. Study Design Retrospective cohort study via a large population-based cancer database. Methods Data were extracted from the SEER 18 database (Surveillance, Epidemiology, and End Results) of the National Cancer Institute. The study cohort included 18,791 patients diagnosed with oropharyngeal squamous cell carcinoma between 2004 and 2012. Results Patients residing in counties with a low socioeconomic status index had worse overall survival (56.5% vs 63.0%, P socioeconomic status index. On multivariable analysis, residing in a county with a low socioeconomic status index was associated with worse overall survival (hazard ratio, 1.21; 95% CI, 1.14-1.29; P status, year of diagnosis, site, American Joint Committee on Cancer stage group, presence of distant metastasis, presence of unresectable tumor, histologic grade, surgical resection of primary site, treatment with neck dissection, and radiation therapy. Conclusion Residing in a county with a low socioeconomic status index is associated with worse survival. Further research is needed to elucidate the mechanism by which socioeconomic status affects survival in oropharyngeal cancer.

  12. How Can the United States Army Improve Human Intelligence in Peace Operations?

    National Research Council Canada - National Science Library

    Wright, David

    2003-01-01

    .... These secondary collectors, such as the Military Police, Psychological Operations, Civil Affairs and Line Units conduct liaison with international and local police forces, host-government official...

  13. Race/ethnicity, socioeconomic status, and ALS mortality in the United States.

    Science.gov (United States)

    Roberts, Andrea L; Johnson, Norman J; Chen, Jarvis T; Cudkowicz, Merit E; Weisskopf, Marc G

    2016-11-29

    To determine whether race/ethnicity and socioeconomic status are associated with amyotrophic lateral sclerosis (ALS) mortality in the United States. The National Longitudinal Mortality Study (NLMS), a United States-representative, multistage sample, collected race/ethnicity and socioeconomic data prospectively. Mortality information was obtained by matching NLMS records to the National Death Index (1979-2011). More than 2 million persons (n = 1,145,368 women, n = 1,011,172 men) were included, with 33,024,881 person-years of follow-up (1,299 ALS deaths , response rate 96%). Race/ethnicity was by self-report in 4 categories. Hazard ratios (HRs) for ALS mortality were calculated for race/ethnicity and socioeconomic status separately and in mutually adjusted models. Minority vs white race/ethnicity predicted lower ALS mortality in models adjusted for socioeconomic status, type of health insurance, and birthplace (non-Hispanic black, HR 0.61, 95% confidence interval [CI] 0.48-0.78; Hispanic, HR 0.64, 95% CI 0.46-0.88; other races, non-Hispanic, HR 0.52, 95% CI 0.31-0.86). Higher educational attainment compared with socioeconomic status, birthplace, or type of health insurance. Higher rate of ALS among whites likely reflects actual higher risk of ALS rather than ascertainment bias or effects of socioeconomic status on ALS risk. © 2016 American Academy of Neurology.

  14. USE OF ELECTRONIC CASE HISTORIES IN OPERATION OF MEDICAL UNITS

    Directory of Open Access Journals (Sweden)

    I. B. Boltenkova

    2016-01-01

    Full Text Available Introduction of electronic case histories to medical units including TB units is one of the factors allowing enhancing quality of medical care provision. Use of the electronic case histories provides conditions for information transparency improvement in a medical unit: financial, statistic and medico-technological. Information contained in the electronic case history is important and required both for internal and external use. Use of electronic case histories contributes to reduction of labor costs of workers in medical units, provides fast access of medical personnel to information, formalizes data, provides preservation, invariance and reliability of the information entered into electronic case history during the whole period of storage, regulates the access rights and confidentiality, personifies data and allows unifying health data of all Russian population into one pool.

  15. Design and operation of gas-heated thermal pumping units

    Energy Technology Data Exchange (ETDEWEB)

    Rostek, H A [Ruhrgas A.G., Essen (Germany, F.R.)

    1979-03-01

    The first gas heat pump systems have been operated since spring 1977. These are applied in living houses, school, swimming pools, and sport places and administration buildings. The heating performance of these systems is 150-3800 kW. Two of these systems, one in a swimming pool and one in a house for several families are operating, each of them for one heating period. The operational experiences with these gas heat pumps are reported on, basing on measurement results. The experience gathered from the operation of gas heat pumps systems is applied to the planning of other plants. The development of a standardized gas heat pump-series is emphasized.

  16. Licensed operating reactors. Status summary report, data as of April 30, 1986

    International Nuclear Information System (INIS)

    1986-05-01

    This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent storage capability, reactor years of experience and non-power reactors in the United States

  17. Licensed operating reactors. Status summary report, data as of February 28, 1986. Volume 10, No. 3

    International Nuclear Information System (INIS)

    1986-04-01

    This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  18. Licensed operating reactors status summary report, data as of August 31, 1985. Volume 9, No. 9

    International Nuclear Information System (INIS)

    1985-10-01

    This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  19. Licensed operating reactors. Status summary report, data as of May 31, 1986. Volume 10, Number 6

    International Nuclear Information System (INIS)

    1986-08-01

    This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  20. Licensed operating reactors. Status summary report: data as of July 31, 1985. Volume 9, No. 8

    International Nuclear Information System (INIS)

    1985-09-01

    This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Head-quarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capabilitiy, reactor years of experience and non-power reactors in the United States

  1. Licensed operating reactors: Status summary report data as of 06-30-86

    International Nuclear Information System (INIS)

    1986-11-01

    This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  2. Licensed operating reactors. Status summary report data as of January 31, 1986. Volume 10, No. 2

    International Nuclear Information System (INIS)

    1986-03-01

    This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  3. Socioeconomic status and risk of intensive care unit admission with sepsis

    DEFF Research Database (Denmark)

    Storm, L; Schnegelsberg, A; Mackenhauer, J

    2018-01-01

    BACKGROUND: A recent study showed higher risk of bacteremia among individuals with low socioeconomic status (SES). We hypothesized that patients with a low SES have a higher risk of intensive care unit (ICU) admission with sepsis compared to patients with higher SES. METHODS: This was a case......, yearly income, cohabitation status, and occupation. The odds ratio (OR) of being admitted with sepsis to the ICU was calculated using conditional logistic regression, adjusting for the Charlson Comorbidity Index and the remaining socioeconomic variables. RESULTS: The adjusted odds of being admitted...

  4. US central station nuclear electric generating units: significant milestones (status as of July 1, 1980)

    International Nuclear Information System (INIS)

    1980-09-01

    The status of 189 US nuclear power plants is reported in a table which gives the name, owner, capacity, type, NSSS architect and contractor and data of public announcement, NSSS order, licensing, and initial operation. The plants are also indexed according to state, region, utility, and alphabetical name. The utility nuclear steam supply system orders are also listed

  5. Operational test procedure for SY tank farm replacement exhauster unit

    International Nuclear Information System (INIS)

    McClees, J.

    1995-01-01

    This operational test procedure will verify that the remaining functions not tested per WHC-SD-WM-ATP-080, or components disturbed during final installation, as well as interfaces with other tank farm equipment and remote monitoring stations are operating correctly

  6. BN-600 power unit 15-year operating experience

    International Nuclear Information System (INIS)

    Saraev, O.M.; Oshkanov, N.N.; Vylomov, V.V.

    1996-01-01

    Comprehensive experience has been gained with the operating fast reactor BN-600 with a power out of 600 MWe. This paper includes important performance results and gives also an overview of the experience gained from BN-600 NPP commercial operation during 15 years. (author). 2 figs, 1 tab

  7. Phase I remedial investigation report for the 300-FF-5 operable unit, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-01-01

    The focus of this remedial investigation (RI) is the 300-FF-5 operable unit, one of five operable units associated with the 300 Area aggregate of the U.S. Department of Energy`s (DOE`s) Hanford Site. The 300-FF-5 operable unit is a groundwater operable unit beneath the 300-FF-1, 300-FF-2, and 300-FF-3 source operable units. This operable unit was designated to include all contamination detected in the groundwater and sediments below the water table that emanates from the 300-FF-1, 300-FF-2, and 300-FF-3 operable units (DOE-RL 1990a). In November 1989, the U.S. Environmental Protection Agency (EPA) placed the 300 Area on the National Priorities List (NPL) contained within Appendix B of the National Oil and Hazardous Substance Pollution Contingency Plan (NCP, 53 FR 51391 et seq.). The EPA took this action pursuant to their authority under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA, 42 USC 9601 et seq.). The DOE Richland Operations Office (DOE-RL), the EPA and Washington Department of Ecology (Ecology) issued the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), in May 1989 (Ecology et al. 1992, Rev. 2). This agreement, among other matters, governs all CERCLA efforts at the Hanford Site. In June 1990, a remedial investigation/feasibility study (RI/FS) workplan for the 300-FF-5 operable unit was issued pursuant to the Tri-Party Agreement.

  8. Phase I remedial investigation report for the 300-FF-5 operable unit, Volume 1

    International Nuclear Information System (INIS)

    1994-01-01

    The focus of this remedial investigation (RI) is the 300-FF-5 operable unit, one of five operable units associated with the 300 Area aggregate of the U.S. Department of Energy's (DOE's) Hanford Site. The 300-FF-5 operable unit is a groundwater operable unit beneath the 300-FF-1, 300-FF-2, and 300-FF-3 source operable units. This operable unit was designated to include all contamination detected in the groundwater and sediments below the water table that emanates from the 300-FF-1, 300-FF-2, and 300-FF-3 operable units (DOE-RL 1990a). In November 1989, the U.S. Environmental Protection Agency (EPA) placed the 300 Area on the National Priorities List (NPL) contained within Appendix B of the National Oil and Hazardous Substance Pollution Contingency Plan (NCP, 53 FR 51391 et seq.). The EPA took this action pursuant to their authority under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA, 42 USC 9601 et seq.). The DOE Richland Operations Office (DOE-RL), the EPA and Washington Department of Ecology (Ecology) issued the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), in May 1989 (Ecology et al. 1992, Rev. 2). This agreement, among other matters, governs all CERCLA efforts at the Hanford Site. In June 1990, a remedial investigation/feasibility study (RI/FS) workplan for the 300-FF-5 operable unit was issued pursuant to the Tri-Party Agreement

  9. Licensed operating reactors. Status summary report: data as of September 30, 1985. Volume 9, No. 10

    International Nuclear Information System (INIS)

    1985-11-01

    This report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Resource Management from the Headquarters staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, IE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US

  10. Licensed operating reactors. Status summary report data as of May 31, 1985. Vol. 9, No. 6

    International Nuclear Information System (INIS)

    1985-07-01

    This report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Resource Management from the Headquarters staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, IE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US

  11. Licensed operating reactors: Status summary report, Data as of 12-31-86

    International Nuclear Information System (INIS)

    1987-09-01

    This report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Administration and Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are monthly highlights and statistics for commercial operating units and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US

  12. Current status of operation and utilization of the Dalat Research Reactor

    International Nuclear Information System (INIS)

    Dien, Nguyen Nhi

    2006-01-01

    research reactors used Russia fuels was submitted to Russian Government though IAEA. After that, the Russian Research Reactor Fuel Return (RRRFR) Program was established and trilateral discussions among the United State, the Russian Federation and the IAEA started. In this aspect, the Dalat reactor core has been considered to insert fresh LEU FAs instead of fresh HEU FAs. It means the mixed core of HEU and LEU FAs may be used in the coming years. For these purposes, neutronics and thermal hydraulics calculations and safety analyses should be done. The current status of the reactor operation and utilization as well as some results on in-core fuel management of the DNRR are presented in this paper. Some activities to participating in the project on Research Reactor Technology for Effective Utilization are proposed for discussions. (author)

  13. United States high-level radioactive waste management program: Current status and plans

    International Nuclear Information System (INIS)

    Williams, J.

    1992-01-01

    The inventory of spent fuel in storage at reactor sites in the United States is approximately 20,000 metric tons heavy metal (MTHM). It is increasing at a rate of 1700 to 2100 MTHM per year. According to current projections, by the time the last license for the current generation of nuclear reactors expires, there will be an estimated total of 84,000 MTHm. No commercial reprocessing capacity exists or is planned in the US. Therefore, the continued storage of spent fuel is required. The majority of spent fuel remains in the spent fuel pools of the utilities that generated it. Three utilities are presently supplementing pool capacity with on-site dry storage technologies, and four others are planning dry storage. Commercial utilities are responsible for managing their spent fuel until the Federal waste management system, now under development, accepts spent fuel for storage and disposal. Federal legislation charges the Office of Civilian Radioactive Waste Management (OCRWM) within the US Department of Energy (DOE) with responsibility for developing a system to permanently dispose of spent fuel and high level radioactive waste in a manner that protects the health and safety of the public and the quality of the environment. We are developing a waste management system consisting for three components: a mined geologic repository, with a projected start date of 2010; a monitored retrievable storage facility (MRS), scheduled to begin waste acceptance in 1998; and a transportation system to support MRS and repository operations. This paper discusses the background and framework for the program, as well as the current status and plans for management of spent nuclear fuel at commercial utilities; the OCRWM's development of a permanent geologic repository, an MRS, and a transportation system; the OCRWM's safety approach; the OCRWM's program management initiatives; and the OCRWM's external relations activities

  14. Information Operations: Countering the Asymmetric Threat to the United States

    National Research Council Canada - National Science Library

    McKeown, Wendell

    1999-01-01

    .... The cornerstone of Joint Vision 2010 is information superiority. Every facet of future military operations will be critically linked to an aggregate cyber network that relies on critical national infrastructures to provide for information superiority...

  15. An Examination of the United States Air Service's Logistics Operations

    National Research Council Canada - National Science Library

    Hunt, Andrew

    1998-01-01

    This historical study details the U.S. Air Service's logistics operations at home and abroad in an attempt to determine the relationship between the process and more recently established logistic principles...

  16. Licensed operating reactors: Status summary report, data as of December 31, 1995. Volume 20

    International Nuclear Information System (INIS)

    1996-06-01

    The US Nuclear Regulatory Commission's monthly summary of licensed nuclear power reactor data is based primarily on the operating data report submitted by licensees for each unit. This report is divided into two sections: the first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 availability factors, capacity factors, and forced outage rates are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensees and notes to the use of weighted averages and starting dates other than commercial operation are provided

  17. 7 CFR 631.22 - Access to operating unit.

    Science.gov (United States)

    2010-01-01

    ..., DEPARTMENT OF AGRICULTURE LONG TERM CONTRACTING GREAT PLAINS CONSERVATION PROGRAM Miscellaneous § 631.22... unit for the purpose of ascertaining the accuracy of any representations made in a contract or leading up to a contract, and as to the performance of the terms and conditions of the contract. Access shall...

  18. Emergency contraception use and counseling after changes in United States prescription status.

    Science.gov (United States)

    Kavanaugh, Megan L; Williams, Sanithia L; Schwarz, E Bimla

    2011-06-30

    Analysis of data from the 2006-2008 National Survey of Family Growth indicates that use of emergency contraception in the United States has increased after changes in its prescription status in 2006. However, clinicians continue to play a pivotal role in ensuring that women have accurate information about emergency contraception. Copyright © 2011 American Society for Reproductive Medicine. Published by Elsevier Inc. All rights reserved.

  19. Interim remedial measures proposed plan for the 200-ZP-1 Operable Unit, Hanford Site, Washington

    International Nuclear Information System (INIS)

    Parker, D.L.

    1993-12-01

    The purpose of this interim remedial measures (IRM) proposed plan is to present and solicit public comments on the IRM planned for the 200-ZP-1 Operable Unit at the Hanford Site in Washington state. The 200-ZP-1 is one of two operable units that envelop the groundwater beneath the 200 West Area of the Hanford Site

  20. Survey method for radiological surveys of 300 FF-1 Operable Unit soil and materials

    International Nuclear Information System (INIS)

    Greif, A.A.

    1997-06-01

    This technical basis document is to be used to survey soils at the 300-FF-1 Operable Unit during remediation of the site. Its purpose is to provide a basis for the survey methods to be employed by the Radiological Control Technician to determine if excavated areas require continued remediation in accordance with the Record of Decision for the operable unit

  1. Brunswick Steam Electric Plant, Units 1 and 2. Annual operating report for 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Net electrical energy generated by Unit 1 was 30,399 MWH with the generator on line 334.5 hrs. Unit 2 generated 2,481,014 MWH with the generator on line 4,915.53 hrs. Information is presented concerning operations, shutdowns and power reductions, maintenance, power generation, modifications, changes to operational procedures, radiation exposures, and leak rate testing

  2. Increasing the flexibility of base-load generating units in operation on fossil fuel

    Energy Technology Data Exchange (ETDEWEB)

    Girshfel' d, V Ya; Khanaev, V A; Volkova, E D; Gorelov, V A; Gershenkroi, M L

    1979-01-01

    Increasing the flexibility of base-load generating units operating on fossil fuel by modifying them is a necessary measure. The highest economic effect is attained with modification of gas- and oil-fired generating units in the Western United Power Systems of the European part of the SPSS. On the basis of available experience, 150- and 200-MW units can be extensively used to regulate the power in the European part of the SPSS through putting them into reserve for the hours of the load dip at night. The change under favorable conditions of 150- and 200-MW units operating on coal to a district-heating operating mode does not reduce the possibilities for flexible operation of these units because it is possible greatly to unload the turbines while the minimum load level of the pulverized fuel fired boiler is retained through transferring a part of the heat load to the desuperheater. It is necessary to accumulate and analyze experience with operation of generating units (especially of supercritical units) with regular shutdowns and starts of groups of units and to solve the problems of modification of generating units, with differentiation with respect to types of fuel and to the united power supply system.

  3. Continued advancement of the programming language HAL to an operational status

    Science.gov (United States)

    1971-01-01

    The continued advancement of the programming language HAL to operational status is reported. It is demonstrated that the compiler itself can be written in HAL. A HAL-in-HAL experiment proves conclusively that HAL can be used successfully as a compiler implementation tool.

  4. Twenty years of operation of WWER 440/230 units in Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Tomek, J.

    1998-01-01

    It is twenty years this year since the first unit WWER 440 of Slovak Nuclear Power Plant Jaslovske Bohunice was commissioned. There are four units WWER 440 in operation Jaslovske Bohunice site. First two units of older soviet PWR design V-230 (also known as V-1) and other two units of newer V-213 type (also known as V-2). The goal of this presentation is to summarize and evaluate the operation of Unit 1 and 2 for this period of time and mainly to describe what has been done and what is planned to be done to increase the nuclear safety and operational reliability of both units. The operating organization and regulatory authority assume that an internationally acceptable level of safety will be reached by accomplishing of the upgrading program.(author)

  5. AN OPERATIONAL MANAGEMENT MODEL FOR A COAL MINING PRODUCTION UNIT

    Directory of Open Access Journals (Sweden)

    R. Visser

    2012-01-01

    Full Text Available

    ENGLISH ABSTRACT: The coal mining industry faces increased pressure for higher quality coal at lower cost and increased volumes. To satisfy these requirements the industry needs technically skilled first line supervisors with operational management skills. Most first line supervisors possess the necessary technical, but not the required operational management skills. Various operational management philosophies, describing world-class operational management practices exist; however, it is not possible to implement these philosophies as-is in a mining environment due to the various differences between manufacturing and mining. The solution is to provide an operational management model, adapted from these philosophies, to first line supervisors in the coal mining industry.

    AFRIKAANSE OPSOMMING: Die steenkoolmynbedryf ervaar groeiende druk van die mark vir hoër gehalte steenkool, laer koste en verhoogde volumes. Om hierdie behoefte te bevredig benodig die myn tegniesgeskoolde eerstelyntoesighouers met bedryfsbestuursvaardighede. Ongelukkig beskik die meeste toesighouers wel oor die nodige tegniese kennis, maar nie die nodige bedryfsbestuursvaardighede nie. Daar bestaan verskeie bedryfsbestuursfilosofieë wat wêreldklas bedryfsbestuurspraktyke omskryf. Dit is egter nie moontlik om die filisofieë net so in die mynbedryf te implimenteer nie a.g.v. die verskille tussen vervaardiging en mynbou. Die oplossing is om ‘n bedryfsbestuurmodel wat op hierdie filosofieë geskoei is, aan eerstelyntoesighouers in die steenkoolbedryf te verskaf.

  6. Calvert Cliffs Nuclear Power Plant, Units 1 and 2. Annual operating report: January--December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Unit 1 successfully completed its first core cycle with unit availability of 95.2 percent. Saltwater leakage into the condenser continues to be a problem. Unit 2 achieved initial criticality November 30 and was initially paralleled to the Baltimore system on December 7. Information is presented concerning operations, specifications, maintenance, shutdowns and power reduction, and personnel exposures

  7. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Unit 2 (Docket No. 50-446)

    International Nuclear Information System (INIS)

    1992-09-01

    This document supplement 25 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Unit 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, 21, 22, 23, and 24 to that report were published. This supplement deals primarily with Unit 2 issues; however, it also references evaluations for several Unit 1 licensing items resolved since Supplement 24 was issued

  8. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Unit 2 (Docket No. 50-446)

    International Nuclear Information System (INIS)

    1993-02-01

    Supplement 26 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Unit 2, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, 21, 22, 23, 24, and 25 to that report were published. This supplement deals primarily with Unit 2 issues; however, it also references evaluations for several licensing issues that relate to Unit 1, which have been resolved since Supplement 25 was issued

  9. Safety-Evaluation Report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2. Docket Nos. 50-416 and 50-417

    International Nuclear Information System (INIS)

    1983-05-01

    Supplement 4 to the Safety Evaluation Report for Mississippi Power and Light Company, et. al., joint application for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2, located on the east bank of the Mississippi River near Port Gibson in Claiborne County, Mississippi, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status on the resolution of those issues that required further evaluation before authorizing operation of Unit 1 above 5% rated power and other issues that were to be evaluated during the first cycle of power operation

  10. Operational challenges and opportunities in pastured poultry operations in the United States.

    Science.gov (United States)

    Elkhoraibi, C; Pitesky, M; Dailey, N; Niemeier, D

    2017-06-01

    As pastured poultry production has gained increased popularity in the United States in recent years, there is a growing need for research and outreach efforts aimed at this sector of poultry production. In order to get familiarized with American pastured poultry producers, we conducted an online questionnaire aimed primarily at evaluating what operational challenges are faced by producers and what educational opportunities should be initiated by researchers. Results showed that pastured poultry farms largely vary in total number of acres farmed and total number of birds kept. The vast majority of farms (96%) rotate their flocks on pasture and include livestock species (78%) in their rotation systems. Mobile coops are the preferred housing option provided by producers (88%). The most common source of mortality listed by respondents was predation (52%), followed by "other" (32%). However, predation was not selected as the most important challenge by the majority of respondents. Sixty-four percent of participants instead mentioned providing adequate feed at reasonable cost as the major challenge in raising poultry on pasture, followed again by "other" (52%) and lack of processing facilities for small numbers of birds (40%). Finally, the topics considered by respondents as the most helpful to learn more about were how to improve egg production rate and/or feed conversion ratio (67%), followed by how to improve pasture condition and optimum vegetative cover all year round (62%). Despite its small sample size, this study's results provide some valuable insights of challenges encountered and information needed on pastured poultry farms. © 2017 Poultry Science Association Inc.

  11. Pilgrim Nuclear Power Station, Unit 1. Annual operating report, 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Net electric power generated in 1975 was 1,074,401 MW(e) with the generator on line 4,680.7 hrs. Information is presented concerning operations, maintenance, radioactive effluents and waste shipments, health physics, shutdowns, and personnel exposures

  12. Startup operation of Browns Ferry's 1152-MW nuclear units

    International Nuclear Information System (INIS)

    Calhoun, J.R.; Green, H.J.; Beers, R.B.

    1975-01-01

    An overview is presented of startup operation for the Browns Ferry-1 reactor, and comparisons are made with the startup of Browns Ferry-2. Included are comments on the selection of the BWR type steam supply system, reactor fueling, problems encountered, and plant availability

  13. Brunswick Steam Electric Plant, Unit 2. Annual operating report, 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Initial criticality occurred in March and start-up testing continued for most of the year. Information is presented concerning operations, shutdowns, maintenance, design changes, personnel radiation exposures, thermal transients, safety/relief valve malfunctions, condenser tube leaks, and recirculation pump seal failures

  14. Pilgrim Nuclear Power Station, Unit 1. Annual operating report, 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Net electrical power generated was 2,587,248 MWH(e) with the reactor on line 6,242.4 hr. Information is presented concerning operations, power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, and reportable occurrences

  15. The BGL coal gasification process - development status, operational experience and potential applications

    Energy Technology Data Exchange (ETDEWEB)

    Williams, A.R.; Brown, D.J.; H. Hirschfelder [Advantica Technologies Ltd., Loughborough (United Kingdom)

    2006-07-01

    The BGL gasifier's fixed bed mode of operation makes for significant operational differences to the various entrained flow bed gasification processes currently available, whilst the slagging lower half offers considerable advantages over older processes in terms of efficiency and steam usage. This paper reviews operating experience of the BGL process on a variety of feedstocks and presents economic and technical assessments of the application of the BGL gasifier for IGCC, Syngas and SNG applications under current market conditions. Finally there a survey of the status of new BGL gasification projects and the scope of the current BGL technology is offering. 2 figs., 3 tabs., 2 photos.

  16. LEGAL STATUS OF ADVISORS IN THE FIELD OF INTELLECTUAL PROPERTY RIGHT IN THE UNITED KINGDOM

    Directory of Open Access Journals (Sweden)

    Khrystyna Kmetyk

    2017-11-01

    Full Text Available Purpose: to research the legal status of advisors in the field of intellectual property right in the United Kingdom. In this article an author distinguishes and gives a legal description of the types of advisors in the field of intellectual property right in the United Kingdom. The main provisions of the Rules of Conduct for Patent Attorneys, Ttrade Mark Attorneys and Other Regulated Persons (2015 are considered. Methods: to analyse the legal status of advisors in the field of intellectual property right in the United Kingdom the method of induction, systematic approach, formal legal methods were used. Results: this research provides an opportunity to broaden the understanding of the institute of advisors in the field of intellectual property right (in particular patent attorneys and trademark attorneys in the UK and thus include this knowledge in domestic research on intellectual property right. Conclusions: the majority of types of advisors in the field of intellectual property right in the United Kingdom (patent attorneys, chartered patent attorneys, European patent attorneys, registered trademark attorneys and trademark attorneys, European trademark attorneys, etc. is well-educated professionals in all areas of intellectual property and are able to advise on a wide range of technical and commercial issues in this field. The obtained results will have a positive impact on the reform of the institute of representatives in the field of intellectual property in Ukraine in order to ensure its effectiveness and relevance to the challenges of the present.

  17. Cognitive model of the power unit operator activity

    International Nuclear Information System (INIS)

    Chachko, S.A.

    1992-01-01

    Basic notions making it possible to study and simulate the peculiarities of man-operator activity, in particular his way of thiking, are considered. Special attention is paid to cognitive models based on concept of decisive role of knowledge (its acquisition, storage and application) in the man mental processes and activity. The models are based on three basic notions, which are the professional world image, activity strategy and spontaneous decisions

  18. Operations Research and the US (United States) Army

    Science.gov (United States)

    1983-04-07

    technology "developed more rapidly than it could be absorbed effectively into military tactics and strategy." 4 World War II is usually identified as...Corporation, was formed by the Air Force as a non-profit organization to provide technological advice. 7 By the early 1950’s the public recognized operations... enlight - ening. He recognized the important and clearly distinguishable roles played by the technical analyst and the military decision maker. The systems

  19. Safety Evaluation Report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    1987-05-01

    This report, Supplement No. 5 to the Safety Evaluation Report for the application filed by the Duquesne Light Company et al. (the applicant) for a license to operate the Beaver Valley Power Station, Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved when the Safety Evaluation Report and its Supplements 1, 2, 3, and 4 were published

  20. Safety Evaluation Report related to the operation of Clinton Power Station, Unit No. 1, Docket No. 50-461

    International Nuclear Information System (INIS)

    1983-05-01

    Supplement No. 2 to the Safety Evaluation Report on the application filed by Illinois Power Company, Soyland Power Cooperative, Inc., and Western Illinois Power Cooperative, Inc., as applicants and owners, for a license to operate the Clinton Power Station, Unit No. 1, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Harp Township, DeWitt County, Illinois. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement No. 1

  1. Safety evaluation report related to the operation of Clinton Power Station, Unit No. 1 (Docket No. 50-461)

    International Nuclear Information System (INIS)

    1987-03-01

    Supplement No. 8 to the Safety Evaluation Report on the application filed by Illinois Power Company, Soyland Power Cooperative, Inc., and Western Illinois Power Cooperative, Inc., as applicants and owners, for a license to operate the Clinton Power Station, Unit No. 1, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Harp Township, DeWitt County, Illinois. This supplement reports the status of items that have been resolved by the staff since Supplement No. 7 was issued

  2. Safety evaluation report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    1987-08-01

    This report, Supplement No. 6 to the Safety Evaluation Report for the application filed by the Duquesne Light Company et al. (the licensee) for a license to operate the Beaver Valley Power Station, Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved when the Safety Evaluation Report and its Supplements 1, 2, 3, 4, and 5 were published

  3. Cost and Operational Effectiveness Analysis of Aiternative Force Structures for Fulfillment of the United States Marine Corps Operational Support Airlift and Search and Rescue Missions

    National Research Council Canada - National Science Library

    Chase, Eric

    2000-01-01

    This thesis provides a preliminary cost and operational effectiveness analysis of alternative force structures for the United States Marine Corps operational support airlift and search and rescue missions...

  4. Experimental determinations of the turbine condenser operation at Cernavoda NPP Unit 1

    International Nuclear Information System (INIS)

    Romascu, Gabriel; Dragusin, Dumitru; Rogociu, Ioan; Macodean, Luminita; Marciulescu, George

    1999-01-01

    The condenser system represents one of the most important BOP (balance of plant) systems of the CANDU 700 MW Unit at Cernavoda NPP. The paper presents theoretical calculation elements, mathematical model for simulation of condenser operation and the results obtained by model implementation as compared to operation data. The model could be adapted to other turbine and operation regime types. (authors)

  5. 14 CFR 375.41 - Agricultural and industrial operations within the United States.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Agricultural and industrial operations... Agricultural and industrial operations within the United States. Foreign civil aircraft shall not be used for such commercial air operations as crop dusting, pest control, pipeline patrol, mapping, surveying...

  6. Biota of the 300-FF-1 operable unit. [Westinghouse Hanford Company

    Energy Technology Data Exchange (ETDEWEB)

    Rickard, W.H. Jr.; Fitzner, R.E.; Brandt, C.A.

    1990-10-01

    This report summarizes Task 5a-2 of the Phase I Remedial Investigation -- Operable Unit Characterization of the 300-FF-1 Operable Unit on the Hanford Site, near Richland, Washington. The ultimate goal of Phase I is to determine the nature and extent of the threat to public health and the environment from releases of hazardous substances from the operable unit. The purpose of Task 5a-2 was to determine what species inhabit the 300-FF-1 Operable Unit and how they use the unit. The focus is on those species listed as endangered or threatened, those that are economically important, or those that constitute significant components of the human food chain. 39 refs., 5 figs., 5 tabs.

  7. The United States nuclear plant reliability data program: Its description and status

    International Nuclear Information System (INIS)

    Wise, M.J.

    1975-01-01

    The American National Standards Institute Subcommittee N18-20 has developed and implemented the United States Nuclear Plant Reliability Data System (NPRDS). The NPRDS is designed to accumulate, store, analyse, and report reliability and failure statistics on systems and components of nuclear power plants related to nuclear safety. Input data to the NPRDS consist of engineering, operating, and failure information submitted on a voluntary basis by participating utilities. Prior to entry into the computerized data base, the data are thoroughly checked for accuracy by both the submitting organizations and the NPRDS operating contractor. The data base is the source of various periodic output reports to the nuclear power industry and is utilized to produce special reports upon request. The present data base represents data accumulated from about thirty nuclear units with additional units expected to begin submitting data immediately. The objective is to have essentially all operating nuclear units in the United States of America participating in the program by the end of 1975. The first NPRDS annual reports containing meaningful reliability and failure statistics are expected to be produced following the end of 1975. (author)

  8. Status of fusiform rust incidence in slash and loblolly pine plantations in the southeastern United States

    Science.gov (United States)

    KaDonna C. Randolph

    2016-01-01

    Southern pine tree improvement programs have been in operation in the southeastern United States since the 1950s. Their goal has been to improve volume growth, tree form, disease resistance, and wood quality in southern pines, particularly slash pine (Pinus elliottii) and loblolly pine (P. taeda). The disease of focus has been...

  9. Operation of the radioactive acid-digestion test unit (RADTU)

    International Nuclear Information System (INIS)

    Blasewitz, A.G.; Allen, C.R.; Lerch, R.E.; Ely, P.C.; Richardson, G.L.

    1981-01-01

    At the Karlsruhe Nuclear Research Center, research and development work concerned with the acid digestion of combustible waste with high plutonium content is being carried out. The main objectives are the reduction of the waste volume, the recovery of the plutonium and the transformation of the process residues into a product suitable for final disposal. For this purpose an inactive demonstration plant with a throughput of 1.5 kg/h has been constructed. In the first version, the reactor of this plant was a tray reactor of the HEDL type. During test operations the sedimentation of a residue was observed on the tray. The density of this residue was higher than that of the residue suspended in the reaction acid. Experiments using tantalum oxide (D=8.4 g/cm 3 ) to simulate the plutonium oxide (D=11.5 g/cm 3 ) have verified this observation. This means that in active operation a sedimentation of plutonium oxide on the tray is to be expected. With respect to these results a new reactor was developed where the settling of the residue is avoided by appropriate design and high circulation velocity of the reaction acid. The reactor consists of a tube 50-80 mm in diameter, which is curved to form a closed loop with an arm length of about 1x1 m. Since October 1979 this ring reactor has been under inactive test operation. Its behaviour is very stable. The velocity of the reaction acid in the heater is 0.5-1 m/s. A settling of residues or tantalum oxide has not been observed. The throughput attained is comparable to that of the tray reactor but the space requirement is three times smaller, and the volume of the reaction acid four times smaller. (author)

  10. Radioprotection in the operation of accelerator and plasma units

    International Nuclear Information System (INIS)

    Ewen, K.

    1984-01-01

    Relatively great problems of radioprotection can be caused by accelerator units, above all in the field of science, because all kinds of ionizing radiation and radioactive substances can be produced in all stages of aggregation. Furthermore, activities with relatively long half-lifes are induced by high particle streams with energies beyond the thresholds of many nuclear reations, to that the conditions of a control zone, even of a prohibited zone exist at many points after having switched off the accelerator. Not all of these radioprotective problems can be solved by constructive or technical measures. A sufficient skill of the persons responsible for radioprotection is very important in this connection. Efficient radioprotective measures are only possible by a close cooperation between the radiation protection officer, the competent authority, and the expert. (orig.) [de

  11. United Kingdom: Procurement Related Nuclear Experience (Operating Experience)

    International Nuclear Information System (INIS)

    2016-01-01

    Procurement of nuclear facilities in the United Kingdom is subject to nuclear site licence conditions issued by the Government through the Office for Nuclear Regulation (ONR). Each nuclear facility in the United Kingdom must have a nuclear site licence and must comply with the 36 general conditions that are set out in the Licence Condition Handbook (October 2014). In addition, the ONR has published a technical assessment guide for the procurement of nuclear safety related items or services; a guide on intelligent customers and a guide on records management also apply to the procurement phase, and ONR interventions look across all three of these documents. Procurement governance arrangements need to be developed (including a policy, manual, procedures and template documents) and approved within the utility company. The ONR monitors the arrangements via interventions and deems the arrangements to be ‘adequate’. Some procurement contracts become lifetime records for nuclear safety related systems and need to be retained while the plant is in place. A formal record retention schedule needs to be created and managed by the procurement organization. The utility company may elect to set hold points during the various procurement stages and, importantly, obtain approval for the contract and its content from all technical stakeholders (with particular emphasis on the engineering, project management and design authority quality functions before contract award). For contracts with high nuclear safety significance, the ONR may enforce additional hold points before and/or after contract award. There is a general requirement that the utility puts in place adequate arrangements to ensure that suitably qualified and experienced personnel are employed to implement adequate management arrangements and to act as an intelligent customer. This includes being able to demonstrate that any contractor or supplier is suitable, capable and experienced, and has the necessary processes and

  12. Population health status of South Asian and African-Caribbean communities in the United Kingdom.

    Science.gov (United States)

    Calvert, Melanie; Duffy, Helen; Freemantle, Nick; Davis, Russell; Lip, Gregory Y H; Gill, Paramjit

    2012-04-25

    Population health status scores are routinely used to inform economic evaluation and evaluate the impact of disease and/or treatment on health. It is unclear whether the health status in black and minority ethnic groups are comparable to these population health status data. The aim of this study was to evaluate health-status in South Asian and African-Caribbean populations. Cross-sectional study recruiting participants aged ≥ 45 years (September 2006 to July 2009) from 20 primary care centres in Birmingham, United Kingdom.10,902 eligible subjects were invited, 5,408 participated (49.6%). 5,354 participants had complete data (49.1%) (3442 South Asian and 1912 African-Caribbean). Health status was assessed by interview using the EuroQoL EQ-5D. The mean EQ-5D score in South Asian participants was 0.91 (standard deviation (SD) 0.18), median score 1 (interquartile range (IQR) 0.848 to 1) and in African-Caribbean participants the mean score was 0.92 (SD 0.18), median 1 (IQR 1 to 1). Compared with normative data from the UK general population, substantially fewer African-Caribbean and South Asian participants reported problems with mobility, usual activities, pain and anxiety when stratified by age resulting in higher average health status estimates than those from the UK population. Multivariable modelling showed that decreased health-related quality of life (HRQL) was associated with increased age, female gender and increased body mass index. A medical history of depression, stroke/transient ischemic attack, heart failure and arthritis were associated with substantial reductions in HRQL. The reported HRQL of these minority ethnic groups was substantially higher than anticipated compared to UK normative data. Participants with chronic disease experienced significant reductions in HRQL and should be a target for health intervention.

  13. Population health status of South Asian and African-Caribbean communities in the United Kingdom

    Directory of Open Access Journals (Sweden)

    Calvert Melanie

    2012-04-01

    Full Text Available Abstract Background Population health status scores are routinely used to inform economic evaluation and evaluate the impact of disease and/or treatment on health. It is unclear whether the health status in black and minority ethnic groups are comparable to these population health status data. The aim of this study was to evaluate health-status in South Asian and African-Caribbean populations. Methods Cross-sectional study recruiting participants aged ≥ 45 years (September 2006 to July 2009 from 20 primary care centres in Birmingham, United Kingdom.10,902 eligible subjects were invited, 5,408 participated (49.6%. 5,354 participants had complete data (49.1% (3442 South Asian and 1912 African-Caribbean. Health status was assessed by interview using the EuroQoL EQ-5D. Results The mean EQ-5D score in South Asian participants was 0.91 (standard deviation (SD 0.18, median score 1 (interquartile range (IQR 0.848 to 1 and in African-Caribbean participants the mean score was 0.92 (SD 0.18, median 1 (IQR 1 to 1. Compared with normative data from the UK general population, substantially fewer African-Caribbean and South Asian participants reported problems with mobility, usual activities, pain and anxiety when stratified by age resulting in higher average health status estimates than those from the UK population. Multivariable modelling showed that decreased health-related quality of life (HRQL was associated with increased age, female gender and increased body mass index. A medical history of depression, stroke/transient ischemic attack, heart failure and arthritis were associated with substantial reductions in HRQL. Conclusions The reported HRQL of these minority ethnic groups was substantially higher than anticipated compared to UK normative data. Participants with chronic disease experienced significant reductions in HRQL and should be a target for health intervention.

  14. Licensed operating reactors. Status summary report data as of 12-31-94: Volume 19

    International Nuclear Information System (INIS)

    1995-04-01

    The Nuclear Regulatory Commission's annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar year 1994) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided

  15. Licensed operating reactors: Status summary report data as of December 31, 1992

    International Nuclear Information System (INIS)

    Hartfield, R.A.

    1993-03-01

    The Nuclear Regulatory Commission's annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar year 1992) and cumulative data, usually from the date of commercial operation. ne data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided

  16. Licensed operating reactors. Status summary report data as of 12-31-94: Volume 19

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    The Nuclear Regulatory Commission`s annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar year 1994) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided.

  17. Licensed operating reactors. Status summary report data as of December 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Hartfield, R.A.

    1994-03-01

    The Nuclear Regulatory Commissions annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December, the year to date (in this case calendar year 1993) and cumulative data, usually for the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided.

  18. Ground Operations Demonstration Unit for Liquid Hydrogen Initial Test Results

    Science.gov (United States)

    Notardonato, W. U.; Johnson, W. L.; Swanger, A. M.; Tomsik, T.

    2015-01-01

    NASA operations for handling cryogens in ground support equipment have not changed substantially in 50 years, despite major technology advances in the field of cryogenics. NASA loses approximately 50% of the hydrogen purchased because of a continuous heat leak into ground and flight vessels, transient chill down of warm cryogenic equipment, liquid bleeds, and vent losses. NASA Kennedy Space Center (KSC) needs to develop energy-efficient cryogenic ground systems to minimize propellant losses, simplify operations, and reduce cost associated with hydrogen usage. The GODU LH2 project has designed, assembled, and started testing of a prototype storage and distribution system for liquid hydrogen that represents an advanced end-to-end cryogenic propellant system for a ground launch complex. The project has multiple objectives including zero loss storage and transfer, liquefaction of gaseous hydrogen, and densification of liquid hydrogen. The system is unique because it uses an integrated refrigeration and storage system (IRAS) to control the state of the fluid. This paper will present and discuss the results of the initial phase of testing of the GODU LH2 system.

  19. Standard formatted data units-control authority operations

    Science.gov (United States)

    1991-01-01

    The purpose of this document is to illustrate a Control Authority's (CA) possible operation. The document is an interpretation and expansion of the concept found in the CA Procedures Recommendation. The CA is described in terms of the functions it performs for the management and control of data descriptions (metadata). Functions pertaining to the organization of Member Agency Control Authority Offices (MACAOs) (e.g., creating and disbanding) are not discussed. The document also provides an illustrative operational view of a CA through scenarios describing interaction between those roles involved in collecting, controlling, and accessing registered metadata. The roles interacting with the CA are identified by their actions in requesting and responding to requests for metadata, and by the type of information exchanged. The scenarios and examples presented in this document are illustrative only. They represent possible interactions supported by either a manual or automated system. These scenarios identify requirements for an automated system. These requirements are expressed by identifying the information to be exchanged and the services that may be provided by a CA for that exchange.

  20. The Input-output Status and Farmers’Willingness to Choose Ecological Operation of Hickory

    Institute of Scientific and Technical Information of China (English)

    LIU Qiang; LI Shi-yong; WU Wei-guang

    2012-01-01

    This study takes Lin’an City which early carries out the experiment of ecological operation of hickory as the study site.On the basis of the input-output data on hickory and farmers’ land,we analyze the input-output status of hickory land which practises ecological operation,the operators’ willingness to accept ecological operation and the influencing factors.The results show that in the short term,ecological operation of hickory will have a certain negative impact on the economic benefits;within the experimental area,the degree of operators’ willingness to accept ecological operation of hickory is high,and the operators have a clear understanding of long-term comprehensive benefits which may be brought by ecological operation;the ecological experiment and demonstration of hickory have achieved certain results;family income level,characteristics of householders,education and training,and so on,are the main factors that affect the operators’ willingness to choose ecological operation.Finally,for how to further improve the promotion efficiency of ecological operation of hickory,we put forth some constructive recommendations.

  1. Hospital markup and operation outcomes in the United States.

    Science.gov (United States)

    Gani, Faiz; Ejaz, Aslam; Makary, Martin A; Pawlik, Timothy M

    2016-07-01

    Although the price hospitals charge for operations has broad financial implications, hospital pricing is not subject to regulation. We sought to characterize national variation in hospital price markup for major cardiothoracic and gastrointestinal operations and to evaluate perioperative outcomes of hospitals relative to hospital price markup. All hospitals in which a patient underwent a cardiothoracic or gastrointestinal procedure were identified using the Nationwide Inpatient Sample for 2012. Markup ratios (ratio of charges to costs) for the total cost of hospitalization were compared across hospitals. Risk-adjusted morbidity, failure-to-rescue, and mortality were calculated using multivariable, hierarchical logistic regression. Among the 3,498 hospitals identified, markup ratios ranged from 0.5-12.2, with a median markup ratio of 2.8 (interquartile range 2.7-3.9). For the 888 hospitals with extreme markup (greatest markup ratio quartile: markup ratio >3.9), the median markup ratio was 4.9 (interquartile range 4.3-6.0), with 10% of these hospitals billing more than 7 times the Medicare-allowable costs (markup ratio ≥7.25). Extreme markup hospitals were more often large (46.3% vs 33.8%, P markup ratio compared with 19.3% (n = 452) and 6.8% (n = 35) of nonprofit and government hospitals, respectively. Perioperative morbidity (32.7% vs 26.4%, P markup hospitals. There is wide variation in hospital markup for cardiothoracic and gastrointestinal procedures, with approximately a quarter of hospital charges being 4 times greater than the actual cost of hospitalization. Hospitals with an extreme markup had greater perioperative morbidity. Copyright © 2016 Elsevier Inc. All rights reserved.

  2. The chemical energy unit partial oxidation reactor operation simulation modeling

    Science.gov (United States)

    Mrakin, A. N.; Selivanov, A. A.; Batrakov, P. A.; Sotnikov, D. G.

    2018-01-01

    The chemical energy unit scheme for synthesis gas, electric and heat energy production which is possible to be used both for the chemical industry on-site facilities and under field conditions is represented in the paper. The partial oxidation reactor gasification process mathematical model is described and reaction products composition and temperature determining algorithm flow diagram is shown. The developed software product verification showed good convergence of the experimental values and calculations according to the other programmes: the temperature determining relative discrepancy amounted from 4 to 5 %, while the absolute composition discrepancy ranged from 1 to 3%. The synthesis gas composition was found out practically not to depend on the supplied into the partial oxidation reactor (POR) water vapour enthalpy and compressor air pressure increase ratio. Moreover, air consumption coefficient α increase from 0.7 to 0.9 was found out to decrease synthesis gas target components (carbon and hydrogen oxides) specific yield by nearly 2 times and synthesis gas target components required ratio was revealed to be seen in the water vapour specific consumption area (from 5 to 6 kg/kg of fuel).

  3. Evaluation of nuclear facility decommissioning projects. Status report. Humboldt Bay Power Plant Unit 3, SAFSTOR decommissioning

    International Nuclear Information System (INIS)

    Baumann, B.L.; Haffner, D.R.; Miller, R.L.; Scotti, K.S.

    1986-06-01

    This document explains the purpose of the US Nuclear Regulatory Commission's (NRC) Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program and summarizes information concerning the decommissioning of the Humboldt Bay Power Plant (HBPP) Unit 3 facility. Preparations to put this facility into a custodial safe storage (SAFSTOR) mode are currently scheduled for completion by June 30, 1986. This report gives the status of activities as of June 1985. A final summary report will be issued after completion of this SAFSTOR decommissioning activity. Information included in this status report has been collected from the facility decommissioning plan, environmental report, and other sources made available by the licensee. This data has been placed in a computerized data base system which permits data manipulation and summarization. A description of the computer reports that can be generated by the decommissioning data system (DDS) for Humboldt Bay and samples of those reports are included in this document

  4. [Construction and operation status of management system of laboratories of schistosomiasis control institutions in Hubei Province].

    Science.gov (United States)

    Zhao-Hui, Zheng; Jun, Qin; Li, Chen; Hong, Zhu; Li, Tang; Zu-Wu, Tu; Ming-Xing, Zeng; Qian, Sun; Shun-Xiang, Cai

    2016-10-09

    To analyze the construction and operation status of management system of laboratories of schistosomiasis control institutions in Hubei Province, so as to provide the reference for the standardized detection and management of schistosomiasis laboratories. According to the laboratory standard of schistosomiasis at provincial, municipal and county levels, the management system construction and operation status of 60 schistosomiasis control institutions was assessed by the acceptance examination method from 2013 to 2015. The management system was already occupied over all the laboratories of schistosomiasis control institutions and was officially running. There were 588 non-conformities and the inconsistency rate was 19.60%. The non-conformity rate of the management system of laboratory quality control was 38.10% (224 cases) and the non-conformity rate of requirements of instrument and equipment was 23.81% (140 cases). The management system has played an important role in the standardized management of schistosomiasis laboratories.

  5. Functional and Mental Health Status of United Kingdom Military Amputees Postrehabilitation.

    Science.gov (United States)

    Ladlow, Peter; Phillip, Rhodri; Etherington, John; Coppack, Russell; Bilzon, James; McGuigan, M Polly; Bennett, Alexander N

    2015-11-01

    To evaluate the functional and mental health status of severely injured traumatic amputees from the United Kingdom military at the completion of their rehabilitation pathway and to compare these data with the published normative data. Retrospective independent group comparison of descriptive rehabilitation data recorded postrehabilitation. A military complex trauma rehabilitation center. Amputees (N=65; mean age, 29±6 y) were evaluated at the completion of their rehabilitation pathway; of these, 54 were operationally (combat) injured (23 unilateral, 23 bilateral, 8 triple) and 11 nonoperationally injured (all unilateral). Continuous ∼4-week inpatient, physician-led, interdisciplinary rehabilitation followed by ∼4-weeks of patient-led, home-based rehabilitation. The New Injury Severity Score at the point of injury was used as the baseline reference. The 6-minute walk test, Amputee Mobility Predictor with Prosthesis, Special Interest Group in Amputee Medicine, Defence Medical Rehabilitation Centre mobility and activity of daily living scores as well as depression (Patient Health Questionnaire-9), anxiety (General Anxiety Disorder Scale-7), mental health support, and pain scores were recorded at discharge and compared with the published normative data. The mean New Injury Severity Score was 40±15. After 34±14 months of rehabilitation, amputees achieved a mean 6-minute walk distance of 489±117 m compared with age-matched normative distances of 459 to 738 m. The 2 unilateral groups walked (544 m) significantly further (P>.05) than did the bilateral amputee (445±104 m) and triple amputee (387±99 m) groups. All groups demonstrated mean functional mobility scores consistent with scores of either active adults or community ambulators with limb loss. In total, 85% could walk/run independently and 95% could walk and perform activities of daily living independently with an aid/adaptation. No significant difference in mental health outcome was reported between the

  6. Nurse managers' decision-making in daily unit operation in peri-operative settings: a cross-sectional descriptive study.

    Science.gov (United States)

    Siirala, Eriikka; Peltonen, Laura-Maria; Lundgrén-Laine, Heljä; Salanterä, Sanna; Junttila, Kristiina

    2016-09-01

    To describe the tactical and the operational decisions made by nurse managers when managing the daily unit operation in peri-operative settings. Management is challenging as situations change rapidly and decisions are constantly made. Understanding decision-making in this complex environment helps to develop decision support systems to support nurse managers' operative and tactical decision-making. Descriptive cross-sectional design. Data were collected from 20 nurse managers with the think-aloud method during the busiest working hours and analysed using thematic content analysis. Nurse managers made over 700 decisions; either ad hoc (n = 289), near future (n = 268) or long-term (n = 187) by nature. Decisions were often made simultaneously with many interruptions. Ad hoc decisions covered staff allocation, ensuring adequate staff, rescheduling surgical procedures, confirmation tangible resources and following-up the daily unit operation. Decisions in the near future were: planning of surgical procedures and tangible resources, and planning staff allocation. Long-term decisions were: human recourses, nursing development, supplies and equipment, and finances in the unit. Decision-making was vulnerable to interruptions, which sometimes complicated the managing tasks. The results can be used when planning decision support systems and when defining the nurse managers' tasks in peri-operative settings. © 2016 John Wiley & Sons Ltd.

  7. Female Participation in Formed Police Units: A Report on the Integration of Women in Formed Police Units of Peacekeeping Operations

    Science.gov (United States)

    2012-09-01

    of Peacekeeping Operations in accor- dance with the principles of United Nations (UN) Res- olution 1325. To address this topic the study (1) briefly...that the eligibility criteria was revised to include women who played support roles to the combatants, as cooks, por- ters, sex slaves or spies

  8. Comprehensive Status and Trends of Nitrogen Loads to Estuaries in the Conterminous United States: Pacific Coast Results

    Science.gov (United States)

    We applied regional SPARROW (SPAtially Referenced Regressions On Watershed attributes) models to estimate status and trends of potential nitrogen loads to estuaries of the conterminous United States. The original Regional SPARROW models predict average detrended loads by source ...

  9. Fatigue status assessment for reactor pressure vessel based on actual operational transient

    International Nuclear Information System (INIS)

    Zhu Guangqiang; Liao Changbin; Dai Bing; Gui Chun

    2013-01-01

    Background: Fatigue is an important aging mechanism in RPV and it must be contained to aging management working range. Purpose: In order to ensure the safety operation of nuclear power plants, as extension of RPV service time, it is necessary to assess the fatigue damage caused by actual operation transient. Methods: Based on monitoring data of actual operation during the past eleven years, refer to design transient, the statistic analysis for types and occurrence times of actual transient is carried out, at the same time, every transients are combined as different operation cycles and the temperature field and stress field of typical components are analyzed by FEM. Results: Based on these information, fatigue analysis and assessment are finished, if later-actual transients are similar with the previous transients, the calculation result shows that the ratio between maximum of cumulative usage factors and design calculation value is 0.4967 the design transients is conservative. Conclusions: Fatigue status of RPV could be assessed and traced quickly through fatigue status assessment method in this paper based on actual operational transient and assessment result would be a good reference for RPV aging management. (authors)

  10. Food irradiation in Asia, the European Union, and the United States. A status update

    International Nuclear Information System (INIS)

    Kume, Tamikazu; Todoriki, Setsuko

    2013-01-01

    This paper reviewed the status of food irradiation in Asia, the European Union, and the United States in 2010. Our results show that quantities of irradiated foods in Asia, the EU, and the US in 2010 were estimated at 285200, 9300, and 103000 tons, respectively. Compared with 2005, the quantity of irradiated foods was 100000 tons higher in Asia and 10000 tons higher in the US but 6000 tons lower in the EU. Thus, commercial food irradiation has increased significantly in Asia during the 5-year period studied. Phytosanitary irradiation of fruits and agricultural products has recently increased with 6 countries having irradiated 18500 tons in 2010. (author)

  11. Status of development and licensing support for advanced liquid metal reactors in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Pedersen, D R [Argonne National Laboratory, Argonne, IL (United States); Gyorey, G [General Electric, San Jose, CA (United States)

    1991-07-01

    The cornerstones of the United States Advanced Liquid Metal Cooled Reactor (ALMR) program sponsored by the Department of Energy are: the ALMR plant design program at General Electric based on the PRISM (Power Reactor Innovative Small Module) concept, and the Integral Fast Reactor program (IFR) at Argonne National Laboratory (ANL). The goal of the U.S. program is to produce a standard, commercial ALMR, including the associated fuel cycle. The paper addresses the status of the IFR program, the ALMR program and the interaction of the ALMR program with the regulatory environment. (author)

  12. Status of development and licensing support for advanced liquid metal reactors in the United States

    International Nuclear Information System (INIS)

    Pedersen, D.R.; Gyorey, G.

    1991-01-01

    The cornerstones of the United States Advanced Liquid Metal Cooled Reactor (ALMR) program sponsored by the Department of Energy are: the ALMR plant design program at General Electric based on the PRISM (Power Reactor Innovative Small Module) concept, and the Integral Fast Reactor program (IFR) at Argonne National Laboratory (ANL). The goal of the US program is to produce a standard, commercial ALMR, including the associated fuel cycle. The paper addresses the status of the IFR program, the ALMR program and the interaction of the ALMR program with the regulatory environment

  13. Status of development and licensing support for advanced liquid metal reactors in the United States

    International Nuclear Information System (INIS)

    Pedersen, D.R.; Gyorey, G.

    1991-01-01

    The cornerstones of the United States Advanced Liquid Metal Cooled Reactor (ALMR) program sponsored by the Department of Energy are: the ALMR plant design program at General Electric based on the PRISM (Power Reactor Innovative Small Module) concept, and the Integral Fast Reactor program (IFR) at Argonne National Laboratory (ANL). The goal of the U.S. program is to produce a standard, commercial ALMR, including the associated fuel cycle. The paper addresses the status of the IFR program, the ALMR program and the interaction of the ALMR program with the regulatory environment. (author)

  14. Multi-unit Operations in Non-Nuclear Systems: Lessons Learned for Small Modular Reactors

    Energy Technology Data Exchange (ETDEWEB)

    OHara J. M.; Higgins, J.; DAgostino, A.

    2012-01-17

    The nuclear-power community has reached the stage of proposing advanced reactor designs to support power generation for decades to come. Small modular reactors (SMRs) are one approach to meet these energy needs. While the power output of individual reactor modules is relatively small, they can be grouped to produce reactor sites with different outputs. Also, they can be designed to generate hydrogen, or to process heat. Many characteristics of SMRs are quite different from those of current plants and may be operated quite differently. One difference is that multiple units may be operated by a single crew (or a single operator) from one control room. The U.S. Nuclear Regulatory Commission (NRC) is examining the human factors engineering (HFE) aspects of SMRs to support licensing reviews. While we reviewed information on SMR designs to obtain information, the designs are not completed and all of the design and operational information is not yet available. Nor is there information on multi-unit operations as envisioned for SMRs available in operating experience. Thus, to gain a better understanding of multi-unit operations we sought the lesson learned from non-nuclear systems that have experience in multi-unit operations, specifically refineries, unmanned aerial vehicles and tele-intensive care units. In this paper we report the lessons learned from these systems and the implications for SMRs.

  15. Analysis of Fukushima unit 2 accident considering the operating conditions of RCIC system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung Il, E-mail: sikim@kaeri.re.kr; Park, Jong Hwa; Ha, Kwang Soon; Cho, Song-Won; Song, JinHo

    2016-03-15

    Highlights: • Fukushima unit 2 accident was analyzed using MELCOR 1.8.6. • RCIC operating conditions were assumed and best case was selected. • Effect of RCIC operating condition on accident scenario was found. - Abstract: A severe accident in Fukushima occurred on March 11, 2011 and units 1, 2 and 3 were damaged severely. A tsunami following an earthquake made the supply of electricity power stop, and the safety systems, which use AC or DC power in plants could not operate properly. It is supposed that the degree of core degradation of unit 2 is less serious than in the other plants, and it was estimated that the operation of reactor core isolation cooling (RCIC) system at the initial stage of the accident minimized the core damage through decay heat removal. Although the operating conditions of the RCIC system are not known clearly, it can be important to analyze the accident scenario of unit 2. In this study, best case of the Fukushima unit 2 accident was presented considering the operating conditions of the RCIC system. The effects of operating condition on core degradation and fission product release rate to environment were also examined. In addition, importance of torus room flooding level in the accident analysis was discussed. MELCOR 1.8.6 was used in this research, and the geometries of plant and operating conditions of safety system were obtained from TEPCO through OECD/NEA BSAF Project.

  16. Explicit isospectral flows for the AKNS operator on the unit interval

    International Nuclear Information System (INIS)

    Amour, L

    2009-01-01

    We consider the AKNS operator on the unit interval. The boundary conditions are self-adjoint separated boundary conditions. For fixed boundary conditions, we make the formulae for flows induced by general tangent vector fields on isospectral sets explicit

  17. Analysis of the Vertical Takeoff and Landing Unmanned Aerial Vehicle (VTUAV) in Small Unit Urban Operations

    National Research Council Canada - National Science Library

    Cason, Roman

    2004-01-01

    ...) to replace the aging Pioneer Unmanned Aerial Vehicle (UAV) system. This thesis examines the critical elements this platform must possess to effectively support small units operating in urban environments...

  18. Start-up and commercial operation of the Laguna Verde power plants, unit 1

    International Nuclear Information System (INIS)

    Torres R, J.F.

    1991-01-01

    The main features of the unit 1 of the Laguna Verde Power Plant is presented as well as the phases of the start-up process. The process includes various steps and tests up to start the commercial operation. (author)

  19. Description of work for 100-DR-2 Operable Unit Vadose Drilling/test pits

    International Nuclear Information System (INIS)

    Naiknimbalkar, N.

    1993-01-01

    This report describes the scope of work for the boreholes/test pits of the 100-DR-2 Operable Unit. Sampling and field activities include: Soil screening; geologic sampling; soil sampling (physical property); analytical sampling and depths; and geophysical logging

  20. Pilgrim Nuclear Power Station, Unit 1. Annual operating report for 1976

    International Nuclear Information System (INIS)

    Net electrical power generated was 2,415,511 MWH with the generator on line 5,333.6 hrs. Information is presented concerning operations, procedure changes, tests, experiments, maintenance, unit shutdowns and power reductions, and radiation doses to personnel

  1. Proposed plan for remedial action at the quarry residuals operable unit of the Weldon Spring Site

    International Nuclear Information System (INIS)

    1998-03-01

    This proposed plan addresses the management of contamination present in various components of the quarry residuals operable unit (QROU) of the Weldon Spring site, which is located in St. Charles County, Missouri. The QROU consists of (1) residual waste at the quarry proper; (2) the Femme Osage Slough, Little Femme Osage Creek, and Femme Osage Creek; and (3) quarry groundwater located primarily north of the slough. Potential impacts to the St. Charles County well field downgradient of the quarry area are also being addressed as part of the evaluations for this operable unit. Remedial activities for the QROU will be conducted by the US Department of Energy (DOE) in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. As part of the remedial investigation/feasibility study (RI/FS) process required for the QROU under CERCLA, three major evaluation documents have been prepared to support cleanup decisions for this operable unit. decisions for this operable unit

  2. Salem Nuclear Generating Station, Unit 1. Annual operating report for 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Initial reactor criticality was achieved 12/11/76 and power generation began 12/25/76. Information is presented concerning operation, maintenance, procedure and specification changes, power generation, unit shutdowns and forced power reductions, testing, and personnel radiation exposures

  3. Record of Decision for the Ford Building Waste Unit (643-11G) Operable Unit; FINAL

    International Nuclear Information System (INIS)

    Fraley, S.

    2002-01-01

    This decision document presents the selected remedial for the Ford Building Waste Unit (FBWU), in Aiken, South Carolina, which was chosen in accordance with CERCLA, as amended by SARA, and, to the extent practical, the National Oil and Hazardous Substances Pollution Contingency Plan (NCP). This decision is based on the Administrative Record File for this specific RCRA/CERCLA site

  4. An operating nuclear utility's experience with the ALARA design of a new nuclear unit

    International Nuclear Information System (INIS)

    Rodgers, R.C.

    1985-01-01

    This talk presents a review of how operating experience at Northeast Utilities has been factored into the design of a new nuclear unit and the development and management of the radiation protection program. Their operational experience has indicated that there are two facets to keeping radiation exposures ALARA. The first is the proper ALARA design of the unit. The other facet is the design of a comprehensive radiation protection program. The author discusses these facets in some detail

  5. Safety Evaluation Report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2 (Docket Nos. 50-416 and 50-417). Supplement No. 5

    International Nuclear Information System (INIS)

    1984-08-01

    Supplement 5 to the Safety Evaluation Report for Mississippi Power and Light Company, et al., joint application for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2, located on the east bank of the Mississippi River near Port Gibson in Claiborne County, Mississippi, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status on the resolution of those issues that require further evaluation before authorizing operation of Unit 1 above 5% of rated power

  6. Licensed operating reactors. Status summary report, data as of September 30, 1984. Volume 8, No. 10

    International Nuclear Information System (INIS)

    1984-11-01

    This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States. The percentage computations, Items 20 through 24 in Section 2, the vendor capacity factors, and actual vs. potential energy production are computed using actual data for the period of consideration. The percentages listed in power generation are computed as an arithmetic average. The factors for the life-span of each unit (the Cumulative column) are reported by the utility. Utility power production data is checked for consistency with previously submitted statistics

  7. Quad-Cities Station, Units 1 and 2. Semiannual operating report, January--June 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Unit 1 generated 2,024,125 net electrical MWH and the generator was on line 3162.6 hours. Unit 2 generated 746,184 net electrical MWH and was on line 1475.3 hrs. Data is included concerning operations, power generation, shutdowns, maintenance, changes, and tests. (FS)

  8. H. B. Robinson Plant, Unit 2. Annual operating report for 1976

    International Nuclear Information System (INIS)

    1977-01-01

    The unit achieved a good performance record through the year, experiencing only short duration shutdowns or power reductions. Information is presented concerning operations, maintenance, shutdowns, and occupational radiation exposures. In November there was a scheduled refueling lasting 40 days. After a start-up physics test program, the unit achieved 100 percent power on December 22, 1976

  9. Dresden Nuclear Power Station, Units 1, 2, and 3. Annual operating report: January thru December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Net electrical energy generated by Unit 1 was 953,015.5 MWH with the generator on line 7,399.37 hrs. Unit 2 generated 4,371,553.689 MWH with the generator on line 6,664.58 hrs while Unit 3 generated 4,034,251 MWH with the generator on line 7,234.86 hrs. Information is presented concerning operations, maintenance, and shutdowns

  10. Status Report from the United Kingdom [Processing of Low-Grade Uranium Ores

    Energy Technology Data Exchange (ETDEWEB)

    North, A A [Warren Spring Laboratory, Stevenage, Herts. (United Kingdom)

    1967-06-15

    The invitation to present this status report could have been taken literally as a request for information on experience gained in the actual processing of low-grade uranium ores in the United Kingdom, in which case there would have been very little to report; however, the invitation naturally was considered to be a request for a report on the experience gained by the United Kingdom of the processing of uranium ores. Lowgrade uranium ores are not treated in the United Kingdom simply because the country does not possess any known significant deposits of uranium ore. It is of interest to record the fact that during the nineteenth century mesothermal vein deposits associated with Hercynian granite were worked at South Terras, Cornwall, and ore that contained approximately 100 tons of uranium oxide was exported to Germany. Now only some 20 tons of contained uranium oxide remain at South Terras; also in Cornwall there is a small number of other vein deposits that each hold about five tons of uranium. Small lodes of uranium ore have been located in the southern uplands of Scotland; in North Wales lower palaeozoic black shales have only as much as 50 to 80 parts per million of uranium oxide, and a slightly lower grade carbonaceous shale is found near the base of the millstone grit that occurs in the north of England. Thus the experience gained by the United Kingdom has been of the treatment of uranium ores that occur abroad.

  11. 2006 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

    International Nuclear Information System (INIS)

    D. E. Shanklin

    2007-01-01

    This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report covers the time period from January 1 through December 31, 2006, and describes inspection and monitoring activities for the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action (DOE/ID-10660) as described in the Group 1 Remedial Design/Remedial Action Work Plan (DOE/ID-10772)

  12. 2005 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

    International Nuclear Information System (INIS)

    D. Shanklin

    2006-01-01

    This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report describes inspection and monitoring activities for the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action, (DOE/ID-10660) and as amended by the agreement to resolve dispute, which was effective in February 2003

  13. Operational present status and reliability analysis of the upgraded EAST cryogenic system

    Science.gov (United States)

    Zhou, Z. W.; Y Zhang, Q.; Lu, X. F.; Hu, L. B.; Zhu, P.

    2017-12-01

    Since the first commissioning in 2005, the cryogenic system for EAST (Experimental Advanced Superconducting Tokamak) has been cooled down and warmed up for thirteen experimental campaigns. In order to promote the refrigeration efficiencies and reliability, the EAST cryogenic system was upgraded gradually with new helium screw compressors and new dynamic gas bearing helium turbine expanders with eddy current brake to improve the original poor mechanical and operational performance from 2012 to 2015. Then the totally upgraded cryogenic system was put into operation in the eleventh cool-down experiment, and has been operated for the latest several experimental campaigns. The upgraded system has successfully coped with various normal operational modes during cool-down and 4.5 K steady-state operation under pulsed heat load from the tokamak as well as the abnormal fault modes including turbines protection stop. In this paper, the upgraded EAST cryogenic system including its functional analysis and new cryogenic control networks will be presented in detail. Also, its operational present status in the latest cool-down experiments will be presented and the system reliability will be analyzed, which shows a high reliability and low fault rate after upgrade. In the end, some future necessary work to meet the higher reliability requirement for future uninterrupted long-term experimental operation will also be proposed.

  14. The current status of emergency operations at a high-volume cancer center.

    Science.gov (United States)

    Komori, Koji; Kimura, Kenya; Kinoshita, Takashi; Ito, Seiji; Abe, Tetsuya; Senda, Yoshiki; Misawa, Kazunari; Ito, Yuichi; Uemura, Norihisa; Natsume, Seiji; Kawai, Ryosuke; Kawakami, Jiro; Asano, Tomonari; Iwata, Yoshinori; Kurahashi, Shintaro; Tsutsuyama, Masayuki; Shigeyoshi, Itaru; Shimizu, Yasuhiro

    2014-01-01

    This study aimed to assess the pathogenic causes, clinical conditions, surgical procedures, in-hospital mortality, and operative death associated with emergency operations at a high-volume cancer center. Although many reports have described the contents, operative procedures, and prognosis of elective surgeries in high-volume cancer centers, emergency operations have not been studied in sufficient detail. We retrospectively enrolled 28 consecutive patients who underwent emergency surgery. Cases involving operative complications were excluded. The following surgical procedures were performed during emergency operations: closure in 3 cases (10.7%), diversion in 22 cases (78.6%), ileus treatment in 2 cases (7.1%), and hemostasis in 1 case (3.6%). Closure alone was performed only once for peritonitis. Diversion was performed in 17 cases (77.3%) of peritonitis, 4 cases (18.2%) of stenosis of the gastrointestinal tract, and 1 case (4.5%) of bleeding. There was a significant overall difference (P = 0.001). The frequency of emergency operations was very low at a high-volume cancer center. However, the recent shift in treatment approaches toward nonoperative techniques may enhance the status of emergency surgical procedures. The results presented in this study will help prepare for emergency situations and resolve them as quickly and efficiently as possible.

  15. State-level differences in breast and cervical cancer screening by disability status: United States, 2008.

    Science.gov (United States)

    Armour, Brian S; Thierry, JoAnn M; Wolf, Lesley A

    2009-01-01

    Despite reported disparities in the use of preventive services by disability status, there has been no national surveillance of breast and cervical cancer screening among women with disabilities in the United States. To address this, we used state-level surveillance data to identify disparities in breast and cervical cancer screening among women by disability status. Data from the 2008 Behavioral Risk Factor Surveillance System were used to estimate disability prevalence and state-level differences in breast and cervical cancer screening among women by disability status. Overall, modest differences in breast cancer screening were found; women with a disability were less likely than those without to report receiving a mammogram during the past 2 years (72.2% vs. 77.8%; p < .001). However, disparities in breast cancer screening were more pronounced at the state level. Furthermore, women with a disability were less likely than those without a disability to report receiving a Pap test during the past 3 years (78.9% vs. 83.4%; p < .001). This epidemiologic evidence identifies an opportunity for federal and state programs, as well as other stakeholders, to form partnerships to align disability and women's health policies. Furthermore, it identifies the need for increased public awareness and resource allocation to reduce barriers to breast and cervical cancer screening experienced by women with disabilities.

  16. Status of liquid metal reactor development in the United States of America

    International Nuclear Information System (INIS)

    Griffith, J.D.; Horton, K.E.

    1991-01-01

    An existing network of government and industry research facilities and engineering test centers in the United States is currently providing test capabilities and the technical expertise required to conduct an aggressive advanced reactor development program. Subsequent to the directive to shut down the Fast Flux Test Facility in early 1990, a variety of activities were undertaken to provide support for continued operation. The United States has made substantial progress in achieving ALMR program objectives. The metal fuel cycle is designed to recycle and burn its own actiniums, and has the potential to be a very effective burner of actiniums generated in the LWRs. The current emphasis in the IFR Program is on the comprehensive development of the IFR (Integral Fast Reactor) technology, to be followed by a period of technology demonstration which would verify the economic feasibility of the concept. The United States has been active in international cooperative activities in the fast reactor sector since 1969. (author). 11 figs, 1 tab

  17. Plutonium Finishing Plan (PFP) Treatment and Storage Unit Interim Status Closure Plan

    International Nuclear Information System (INIS)

    PRIGNANO, A.L.

    2000-01-01

    This document describes the planned activities and performance standards for closing the Plutonium Finishing Plant (PFP) Treatment and Storage Unit. The PFP Treatment and Storage Unit is located within the 234-52 Building in the 200 West Area of the Hanford Facility. Although this document is prepared based upon Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the unit will comply with Washington Administrative Code (WAC) 173-303-610 regulations pursuant to Section 5.3 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Action Plan (Ecology et al. 1996). Because the PFP Treatment and Storage Unit manages transuranic mixed (TRUM) waste, there are many controls placed on management of the waste. Based on the many controls placed on management of TRUM waste, releases of TRUM waste are not anticipated to occur in the PFP Treatment and Storage Unit. Because the intention is to clean close the PFP Treatment and Storage Unit, postclosure activities are not applicable to this closure plan. To clean close the unit, it will be demonstrated that dangerous waste has not been left onsite at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or is environmentally impractical, the closure plan will be modified to address required postclosure activities. The PFP Treatment and Storage Unit will be operated to immobilize and/or repackage plutonium-bearing waste in a glovebox process. The waste to be processed is in a solid physical state (chunks and coarse powder) and will be sealed into and out of the glovebox in closed containers. The containers of immobilized waste will be stored in the glovebox and in additional permitted storage locations at PFP. The waste will be managed to minimize the potential for spills outside the glovebox, and to preclude spills from reaching soil. Containment surfaces will be maintained to ensure

  18. 78 FR 14361 - U.S. Steel Tubular Products, Inc., Mckeesport Tubular Operations Division, Subsidiary of United...

    Science.gov (United States)

    2013-03-05

    ... Products, Inc., Mckeesport Tubular Operations Division, Subsidiary of United States Steel Corporation, Mckeesport, PA; Notice of Initiation of Investigation To Terminate Certification of Eligibility Pursuant to... Tubular Products, McKeesport Tubular Operations Division, Subsidiary of United States Steel Corporation...

  19. Operating experience with unit for sulfuric acid alkylation of isobutane by butylenes

    Energy Technology Data Exchange (ETDEWEB)

    Tagavov, I.T.; Sumanov, V.T.; Khadzhiev, S.N.

    1988-09-01

    The operation of units for the sulfuric acid alkylation of isobutanes by butylenes have been performed. The reaction was carried out in a KSG-3 horizontal sulfuric acid contractor. A butane-butylene fraction from catalytic cracking and an isobutane fraction from the central gas fractionating unit were used as a feedstock. The studies have shown that the unit will give a high-quality product under various conditions of operation. The specific consumption of sulfuric acid in processing different types of feed remains within acceptable limits.

  20. Decommissioning strategy of the operating WWER type units in the Ukraine

    International Nuclear Information System (INIS)

    Litvinsky, L.L.; Lobach, Yu.N.; Skripov, A.E.

    2002-01-01

    At present in Ukraine, 13 WWER type units are in operation and two other ones are in the final stage of construction. Decommissioning of these units is expected after the year 2010. General planning of their decommissioning is developed in the framework of the decommissioning strategy of operating WWER type units. The strategy contains the objectives, principles and main tasks of the decommissioning as well as the activities at each phase of decommissioning. It is considered a broad range of factors important for the planning and implementation of decommissioning. (author)

  1. Operational status of the JAEA-MUTSU tandetron AMS 2008-2009

    International Nuclear Information System (INIS)

    Kabuto, Shoji; Kinoshita, Naoki; Tanaka, Takayuki; Yamamoto, Nobuo

    2010-01-01

    A Tandetron Accelerator Mass Spectrometer (AMS) manufactured by High Voltage Engineering Europa in Netherlands had been set up at the Mutsu office of Aomori Research and Development Center, Japan Atomic Energy Agency (JAEA) in 1997. This AMS features 3MV Tandetron accelerator and two independence beamlines for 14 C and 129 I measurement. This AMS has measured both internal and external JAEA researcher's samples based on an open door policy since April 2006. Furthermore, the total operation time of this AMS from the routine operation started exceeds more than 20,000 hours in this year. In this report, we describe not only the summary of the current status and troubles from the previous symposium but also the upgrading of the operation system in this AMS which is carried out from June to July in 2009. (author)

  2. OPERATING OF MOBILE MACHINE UNITS SYSTEM USING THE MODEL OF MULTICOMPONENT COMPLEX MOVEMENT

    Directory of Open Access Journals (Sweden)

    A. Lebedev

    2015-07-01

    Full Text Available To solve the problems of mobile machine units system operating it is proposed using complex multi-component (composite movement physical models. Implementation of the proposed method is possible by creating of automatic operating systems of fuel supply to the engines using linear accelerometers. Some examples to illustrate the proposed method are offered.

  3. Operating of mobile machine units system using the model of multicomponent complex movement

    OpenAIRE

    A. Lebedev; R. Kaidalov; N. Artiomov; M. Shulyak; M. Podrigalo; D. Abramov; D. Klets

    2015-01-01

    To solve the problems of mobile machine units system operating it is proposed using complex multi-component (composite) movement physical models. Implementation of the proposed method is possible by creating of automatic operating systems of fuel supply to the engines using linear accelerometers. Some examples to illustrate the proposed method are offered.

  4. Oconee Nuclear Station, Units 1, 2, and 3. Semiannual operating report, January--June 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Information is presented concerning operations, performance characteristics, changes, tests, inspections, containment leak tests, maintenance, primary coolant chemistry, station staff changes, reservoir investigations, plume mapping, and operational environmental radioactivity monitoring data for oconee Units 1, 2, and 3. The non-radiological environmental surveillance program is also described. (FS)

  5. Effect of RCIC Operating Conditions on the Accident Scenario in Fukushima Unit 2

    International Nuclear Information System (INIS)

    Kim, Sung Il; Park, Jong Hwa; Ha, Kwang Soon

    2015-01-01

    This study was conducted by using MELCOR 1.8.6. Fukushima unit 2 accident was analyzed using MELCOR in this study, and best estimate scenario with considering RCIC operating conditions was presented. Researches on the boiling water reactor (BWR) plant with reactor core isolation cooling (RCIC) system have been conducted. Research on the RCIC operation in Fukushima unit 2 was also conducted by Sandia National Laboratory. MELCOR analysis of the Fukushima unit 2 accident was conducted in the report and energy balance in wetwell was described by considering RCIC operation. However, the effect of RCIC operation condition on the accident scenario has not been studied. The operating conditions of RCIC system affect the pressures in wetwell and drywell, and the high pressure can make leakage path of fission product from PCV to reactor building. Thus it can be directly related with the amount of fission product which released to environment. In this study, severe accident on Fukushima unit 2 was analyzed considering the operating condition of RCIC system, and best estimated scenario was presented. In addition, the effect of RCIC turbine efficiency on the accident progression was examined. Energy balance in suppression chamber was also considered with discussion on the effect of torus room flooding level. It was found that the operating condition of RCIC turbine not only affects the variation of drywell pressure but also the amount of released fission products to environment. It was also confirmed that the RCIC turbine efficiency in the accident would be less than normal operating condition

  6. Analysis of long-time operation of micro-cogeneration unit with fuel cell

    Directory of Open Access Journals (Sweden)

    Patsch Marek

    2015-01-01

    Full Text Available Micro-cogeneration is cogeneration with small performance, with maximal electric power up to 50 kWe. On the present, there are available small micro-cogeneration units with small electric performance, about 1 kWe, which are usable also in single family houses or flats. These micro-cogeneration units operate on principle of conventional combustion engine, Stirling engine, steam engine or fuel cell. Micro-cogeneration units with fuel cells are new progressive developing type of units for single family houses. Fuel cell is electrochemical device which by oxidation-reduction reaction turn directly chemical energy of fuel to electric power, secondary products are pure water and thermal energy. The aim of paper is measuring and evaluation of operation parameters of micro-cogeneration unit with fuel cell which uses natural gas as a fuel.

  7. United States Department of Energy, Nevada Operations Office, completion report Operation KLAXON, Fiscal Year 1993

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The U.S. Department of Energy, Nevada Operations Office (DOE/NV), Completion Report provides a summary of activities conducted at the Nevada Test Site (NTS) between October 1, 1992, and September 30, 1993, associated with Operation KLAXON. (In the past, each annual Completion Report dealt with a series of underground nuclear detonations; however, because no nuclear tests were conducted during FY 1993, this Report summarizes continuing nonnuclear and nuclear test readiness activities at the NTS sponsored by DOE/NV.) The report serves as a reference for those involved with the planning and execution of Operation KLAXON and also serves as a planning guide for future operations. Information in the report covers the logistics and management of activities. Scientific information and data associated with NTS activities are presented in technical documents published by participating agencies. In September 1992, Congress legislated a nine-month moratorium on the testing of nuclear weapons. The bill also provided for a resumption of testing (with no more than five tests per year, or a total of 15 during the next three years) in July 1993, and mandated an end to nuclear testing, entirely, by 1996. President Bush signed the bill into law in October 1992.

  8. United States Department of Energy, Nevada Operations Office, completion report Operation KLAXON, Fiscal Year 1993

    International Nuclear Information System (INIS)

    1994-06-01

    The U.S. Department of Energy, Nevada Operations Office (DOE/NV), Completion Report provides a summary of activities conducted at the Nevada Test Site (NTS) between October 1, 1992, and September 30, 1993, associated with Operation KLAXON. (In the past, each annual Completion Report dealt with a series of underground nuclear detonations; however, because no nuclear tests were conducted during FY 1993, this Report summarizes continuing nonnuclear and nuclear test readiness activities at the NTS sponsored by DOE/NV.) The report serves as a reference for those involved with the planning and execution of Operation KLAXON and also serves as a planning guide for future operations. Information in the report covers the logistics and management of activities. Scientific information and data associated with NTS activities are presented in technical documents published by participating agencies. In September 1992, Congress legislated a nine-month moratorium on the testing of nuclear weapons. The bill also provided for a resumption of testing (with no more than five tests per year, or a total of 15 during the next three years) in July 1993, and mandated an end to nuclear testing, entirely, by 1996. President Bush signed the bill into law in October 1992

  9. Use of Special Operations Forces in United Nations Missions: a Method to Resolve Complexity

    Science.gov (United States)

    2015-05-21

    physical stamina and psychological stability, followed by a rigorous training program are the imperatives to create SOF soldiers.42 Mark Bowden in...recommendation is that the United Nations should establish a Special Operations planning cell within the UN Department of Peacekeeping Operations. As of...now, the cell is nonexistent. This cell should be able to facilitate the integration of SOF into the overall peace operations concept. Finally, the

  10. Regulation imposed to nuclear facility operators for the elaboration of 'waste studies' and 'waste statuses'

    International Nuclear Information System (INIS)

    2001-01-01

    This decision from the French authority of nuclear safety (ASN) aims at validating the new versions of the guidebook for the elaboration of 'waste studies' for nuclear facilities and of the specifications for the elaboration of 'waste statuses' for nuclear facilities. This paper includes two documents. The first one is a guidebook devoted to nuclear facility operators which fixes the rules of production of waste studies according to the articles 20 to 26 of the inter-ministry by-law from December 31, 1999 (waste zoning conditions and ASN's control modalities). The second document concerns the specifications for the establishment of annual waste statuses according to article 27 of the inter-ministry by-law from December 31, 1999 (rational management of nuclear wastes). (J.S.)

  11. Indian Point Station, Units 1, 2, and 3. Annual operating report for 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Unit 1 remained in a shutdown condition pending a decision by the Company on the installation of an ECCS as required by NRC. Net electrical power generated by Unit 2 was 2,267,654 MWH with the unit on line 3,056.45 hrs. Unit 3 generated 1,872,947 MWH and was on line 2,286.01 hrs. Information is presented concerning operations, reportable events, corrective maintenance, fuel performance, radioactivity releases, shutdowns, primary coolant chemistry, and occupational radiation exposures

  12. Results of toxicity tests and chemical analyses conducted on sediments collected from the TNX Outfall Delta Operable Unit, July 1999

    International Nuclear Information System (INIS)

    Specht, W.L.

    2000-01-01

    In order to provide unit specific toxicity data that will be used to address critical uncertainty in the ecological risk assessment (ERA) for the TNX Outfall Delta Operable Unit (TNXOD OU), sediments were collected from eight locations in the Inner Swamp portion of the operable unit and two unit specific background locations. These samples were analyzed for total mercury, total uranium, and sediment toxicity

  13. An Analysis of United States Marine Corps Enlisted Entry-Level Training Using Supply Chain and Operations Management

    Science.gov (United States)

    2010-12-01

    An Analysis of United States Marine Corps Enlisted Entry-Level Training Using Supply Chain and Operations Management ______________________________________ By...Report 4. TITLE AND SUBTITLE: An Analysis of United States Marine Corps Enlisted Entry-Level Training Using Supply Chain and Operations Management 6...Level Training; United States Marine Corps; Operations Management ; Supply Chain Management; Process Analysis 16. PRICE CODE 17. SECURITY

  14. High magnetic field science and its application in the United States current status and future directions

    CERN Document Server

    National Research Council of the National Academies

    2013-01-01

    The Committee to Assess the Current Status and Future Direction of High Magnetic Field Science in the United States was convened by the National Research Council in response to a request by the National Science Foundation. This report answers three questions: (1) What is the current state of high-field magnet science, engineering, and technology in the United States, and are there any conspicuous needs to be addressed? (2) What are the current science drivers and which scientific opportunities and challenges can be anticipated over the next ten years? (3) What are the principal existing and planned high magnetic field facilities outside of the United States, what roles have U.S. high field magnet development efforts played in developing those facilities, and what potentials exist for further international collaboration in this area? A magnetic field is produced by an electrical current in a metal coil. This current exerts an expansive force on the coil, and a magnetic field is "high" if it challenges the str...

  15. Safety Evaluation Report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353). Supplement No. 6

    International Nuclear Information System (INIS)

    1985-08-01

    In August 1983 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the licensee) for licenses to operate the Limerick Generating Station, Units 1 and 2, located on a site in Montgomery and Chester Counties, Pennsylvania. A license for the operation of Limerick Unit 1 was issued on October 26, 1984. The license, which was restricted to a five percent power level, contained conditions which required resolution prior to proceeding beyond the five percent power level. Supplement 4, issued in May 1985, addressed some of these issues. Supplement 4 also contained the comments made by the Advisory Committee on Reactor Safeguards in its report dated November 6, 1984, regarding full power operation of Limerick Unit 1. Supplement 5, issued in July 1985, and this Supplement 6 address further issues, principally the status of offsite emergency planning, that require resolution prior to proceeding beyond the five percent power level

  16. Status and trends of land change in the Eastern United States—1973 to 2000

    Science.gov (United States)

    Sayler, Kristi L.; Acevedo, William; Taylor, Janis

    2016-09-28

    PrefaceU.S. Geological Survey (USGS) Professional Paper 1794–D is the fourth in a four-volume series on the status and trends of the Nation’s land use and land cover, providing an assessment of the rates and causes of land-use and land-cover change in the Eastern United States between 1973 and 2000. Volumes A, B, and C provide similar analyses for the Western United States, the Great Plains of the United States, and the Midwest–South Central United States, respectively. The assessments of land-use and land-cover trends are conducted on an ecoregion-by-ecoregion basis, and each ecoregion assessment is guided by a nationally consistent study design that includes mapping, statistical methods, field studies, and analysis. Individual assessments provide a picture of the characteristics of land change occurring in a given ecoregion; in combination, they provide a framework for understanding the complex national mosaic of change and also the causes and consequences of change. Thus, each volume in this series provides a regional assessment of how (and how fast) land use and land cover are changing, and why. The four volumes together form the first comprehensive picture of land change across the Nation.Geographic understanding of land-use and land-cover change is directly relevant to a wide variety of stakeholders, including land and resource managers, policymakers, and scientists. The chapters in this volume present brief summaries of the patterns and rates of land change observed in each ecoregion in the Eastern United States, together with field photographs, statistics, and comparisons with other assessments. In addition, a synthesis chapter summarizes the scope of land change observed across the entire Eastern United States. The studies provide a way of integrating information across the landscape, and they form a critical component in the efforts to understand how land use and land cover affect important issues such as the provision of ecological goods and

  17. Status of existing federal environmental risk-based standards applicable to Department of Energy operations

    International Nuclear Information System (INIS)

    Bilyard, G.R.

    1991-09-01

    When conducting its environmental restoration, waste management, and decontamination and decommissioning activities, the US Department of Energy (DOE) must comply with a myriad of regulatory procedures and environmental standards. This paper assesses the status of existing federal risk-based standards that may be applied to chemical and radioactive substances on DOE sites. Gaps and inconsistencies among the existing standards and the technical issues associated with the application of those standards are identified. Finally, the implications of the gaps, inconsistencies, and technical issues on DOE operations are discussed, and approaches to resolving the gaps, inconsistencies, and technical issues are identified. 6 refs

  18. Deep-well injection of liquid radwaste in Russia - current status and operations

    International Nuclear Information System (INIS)

    Bradley, D.J.; Foley, M.G.; Rybal'chenko, A.I.

    1995-01-01

    This paper is submitted as part of a coordinated effort to present the topic of deep-well injection. The companion paper, open-quotes Deep-Well Injection of Liquid Radwaste in Russia - Background and Technical Basis,close quotes focuses on the original decision to inject liquid radwaste, the research behind that decision, and the design and construction of the injection facilities. The emphasis in this paper is on the current status and operation of the well facilities and the control systems used to minimize environmental impact

  19. 100 Area source operable unit focused feasibility study report. Draft A

    International Nuclear Information System (INIS)

    1994-09-01

    In accordance with the Hanford Past-Practice Strategy (HPPS), a focused feasibility study (FFS) is performed for those waste sites which have been identified as candidates for interim remedial measures (IRM) based on information contained in applicable work plans and limited field investigations (LFI). The FFS process for the 100 Area source operable units will be conducted in two stages. This report, hereafter referred to as the Process Document, documents the first stage of the process. In this stage, IRM alternatives are developed and analyzed on the basis of waste site groups associated with the 100 Area source operable units. The second stage, site-specific evaluation of the IRM alternatives presented in this Process Document, is documented in a series of operable unit-specific reports. The objective of the FFS (this Process Document and subsequent operable unit-specific reports) is to provide decision makers with sufficient information to allow appropriate and timely selection of IRM for sites associated with the 100 Area source operable units. Accordingly, the following information is presented: a presentation of remedial action objectives; a description of 100 Area waste site groups and associated group profiles; a description of IRM alternatives; and detailed and comparative analyses of the IRM alternatives

  20. Current status of operation and utilization of the Dalat research reactor

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien; Le Van So

    2004-01-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500 kW swimming pool type reactor using the Soviet WWR-SM fuel assembly with 36% enrichment of U-235. It was upgraded from the USA 250 kW TRIGA Mark-II reactor. The first criticality of the renovated reactor was in November 1983 and its regular operation at nominal power of 500 kW has been since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs, once every 4 weeks, for radioisotope production, neutron activation analyses and research purposes. The remaining time between two continuous runs is devoted to maintenance activities and also to short run for physics experiments and training purpose. From the first start-up to the end of December 2002, it totaled about 24,700 hrs of operation and the total energy released was 490 MWd. After 10 years of operation with the core of 89-fuel assembly configuration, in April 1994, the first refueling work was done and the 100-fuel assembly configuration was set-up. The second fuel reloading was executed in March 2002. At present time, the working configuration of the reactor core consists of 104 fuel assemblies. This fuel reloading will ensure efficient exploitation of the reactor for about 3 years with 1200-1300 hrs per year at nominal power. The current status of operation and utilization and some activities related to the reactor core management of the DNRR are presented and discussed in this paper. (author)

  1. Current status of operation and utilization of the Dalat Research Reactor

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien

    2006-01-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500 kW pool-type reactor using the Soviet VVR-M2 fuel assembly with 36% enrichment of U-235. It was renovated and upgraded from the USA 250 kW TRIGA Mark-II reactor. The first criticality of the renovated reactor was in November 1983 and its regular operation at nominal power of 500 kW has been since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs, once every 4 weeks, for radioisotope production, neutron activation analysis, scientific research and training. The remaining time between two continuous runs is devoted to maintenance activities and also to short run for reactor physics and thermal hydraulics experiments. From the first start-up to the end of December 2003, it totaled about 26,000 hrs of operation and the total energy released was about 515 MWd. After 10 years of operation with the core of 89-fuel assembly configuration, in April 1994, the first refueling work was done and the 100-fuel assembly configuration was set-up. The second fuel reloading was executed in March 2002. At present time, the working configuration of the reactor core consists of 104 fuel assemblies. The next fuel reloading has been planned at the end of 2004. The current status of operation and utilization of the DNRR is presented and discussed in this paper. (author)

  2. The Applied Meteorology Unit: Nineteen Years Successfully Transitioning Research Into Operations for America's Space Program

    Science.gov (United States)

    Madura, John T.; Bauman, William H., III; Merceret, Francis J.; Roeder, William P.; Brody, Frank C.; Hagemeyer, Bartlett C.

    2011-01-01

    The Applied Meteorology Unit (AMU) provides technology development and transition services to improve operational weather support to America's space program . The AMU was founded in 1991 and operates under a triagency Memorandum of Understanding (MOU) between the National Aeronautics and Space Administration (NASA), the United States Air Force (USAF) and the National Weather Service (NWS) (Ernst and Merceret, 1995). It is colocated with the 45th Weather Squadron (45WS) at Cape Canaveral Air Force Station (CCAFS) and funded by the Space Shuttle Program . Its primary customers are the 45WS, the Spaceflight Meteorology Group (SMG) operated for NASA by the NWS at the Johnson Space Center (JSC) in Houston, TX, and the NWS forecast office in Melbourne, FL (MLB). The gap between research and operations is well known. All too frequently, the process of transitioning research to operations fails for various reasons. The mission of the AMU is in essence to bridge this gap for America's space program.

  3. Multipurpose units: combining of technological operations of a soil cultivating and seeding

    Directory of Open Access Journals (Sweden)

    D. A. Petukhov

    2015-01-01

    Full Text Available The modern domestic market of technique for grain crops seeding differs variety of machines brands and types. The intensive type technologies combining technological operations of a soil cultivating and grain crops seeding in one pass are more widely used. The authors have established that one-operational units in new machine park have to be replaced multipurpose, universal and combined machines. Such approach will reduce number of machines in grain production from 20-30 to 5-6 name titles. Possibilities of multipurpose sowing units for simultaneous fertilizers application, soil cultivating and weeds destruction were analyzed. It was specified that nowadays there are several technologies types with two, four or six operations overlapping. Operational performance, technological and economical efficiency of the best multipurpose and also efficiency of technological operations overlapping at grain crops cultivating in the conditions of their real operation and at a trial establishment in the Kuban research institute of information and technical and economic studies of agro-industrial complex engineering and technical services were studied. Tit was defined that use of multipurpose sowing units and also studied efficiency of decreases operational costs by 48-71 percent, fuel consumption - by 41-76 percent and reduces labor input by 72-80 percent. Thus grain crops seeding is possible in optimal agrotime because of 4-6 technological operations overlapping in one pass.

  4. Status of the Instrument Control Unit for EPD on-board Solar Orbiter

    Science.gov (United States)

    Sánchez Prieto, Sebastián; Da Silva, Antonio; Rodriguez Polo, Oscar; Parra Espada, Pablo; Gutierrez Molina, Oscar; Fernandez Salgado, Javier

    Solar Orbiter is the next heliospheric mission sponsored by ESA. The launch is planned for 2017 and it will be as close as 0.28 AU from the Sun. One of the instruments for Solar Orbiter is the Energetic Particle Detector (EPD) responsible for measuring energies from 2 keV to 200 MeV/n. EPD consists of four detectors, Electron Proton Telescope (EPT), High Energy Telescope (HET), SupraThermal Electrons, Ions, & Neutrals (STEIN), and Suprathermal Ion Spectrograph (SIS), plus the Instrument Control Unit called ICU. The Space Research Group of the University of Alcalá in Spain is the responsible for developing the ICU. In this work we present the development status of the ICU after the Critical Design Review. We also address the planned activities for the next year including the development of the Engineering and Qualification Model (EQM) and Flight Model (PM). Special focus is paid to the software and verification & validation activities.

  5. Status and prospects for renewable energy using wood pellets from the southeastern United States

    DEFF Research Database (Denmark)

    Dale, Virginia H.; Kline, Keith L.; Parish, Esther S.

    2017-01-01

    The ongoing debate about costs and benefits of wood-pellet based bioenergy production in the southeastern United States (SE USA) requires an understanding of the science and context influencing market decisions associated with its sustainability. Production of pellets has garnered much attention...... as US exports have grown from negligible amounts in the early 2000s to 4.6 million metric tonnes in 2015. Currently, 98% of these pellet exports are shipped to Europe to displace coal in power plants. We ask, 'How is the production of wood pellets in the SE USA affecting forest systems and the ecosystem...... services they provide?' To address this question, we review current forest conditions and the status of the wood products industry, how pellet production affects ecosystem services and biodiversity, and what methods are in place to monitor changes and protect vulnerable systems. Scientific studies provide...

  6. Marrying Up by Marrying Down: Status Exchange between Social Origin and Education in the United States.

    Science.gov (United States)

    Schwartz, Christine R; Zeng, Zhen; Xie, Yu

    2016-11-01

    Intermarriage plays a key role in stratification systems. Spousal resemblance reinforces social boundaries within and across generations, and the rules of intermarriage govern the ways that social mobility may occur. We examine intermarriage across social origin and education boundaries in the United States using data from the 1968-2013 Panel Study of Income Dynamics. Our evidence points to a pattern of status exchange-that is, persons with high education from modest backgrounds tend to marry those with lower education from more privileged backgrounds. Our study contributes to an active methodological debate by pinpointing the conditions under which the results pivot from evidence against exchange to evidence for exchange and advances theory by showing that the rules of exchange are more consistent with the notion of diminishing marginal utility than the more general theory of compensating differentials.

  7. Influence of deleting some of the inputs and outputs on efficiency status of units in DEA

    Directory of Open Access Journals (Sweden)

    Abbas ali Noora

    2013-06-01

    Full Text Available One of the important issues in data envelopment analysis (DEA is sensitivity analysis. This study discusses about deleting some of the inputs and outputs and investigates the influence of it on efficiency status of Decision Making Units (DMUs. To this end some models are presented for recognizing this influence on efficient DMUs. Model 2 (Model 3 in section 3 investigates the influence of deleting i(th input (r(th output on an efficient DMU. Thereafter these models are improved for deleting multiple inputs and outputs. Furthermore, a model is presented for recognizing the maximum number of inputs and (or outputs from among specified inputs and outputs which can be deleted, whereas an efficient DMU preserves its efficiency. Finally, the presented models are utilized for a set of DMUs and the results are reported.

  8. Economic impacts of electricity liberalization on the status of nuclear power generation in the United States

    International Nuclear Information System (INIS)

    Hattori, Toru

    2015-01-01

    This paper discusses the economic impact of electricity liberalization on the status of nuclear power generation in the United States. Nuclear power plants have been treated equally with other types of power plants in the liberalized electricity market. The existing nuclear power plants were thought to be competitive in liberalized wholesale electricity market. Competitive pressure from the market also facilitated efficiency improvement among the existing nuclear power plants. Although it was difficult to build new reactor, the U.S. nuclear power generators expanded capacity through up rates. In recent years, however, nuclear power plants suffer from the decline in wholesale power prices and some of them are forced to retire early. Although there are some market design issues that could be improved to maintain the efficient nuclear power plants in competitive environment, it is now argued that some additional arrangements to mitigate the investment risks of the nuclear power plants are necessary. (author)

  9. Highway vehicle electric drive in the United States : 2009 status and issues.

    Energy Technology Data Exchange (ETDEWEB)

    Santini, D. J.; Energy Systems

    2011-02-16

    The status of electric drive technology in the United States as of early 2010 is documented. Rapidly evolving electric drive technologies discussed include hybrid electric vehicles, multiple types of plug-in hybrid electric vehicles, and battery electric vehicles. Recent trends for hybrids are quantified. Various plug-in vehicles entering the market in the near term are examined. The technical and economic requirements for electric drive to more broadly succeed in a wider range of highway vehicle applications are described, and implications for the most promising new markets are provided. Federal and selected state government policy measures promoting and preparing for electric drive are discussed. Taking these into account, judgment on areas where increased Clean Cities funds might be most productively focused over the next five years are provided. In closing, the request by Clean Cities for opinion on the broad range of research needs providing near-term support to electric drive is fulfilled.

  10. FEASIBILITY STUDY REPORT FOR THE 200-ZP-1 GROUNDWATER OPERABLE UNIT

    Energy Technology Data Exchange (ETDEWEB)

    BYRNES ME

    2008-07-18

    , and to the extent practicable, the NCP. This FS conforms to the conditions set forth in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 2003) and amendments, signed by the Washington State Department of Ecology (Ecology), EPA, and DOE Richland Operations Office (RL). This also includes Tri-Party Agreement Milestone M-015-00C for completing all 200 Area non-tank farm OU pre-Record of Decision (ROD) documents on or before December 31, 2011. This FS supports the final remedy selection for the 200-ZP-1 OU, as described in the Remedial Investigation/Feasibility Study Work Plan for the 200-ZP-1 Groundwater Operable Unit (referred to as the 200-ZP-1 RI/FS work plan) (DOE/RL-2003-55), as agreed upon by RL and EPA. Tri-Party Agreement Milestone M-015-48B required Draft A of the 200-ZP-1 OU FS and proposed plan to be transmitted to EPA by September 30, 2007. As agreed to with EPA in the 200 Area Unit Managers Meeting Groundwater Operable Unit Status (FH-0503130), the baseline risk assessment (BRA) was delayed from inclusion in the remedial investigation (RI) report and is completed and documented in this FS. The Remedial Investigation Report for 200-ZP-1 Groundwater Operable Unit (referred to as the 200-ZP-1 RI report) (DOE/RL-2006-24) included an evaluation of human health and ecological risks and hazards. The RI report identified the radiological and chemical contaminants of potential concern (COPCs) that represent the primary risks to human health and the environment. The complete risk assessment in this FS incorporates additional analytical data from the unconfined aquifer that were obtained during or after preparation of the RI report, particularly for carbon tetrachloride and technetium-99. This FS also includes the initial results from an ongoing study of technetium-99 contamination near WMA-T, the sampling of new wells near the 216-W-LC laundry waste crib and T Plant, updated Hanford vadose zone fate and transport modeling

  11. An Analysis of the Reflector Cooling System Repair Status after the Initial Operation of HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Park, Young Chul; Seo, Kyoung Woo; Chi, Dae Young; Yoon, Hyun Gi [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Park, Jung Geun [Safety Evaluation Department, System D and D Co., Daejeon (Korea, Republic of)

    2011-05-15

    HANARO, an open-tank-in-pool type multi-purpose research reactor of 30 MWth power in Korea, has been operating normally since its initial criticality in February, 1995. During the last operation period of HANARO, when a trouble occurred, the trouble was fixed on site. As preventive maintenance can reduce the corrective maintenance, the reasons of the occurred troubles are reviewed to prepare preventive maintenance. About twelve hundred cases of work requests and nonconformance reports (NCRs) have been issued since the initial criticality of HANARO. The cases are analyzed according to the trouble status, the trouble equipment function and the cause of the major trouble for reflector cooling system (RCS, hereinafter) including cover gas system and leakage monitoring and collection system

  12. Iron status of toddlers, nonpregnant females, and pregnant females in the United States.

    Science.gov (United States)

    Gupta, Priya M; Hamner, Heather C; Suchdev, Parminder S; Flores-Ayala, Rafael; Mei, Zuguo

    2017-12-01

    Background: Total-body iron stores (TBI), which are calculated from serum ferritin and soluble transferrin receptor concentrations, can be used to assess the iron status of populations in the United States. Objective: This analysis, developed to support workshop discussions, describes the distribution of TBI and the prevalence of iron deficiency (ID) and ID anemia (IDA) among toddlers, nonpregnant females, and pregnant females. Design: We analyzed data from NHANES; toddlers aged 12-23 mo (NHANES 2003-2010), nonpregnant females aged 15-49 y (NHANES 2007-2010), and pregnant females aged 12-49 y (NHANES 1999-2010). We used SAS survey procedures to plot distributions of TBI and produce prevalence estimates of ID and IDA for each target population. All analyses were weighted to account for the complex survey design. Results: According to these data, ID prevalences (± SEs) were 15.1% ± 1.7%, 10.4% ± 0.5%, and 16.3% ± 1.3% in toddlers, nonpregnant females, and pregnant females, respectively. ID prevalence in pregnant females increased significantly with each trimester (5.3% ± 1.5%, 12.7% ± 2.3%, and 27.5% ± 3.5% in the first, second, and third trimesters, respectively). Racial disparities in the prevalence of ID among both nonpregnant and pregnant females exist, with Mexican American and non-Hispanic black females at greater risk of ID than non-Hispanic white females. IDA prevalence was 5.0% ± 0.4% and 2.6% ± 0.7% in nonpregnant and pregnant females, respectively. Conclusions: Available nationally representative data suggest that ID and IDA remain a concern in the United States. Estimates of iron-replete status cannot be made at this time in the absence of established cutoffs for iron repletion based on TBI. The study was registered at clinicaltrials.gov as NCT03274726. © 2017 American Society for Nutrition.

  13. Marital status and female and male contraceptive sterilization in the United States.

    Science.gov (United States)

    Eeckhaut, Mieke Carine Wim

    2015-06-01

    To examine female and male sterilization patterns in the United States based on marital status, and to determine if sociodemographic characteristics explain these patterns. Survival analysis of cross-sectional data from the female and male samples from the 2006-2010 National Survey of Family Growth. Not applicable. The survey is designed to be representative of the US civilian noninstitutionalized population, ages 15-44 years. None. Vasectomy and tubal sterilization. In the United States, vasectomy is the near-exclusive domain of married men. Never-married and ever-married single men, and never-married cohabiting men, had a low relative risk (RR) of vasectomy (RR = 0.1, 0.3, and 0.0, respectively), compared with men in first marriages. Tubal sterilization was not limited to currently married, or even to ever-married women, although it was less common among never-married single women (RR = 0.2) and more common among women in higher-order marriages (RR = 1.8), compared with women in first marriages. In contrast to vasectomy, differential use of tubal sterilization by marital status was driven in large part by differences in parity. This study shows that being unmarried at the time of sterilization--an important risk factor for poststerilization regret--was much more common among women than men. In addition to contributing to the predominance of female, vs. male, sterilization, this pattern highlights the importance of educating women on the permanency of sterilization, and the opportunity to increase reliance on long-acting reversible contraceptive methods. Copyright © 2015 American Society for Reproductive Medicine. Published by Elsevier Inc. All rights reserved.

  14. Evaluation of Nutritional Status in a Teaching Hospital Neonatal Intensive Care Unit

    Directory of Open Access Journals (Sweden)

    Mohammadreza Rafati

    2015-02-01

    Full Text Available Background: Extrauterine growth restriction remains a common and serious problem in newborns especially who are small, immature, and critically ill. Very low birth weight infants (VLBW had 97% and 40% growth failure at 36 weeks and 18-22 months post-conceptual age respectively. The postnatal development of premature infants is critically dependent on an adequate nutritional intake that mimics a similar gestational stage. Deficient protein or amino acid administration over an extended period may cause significant growth delay or morbidity in VLBW infants. The purpose of this study was to evaluate current nutritional status in the neonatal intensive care unit in a teaching hospital. Methods: During this prospective observational study, the nutritional status of 100 consecutive critically ill neonates were evaluated by anthropometric and biochemical parameters in a tertiary neonatal intensive care unit. Their demographic characteristics (weight, height and head circumference, energy source (dextrose and lipid and protein were recorded in the first, 5th, 10th, 15th and 20th days of admission and blood samples were obtained to measure serum albumin and prealbumin. The amount of calorie and protein were calculated for all of preterm and term neonates and compared to standard means separately. Results: The calorie and amino acids did not meet in the majority of the preterm and term neonates and mean daily parenteral calorie intake was 30% or lower than daily requirements based on neonates’ weight. Mortality rate was significantly higher in neonates with lower serum albumin and severity of malnutrition but not with serum prealbumin concentration. Conclusion: Infants were studied did not receive their whole of daily calorie and protein requirements and it is recommended early and enough administration of calorie source (dextrose, lipids and amino acids. Prealbumin was a more benefit biochemical parameter than albumin to evaluate short term nutrition

  15. Traffic citation rates among drivers of different residency status in the United States.

    Science.gov (United States)

    Romano, Eduardo; Tippetts, Scott; Fell, James; Eichelberger, Angela; Grosz, Milton; Wiliszowski, Connie

    2013-03-01

    Racial/ethnic groups in the United States may be overrepresented in motor-vehicle incidents (crashes and violations), particularly among low-acculturated immigrants coming from countries in which traffic laws are not well enforced. Some evidence suggests just the opposite. We collected and analyzed information on the residency status of licensed drivers in Florida and Tennessee to examine the hypothesis that the prevalence of seat-belt nonuse, DWI, speeding, and failures to obey a traffic signal was higher among recent immigrants than among US citizens. We rejected this hypothesis. Both in Florida and Tennessee, US citizens were more likely to be cited for DWI, seat-belt, or speeding violations than the noncitizens. However, immigrants were more often cited for failure-to-obey than US citizens. We concluded that residency status does, appear to play a role in the likelihood of traffic violations, but this role is far from uniform; varying depending upon the type of traffic violation, the racial/ethnic group, and the state in which the violation occurred. Copyright © 2012. Published by Elsevier Ltd.

  16. Conservation status of freshwater gastropods of Canada and the United States

    Science.gov (United States)

    Johnson, Paul D.; Bogan, Arthur E.; Brown, Kenneth M.; Burkhead, Noel M.; Cordeiro, James R.; Garner, Jeffrey T.; Hartfield, Paul D.; Lepitzki, Dwayne A.; Mackie, Gerry L.; Pip, Eva; Tarpley, Thomas A.; Tiemann, Jeremy S.; Whelan, Nathan V.; Strong, Ellen E.

    2013-01-01

    This is the first American Fisheries Society conservation assessment of freshwater gastropods (snails) from Canada and the United States by the Gastropod Subcommittee (Endangered Species Committee). This review covers 703 species representing 16 families and 93 genera, of which 67 species are considered extinct, or possibly extinct, 278 are endangered, 102 are threatened, 73 are vulnerable, 157 are currently stable, and 26 species have uncertain taxonomic status. Of the entire fauna, 74% of gastropods are imperiled (vulnerable, threatened, endangered) or extinct, which exceeds imperilment levels in fishes (39%) and crayfishes (48%) but is similar to that of mussels (72%). Comparison of modern to background extinction rates reveals that gastropods have the highest modern extinction rate yet observed, 9,539 times greater than background rates. Gastropods are highly susceptible to habitat loss and degradation, particularly narrow endemics restricted to a single spring or short stream reaches. Compilation of this review was hampered by a paucity of current distributional information and taxonomic uncertainties. Although research on several fronts including basic biology, physiology, conservation strategies, life history, and ecology are needed, systematics and curation of museum collections and databases coupled with comprehensive status surveys (geographic limits, threat identification) are priorities.

  17. Compex system for teaching and training operators for TPP and NPP power units

    International Nuclear Information System (INIS)

    Tsiptsyura, R.D.

    1985-01-01

    Requirements, taken as a principle for constructing the system for operator teaching and training (OTT), have been formulated on the basis of investigation of operators' work at TPP and NPP power units. Functional structure and a structural block-diagram for OTT are built. As a criterion, which determines the structure of any trainers, being a part of OTT a requirement has been chosen satisfying the correspondence beetween habits developed with the help of trainers and habits of real operators' work. Results of analysis permit to confirm that refusal or under statement of the role of any stage of operator training leads to reduction of quality of his training

  18. NRC plan for cleanup operations at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Lo, R.; Snyder, B.J.

    1980-07-01

    The NRC plan defines the functional role of the NRC in cleanup operations at Three Mile Island Unit 2 to assure that agency regulatory responsibilities and objectives will be fulfilled. The plan outlines NRC functions in TMI-2 cleanup operations in the following areas: (1) the functional relationship of NRC to other government agencies, the public, and the licensee to coordinate activities, (2) the functional roles of these organizations in cleanup operations, (3) the NRC review and decision-making procedure for the licensee's proposed cleanup operation, (4) the NRC/licensee estimated schedule of major actions, and (5) NRC's functional role in overseeing implementation of approved licensee activities

  19. Multi-unit Integration in Microfluidic Processes: Current Status and Future Horizons

    Directory of Open Access Journals (Sweden)

    Pratap R. Patnaik

    2011-07-01

    Full Text Available Microfluidic processes, mainly for biological and chemical applications, have expanded rapidly in recent years. While the initial focus was on single units, principally microreactors, technological and economic considerations have caused a shift to integrated microchips in which a number of microdevices function coherently. These integrated devices have many advantages over conventional macro-scale processes. However, the small scale of operation, complexities in the underlying physics and chemistry, and differences in the time constants of the participating units, in the interactions among them and in the outputs of interest make it difficult to design and optimize integrated microprocesses. These aspects are discussed here, current research and applications are reviewed, and possible future directions are considered.

  20. Safety Evaluation Report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

    International Nuclear Information System (INIS)

    1984-02-01

    Supplement 17 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for licenses to operate Diablo Canyon Nuclear Power Plants, Units 1 and 2 (Docket Nos. 50-275 and 50-323) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and the previous supplements

  1. Safety Evaluation Report, related to the operation of Byron Station, Units 1 and 2 (Docket Nos. STN 50-454 and STN 50-455)

    International Nuclear Information System (INIS)

    1983-11-01

    Supplement No. 3 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  2. Safety evaluation report related to the operation of Byron Station, Units 1 and 2. Docket Nos. STN 50-454 and STN 50-455

    International Nuclear Information System (INIS)

    1983-01-01

    Supplement No. 2 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  3. Safety Evaluation Report related to the operation of Byron Station, Units 1 and 2 (Docket Nos. STN 50-454 and STN 50-455)

    International Nuclear Information System (INIS)

    1984-05-01

    Supplement No. 4 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  4. Safety Evaluation Report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412). Supplement No. 2

    International Nuclear Information System (INIS)

    1986-08-01

    This report, Supplement No. 2 to the the Safety Evaluation Report for the application filed by the Duquesne Light Company, et al. (the applicant) for a license to operate the Beaver Valley Power Station Unit 2 (Docket No. 50-412), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time the Safety Evaluation Report was published

  5. Study of the thermal behavior of a latent heat cold storage unit operating under frosting conditions

    International Nuclear Information System (INIS)

    Simard, A.P.; Lacroix, M.

    2003-01-01

    A study is performed of the thermal behavior of a latent heat cold storage unit operating under frosting conditions. This unit is employed to maintain the temperature inside the refrigerated compartment of a truck below 265 K. The system consists of parallel plates filled with a phase change material (PCM) that absorbs heat from the flow of warm moist air. A mathematical model for the system is first presented and, next, validated with numerical and experimental data. It is then exploited to assess the effects of design parameters and operating conditions on the performance of the system. The recommended thickness and distance separating the PCM plates are found to be 50x10 -3 and 30x10 -3 m, respectively. The results indicate that the performance of the unit is enhanced by turbulent air flow in spite of the increased pressure loss and accentuated frost growth. The unit also performs well even when the surrounding relative humidity is 100%

  6. Barriers to high conversion operations in an ebullated bed unit -- Relationship between sedimentation and operability

    Energy Technology Data Exchange (ETDEWEB)

    Sherwood, D. [Criterion Catalysts Company L.P., Houston, TX (United States)

    2000-07-01

    Ebullated-Bed (EB) catalytic processes are high temperature, high pressure residue hydrocrackers, which transform sour feeds into light, sweet products. EB processes typically involve one or more trains, with one, two, or three EB reactors in series. The key to operating any EB process is to control the 'sediment' which tends to increase with increasing level of conversion. Sediment problems are generally attributed to the catalyst. While this is true in some cases, there are certain problems that occur regardless of the catalyst used, whereas in some situations sediments from the EB process can actually be controlled by the catalyst. This paper describes two typical sedimentation patterns; one in which the sediment increases, and another in which sediment decreases as the EB products move through the recovery section. The benefits of sediment control are illustrated for the latter sedimentation pattern.

  7. Investigation of ageing status assessment and lifetime evaluation based on actual operation conditions of QNPC NPP

    International Nuclear Information System (INIS)

    Huilie, S.; Chun, G.; Hongyun, L.; Yinqiang, C.; Jun, T.; Wenbing, W.

    2009-01-01

    Qinshan NPP has been successfully operated for over 18 years with 30 year's design life. For 2nd PSR preparation and life extension strategies, a comprehensive status assessment and lifetime evaluation project is performed by NPP and SG research organization (CNPO). Assessment is subjects to main degradation mechanism of SG materials, including tube IGA/IGSCC tube pitting, fatigue of pressure boundary. Based on two primary functions of PWR steam generator, a comprehensive lifetime evaluation system and indicators has been established for keeping structural integrity of SG pressure boundary and thermal output performance. A series of specific assessment activities are implemented for defining actual ageing status and estimating safety and function margin of SG, including SG impurities hideout return analysis, fatigue evaluation of feedwater pipes based thermal stratification number simulation, fatigue evaluation of pressure boundary based on actual transition records, structure integrity assessment for lower chamber with defect, tube fouling analysis and trending etc. Assessment results shows, even extending operation to 50 years, SG would still keep sufficient safety and function margin, SG is not the neck of NPP life extension. (author)

  8. Estimation of the optimal operating conditions for a radiation chemical neutralization unit

    International Nuclear Information System (INIS)

    Putilov, A.V.; Kamenetskaya, S.A.; Pshezhetskii, S.Ya.; Kazakov, M.S.; Kudryavtsev, S.L.; Petrukhin, N.V.; Misharin, B.A.; Koneev, V.Z.

    1985-01-01

    An estimate is made of the effect of the hydrodynamic conditions on the efficiency of foam units for the radiation chemical neutralization of impurities, taking into account the penetrating power of accelerated electrons having various energies. Expressions are obtained for calculating the efficiency of such units with sectionized operation of the chamber and taking account of the effect of incomplete mixing of the products of radiolysis through the height of the foam layer

  9. Design and operational parameters of transportable supercritical water oxidation waste destruction unit

    International Nuclear Information System (INIS)

    McFarland, R.D.; Brewer, G.R.; Rofer, C.K.

    1991-12-01

    Supercritical water oxidation (SCWO) is the destruction of hazardous waste by oxidation in the presence of water at temperatures and pressures above its critical point. A 1 gal/h SCWO waste destruction unit (WDU) has been designed, built, and operated at Los Alamos National Laboratory. This unit is transportable and is intended to demonstrate the SCWO technology on wastes at Department of Energy sites. This report describes the design of the WDU and the preliminary testing phase leading to demonstration

  10. Control technique for enhancing the stable operation of distributed generation units within a microgrid

    International Nuclear Information System (INIS)

    Mehrasa, Majid; Pouresmaeil, Edris; Mehrjerdi, Hasan; Jørgensen, Bo Nørregaard; Catalão, João P.S.

    2015-01-01

    Highlights: • A control technique for enhancing the stable operation of distributed generation units is proposed. • Passivity-based control technique is considered to analyze the dynamic and steady-state behaviors. • The compensation of instantaneous variations in the reference current components is considered. • Simulation results confirm the performance of the control scheme within the microgrid. - Abstract: This paper describes a control technique for enhancing the stable operation of distributed generation (DG) units based on renewable energy sources, during islanding and grid-connected modes. The Passivity-based control technique is considered to analyze the dynamic and steady-state behaviors of DG units during integration and power sharing with loads and/or power grid, which is an appropriate tool to analyze and define a stable operating condition for DG units in microgrid technology. The compensation of instantaneous variations in the reference current components of DG units in ac-side, and dc-link voltage variations in dc-side of interfaced converters, are considered properly in the control loop of DG units, which is the main contribution and novelty of this control technique over other control strategies. By using the proposed control technique, DG units can provide the continuous injection of active power from DG sources to the local loads and/or utility grid. Moreover, by setting appropriate reference current components in the control loop of DG units, reactive power and harmonic current components of loads can be supplied during the islanding and grid-connected modes with a fast dynamic response. Simulation results confirm the performance of the control scheme within the microgrid during dynamic and steady-state operating conditions

  11. Turkey Point Plant, Units 3 and 4. Semiannual operating report No. 7, July--December 1975

    International Nuclear Information System (INIS)

    1976-01-01

    Unit 3 generated 1,968,074 MWh(e) net electric power and the generator was on line 2,802.9 hrs. Unit 4 generated 2,560,476 MWh(e) and was on line 3,944.8 hrs. Information is presented concerning operations, power generation, shutdowns, maintenance, changes, tests, experiments, radioactive effluent releases, radiological environmental monitoring, and occupational personnel radiation monitoring

  12. Interim action record of decision remedial alternative selection: TNX area groundwater operable unit

    International Nuclear Information System (INIS)

    Palmer, E.R.

    1994-10-01

    This document presents the selected interim remedial action for the TNX Area Groundwater Operable Unit at the Savannah River Site (SRS), which was developed in accordance with CERCLA of 1980, as amended by the Superfund Amendments and Reauthorization Act (SARA) of 1986, and to the extent practicable, the National Oil and Hazardous Substances Pollution contingency Plan (NCP). This decision is based on the Administrative Record File for this specific CERCLA unit

  13. Reservoir release patterns for hydropower operations at the Aspinall Unit on the Gunnison River, Colorado

    International Nuclear Information System (INIS)

    Yin, S.C.L.; Sedlacek, J.

    1995-05-01

    This report presents the development of reservoir release patterns for the Aspinall Unit, which includes Blue Mesa, Morrow Point, and Crystal Reservoirs on the Gunnison River in Colorado. Release patterns were assessed for two hydropower operational scenarios--seasonally adjusted steady flows and seasonally adjusted high fluctuating flows--and three representative hydrologic years--moderate (1987), dry (1989), and wet (1983). The release patterns for the operational scenarios were developed with the aid of monthly, daily, and hourly reservoir operational models, which simulate the linked operation of the three Aspinall Unit reservoirs. Also presented are reservoir fluctuations and downstream water surface elevations corresponding to the reservoir release patterns. Both of the hydropower operational scenarios evaluated are based on the ecological research flows proposed by the US Fish and Wildlife Service for the Aspinall Unit. The first operational scenario allows only seasonally adjusted steady flows (no hourly fluctuations at any dam within one day), whereas the second scenario permits high fluctuating flows from Blue Mesa and Morrow Point Reservoirs during certain times of the year. Crystal Reservoir would release a steady flow within each day under both operational scenarios

  14. Prospects and requirements for an operational modelling unit in flood crisis situations

    Directory of Open Access Journals (Sweden)

    Anders Katharina

    2016-01-01

    Full Text Available Dike failure events pose severe flood crisis situations on areas in the hinterland of dikes. In recent decades the importance of being prepared for dike breaches has been increasingly recognized. However, the pre-assessment of inundation resulting from dike breaches is possible only based on scenarios, which might not reflect the situation of a real event. This paper presents a setup and workflow that allows to model dike breachinduced inundation operationally, i.e. when an event is imminent or occurring. A comprehensive system setup of an operational modelling unit has been developed and implemented in the frame of a federal project in Saxony-Anhalt, Germany. The modelling unit setup comprises a powerful methodology of flood modelling and elaborated operational guidelines for crisis situations. Nevertheless, it is of fundamental importance that the modelling unit is instated prior to flood events as a permanent system. Moreover the unit needs to be fully integrated in flood crisis management. If these crucial requirements are met, a modelling unit is capable of fundamentally supporting flood management with operational prognoses of adequate quality even in the limited timeframe of crisis situations.

  15. Biblis 1,300 MW unit B in operation for thirty years

    International Nuclear Information System (INIS)

    Lauer, H.

    2006-01-01

    Over the past thirty years, unit B of the Biblis nuclear power station has contributed towards safe, reliable and non-polluting electricity generation. Unit B was the first 1,300 MW unit in the world confirming the good experience accumulated in the construction and operation of plants this size. It laid the foundation for the advanced development of nuclear power plants up to the convoy line. The good availability this plant has achieved in its operating cycles proves the mature state of technology and the high level of qualification and motivation of the power plant staff and the personnel of external firms contracted to work for Biblis. Biblis B has served as a reference plant in German nuclear safety research, demonstrating that units this size can be operated safely. Unit B is also living proof of the possibility to raise nuclear power plants built in the seventies to the current state of the art by implementing the appropriate backfitting and modernization measures. Today, Biblis B is operated at a safety level clearly higher than that to be achieved for new plants internationally. This is also evident from comparison with the guiding values for the safety of new facilities as published by the International Atomic Energy Agency (IAEA). (orig.)

  16. Nutritional status, nutrition practices and post-operative complications in patients with gastrointestinal cancer.

    Science.gov (United States)

    Garth, A K; Newsome, C M; Simmance, N; Crowe, T C

    2010-08-01

    Malnutrition and its associated complications are a considerable issue for surgical patients with upper gastrointestinal and colorectal cancer. The present study aimed to determine whether specific perioperative nutritional practices and protocols are associated with improved patient outcomes in this group. Patients admitted for elective upper gastrointestinal or colorectal cancer surgery (n = 95) over a 19-month period underwent a medical history audit assessing weight changes, nutritional intake, biochemistry, post-operative complications and length of stay. A subset of patients (n = 25) underwent nutritional assessment by subjective global assessment prior to surgery in addition to assessment of post-operative medical outcomes, nutritional intake and timing of dietetic intervention. Mean (SD) length of stay for patients was 14.0 (12.2) days, with complication rates at 35%. Length of stay was significantly longer in patients who experienced significant preoperative weight loss compared to those who did not [17.0 (15.8) days versus 10.0 (6.8) days, respectively; P nutritional assessment, 32% were classified as mild-moderately malnourished and 16% severely malnourished. Malnourished patients were hospitalised twice as long as well-nourished patients [15.8 (12.8) days versus 7.6 (3.5) days; P nutrition post surgery was a factor in post-operative outcomes, with a positive correlation with length of stay (r = 0.493; P cancer. Poor nutritional status coupled with delayed and inadequate post-operative nutrition practices are associated with worse clinical outcomes.

  17. Qualitative risk assessment for the 100-KR-4 groundwater operable unit

    Energy Technology Data Exchange (ETDEWEB)

    Biggerstaff, R.L.

    1994-06-30

    This report provides the qualitative risk assessment (QRA) for the 100-KR-4 groundwater operable unit at the US Department of Energy`s (DOE) Hanford Site in southeastern Washington State. The extent of the groundwater beneath the 100 K Area is defined in the Remedial Investigation/Feasibility Study Work Plan for the 100-KR-4 Operable Unit (DOE-RL 1992a). The QRA is an evaluation or risk using a limited amount of data and a predefined set of human and environmental exposure scenarios and is not intended to replace or be a substitute for a baseline risk assessment.

  18. Operable Unit 3-13, Group 3, Other Surface Soils (Phase II) Field Sampling Plan

    Energy Technology Data Exchange (ETDEWEB)

    G. L. Schwendiman

    2006-07-27

    This Field Sampling Plan describes the Operable Unit 3-13, Group 3, Other Surface Soils, Phase II remediation field sampling activities to be performed at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Laboratory Site. Sampling activities described in this plan support characterization sampling of new sites, real-time soil spectroscopy during excavation, and confirmation sampling that verifies that the remedial action objectives and remediation goals presented in the Final Record of Decision for Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13 have been met.

  19. Engineering evaluation/conceptual plan for the 200-UP-1 groundwater operable unit interim remedial measure

    International Nuclear Information System (INIS)

    Myers, D.A.; Swanson, L.C.; Weeks, R.S.; Giacinto, J.; Gustafson, F.W.; Ford, B.H.; Wittreich, C.; Parnell, S.; Green, J.

    1995-04-01

    This report presents an engineering evaluation and conceptual plan for an interim remedial measure (ERM) to address a uranium and technetium-99 groundwater plume and an associated nitrate contamination plume in the 200-UP-1 Groundwater Operable Unit located in the 200 West Area of the Hanford Site. This report provides information regarding the need and potentially achievable objectives and goals for an IRM and evaluates alternatives to contain elevated concentrations of uranium, technetium-99, nitrate, and carbon tetrachloride and to obtain information necessary to develop final remedial actions for the operable unit

  20. Qualitative risk assessment for the 100-KR-4 groundwater operable unit

    International Nuclear Information System (INIS)

    Biggerstaff, R.L.

    1994-01-01

    This report provides the qualitative risk assessment (QRA) for the 100-KR-4 groundwater operable unit at the US Department of Energy's (DOE) Hanford Site in southeastern Washington State. The extent of the groundwater beneath the 100 K Area is defined in the Remedial Investigation/Feasibility Study Work Plan for the 100-KR-4 Operable Unit (DOE-RL 1992a). The QRA is an evaluation or risk using a limited amount of data and a predefined set of human and environmental exposure scenarios and is not intended to replace or be a substitute for a baseline risk assessment

  1. RCRA facility investigation report for the 200-PO-1 operable unit. Revision 1

    International Nuclear Information System (INIS)

    1997-05-01

    This Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) report is prepared in support of the RFI/corrective measures study process for the 200-PO-1 Groundwater Operable Unit in the 200 East Area of the Hanford Site. This report summarizes existing information on this operable unit presented in the 200 East and PUREX Aggregate Area Management Study Reports, contaminant specific studies, available modeling data, and groundwater monitoring data summary reports. Existing contaminant data are screened against current regulatory limits to determine contaminants of potential concern (COPC). Each identified COPC is evaluated using well-specific and plume trend analyses

  2. Survey Method for Radiological Surveys of 300-FF-1 Operable Unit Soils and Material

    International Nuclear Information System (INIS)

    Brehm, D.M.

    1998-06-01

    This technical basis is to be used to survey soils at the 300-FF-1 Operable Unit during remediation of the site. Its purpose is to provide a basis for the survey methods to be employed by radiological control technician (RCTs) to guide the excavation effort in accordance with the 300-FF-1 waste site Record of Decision (ROD). The ROD for the 300-FF-1 Operable Unit requires selective excavation, removal, and disposal of contaminated soil above 350 pCi/g total uranium activity. Soil above this level will be disposed of as radioactive waste. The remaining soil will remain onsite

  3. Modeling the status, trends, and impacts of wild bee abundance in the United States.

    Science.gov (United States)

    Koh, Insu; Lonsdorf, Eric V; Williams, Neal M; Brittain, Claire; Isaacs, Rufus; Gibbs, Jason; Ricketts, Taylor H

    2016-01-05

    Wild bees are highly valuable pollinators. Along with managed honey bees, they provide a critical ecosystem service by ensuring stable pollination to agriculture and wild plant communities. Increasing concern about the welfare of both wild and managed pollinators, however, has prompted recent calls for national evaluation and action. Here, for the first time to our knowledge, we assess the status and trends of wild bees and their potential impacts on pollination services across the coterminous United States. We use a spatial habitat model, national land-cover data, and carefully quantified expert knowledge to estimate wild bee abundance and associated uncertainty. Between 2008 and 2013, modeled bee abundance declined across 23% of US land area. This decline was generally associated with conversion of natural habitats to row crops. We identify 139 counties where low bee abundances correspond to large areas of pollinator-dependent crops. These areas of mismatch between supply (wild bee abundance) and demand (cultivated area) for pollination comprise 39% of the pollinator-dependent crop area in the United States. Further, we find that the crops most highly dependent on pollinators tend to experience more severe mismatches between declining supply and increasing demand. These trends, should they continue, may increase costs for US farmers and may even destabilize crop production over time. National assessments such as this can help focus both scientific and political efforts to understand and sustain wild bees. As new information becomes available, repeated assessments can update findings, revise priorities, and track progress toward sustainable management of our nation's pollinators.

  4. Phase 1 remedial investigation report for 200-BP-1 operable unit. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    The US Department of Energy (DOE) Hanford Site, in Washington State is organized into numerically designated operational areas including the 100, 200, 300, 400, 600, and 1100 Areas. The US Environmental Protection Agency (EPA), in November 1989 included the 200 Areas of the Hanford Site on the National Priority List (NPL) under the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA). Inclusion on the NPL initiated the remedial investigation (RD process for the 200-BP-1 operable unit. These efforts are being addressed through the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1989) which was negotiated and approved by the DOE, the EPA, and the State of Washington Department of Ecology (Ecology) in May 1989. This agreement, known as the Tri-Party Agreement, governs all CERCLA efforts at Hanford. In March of 1990, the Department of Energy, Richland Operations (DOE-RL) issued a Remedial Investigation/Feasibility Study (RI/FS) work plan (DOE-RL 1990a) for the 200-BP-1 operable unit. The work plan initiated the first phase of site characterization activities associated with the 200-BP-1 operable unit. The purpose of the 200-BP-1 operable unit RI is to gather and develop the necessary information to adequately understand the risks to human health and the environment posed by the site and to support the development and analysis of remedial alternatives during the FS. The RI analysis will, in turn, be used by Tri-Party Agreement signatories to make a risk-management-based selection of remedies for the releases of hazardous substances that have occurred from the 200-BP-1 operable unit.

  5. Phase 1 remedial investigation report for 200-BP-1 operable unit

    International Nuclear Information System (INIS)

    1993-09-01

    The US Department of Energy (DOE) Hanford Site, in Washington State is organized into numerically designated operational areas including the 100, 200, 300, 400, 600, and 1100 Areas. The US Environmental Protection Agency (EPA), in November 1989 included the 200 Areas of the Hanford Site on the National Priority List (NPL) under the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA). Inclusion on the NPL initiated the remedial investigation (RD process for the 200-BP-1 operable unit. These efforts are being addressed through the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1989) which was negotiated and approved by the DOE, the EPA, and the State of Washington Department of Ecology (Ecology) in May 1989. This agreement, known as the Tri-Party Agreement, governs all CERCLA efforts at Hanford. In March of 1990, the Department of Energy, Richland Operations (DOE-RL) issued a Remedial Investigation/Feasibility Study (RI/FS) work plan (DOE-RL 1990a) for the 200-BP-1 operable unit. The work plan initiated the first phase of site characterization activities associated with the 200-BP-1 operable unit. The purpose of the 200-BP-1 operable unit RI is to gather and develop the necessary information to adequately understand the risks to human health and the environment posed by the site and to support the development and analysis of remedial alternatives during the FS. The RI analysis will, in turn, be used by Tri-Party Agreement signatories to make a risk-management-based selection of remedies for the releases of hazardous substances that have occurred from the 200-BP-1 operable unit

  6. Structural characterization and condition for measurement statistics preservation of a unital quantum operation

    International Nuclear Information System (INIS)

    Lee, Kai-Yan; Fung, Chi-Hang Fred; Chau, H F

    2013-01-01

    We investigate the necessary and sufficient condition for a convex cone of positive semidefinite operators to be fixed by a unital quantum operation ϕ acting on finite-dimensional quantum states. By reducing this problem to the problem of simultaneous diagonalization of the Kraus operators associated with ϕ, we can completely characterize the kinds of quantum states that are fixed by ϕ. Our work has several applications. It gives a simple proof of the structural characterization of a unital quantum operation that acts on finite-dimensional quantum states—a result not explicitly mentioned in earlier studies. It also provides a necessary and sufficient condition for determining what kind of measurement statistics is preserved by a unital quantum operation. Finally, our result clarifies and extends the work of Størmer by giving a proof of a reduction theorem on the unassisted and entanglement-assisted classical capacities, coherent information, and minimal output Renyi entropy of a unital channel acting on a finite-dimensional quantum state. (paper)

  7. Peach Bottom Atomic Power Station, Units 2 and 3. Annual operating report: January--December 1976

    International Nuclear Information System (INIS)

    1977-01-01

    Unit 2 experienced 11 forced outages, 5 power reductions, and one major refueling outage which lasted about 3 months during which time the feedwater spargers were replaced. Net electrical power generated was 5,569,633 MWH with the generator on line 5,998 hrs. Unit 3 experienced 17 forced outages, 11 power reductions and 2 major outages. The first refueling outage began 12/24/77. Net electrical power generated was 6,049,644 MWH with the unit on line 6,829 hrs. Information is presented concerning operations, personnel exposures, radioactive releases, maintenance, and irradiated fuel examination

  8. NUMATH: a nuclear-material-holdup estimator for unit operations and chemical processes

    International Nuclear Information System (INIS)

    Krichinsky, A.M.

    1981-01-01

    A computer program, NUMATH (Nuclear Material Holdup Estimator), has been developed to permit inventory estimation in vessels involved in unit operations and chemical processes. This program has been implemented in an operating nuclear fuel processing plant. NUMATH's purpose is to provide steady-state composition estimates for material residing in process vessels until representative samples can be obtained and chemical analyses can be performed. Since these compositions are used for inventory estimation, the results are determined for and cataloged in container-oriented files. The estimated compositions represent material collected in applicable vessels-including consideration for material previously acknowledged in these vessels. The program utilizes process measurements and simple material balance models to estimate material holdups and distribution within unit operations. During simulated run testing, NUMATH-estimated inventories typically produced material balances within 7% of the associated measured material balances for uranium and within 16% of the associated, measured material balance for thorium during steady-state process operation

  9. Categorization of safety related motor operated valve safety significance for Ulchin Unit 3

    International Nuclear Information System (INIS)

    Kang, D. I.; Kim, K. Y.

    2002-03-01

    We performed a categorization of safety related Motor Operated Valve (MOV) safety significance for Ulchin Unit 3. The safety evaluation of MOV of domestic nuclear power plants affects the generic data used for the quantification of MOV common cause failure ( CCF) events in Ulchin Units 3 PSA. Therefore, in this study, we re-estimated the MGL(Multiple Greek Letter) parameter used for the evaluation of MOV CCF probabilities in Ulchin Units 3 Probabilistic Safety Assessment (PSA) and performed a classification of the MOV safety significance. The re-estimation results of the MGL parameter show that its value is decreased by 30% compared with the current value in Ulchin Unit 3 PSA. The categorization results of MOV safety significance using the changed value of MGL parameter shows that the number of HSSCs(High Safety Significant Components) is decreased by 54.5% compared with those using the current value of it in Ulchin Units 3 PSA

  10. SAE for the prediction of road traffic status from taxicab operating data and bus smart card data

    Science.gov (United States)

    Zhengfeng, Huang; Pengjun, Zheng; Wenjun, Xu; Gang, Ren

    Road traffic status is significant for trip decision and traffic management, and thus should be predicted accurately. A contribution is that we consider multi-modal data for traffic status prediction than only using single source data. With the substantial data from Ningbo Passenger Transport Management Sector (NPTMS), we wished to determine whether it was possible to develop Stacked Autoencoders (SAEs) for accurately predicting road traffic status from taxicab operating data and bus smart card data. We show that SAE performed better than linear regression model and Back Propagation (BP) neural network for determining the relationship between road traffic status and those factors. In a 26-month data experiment using SAE, we show that it is possible to develop highly accurate predictions (91% test accuracy) of road traffic status from daily taxicab operating data and bus smart card data.

  11. The trip status and the reduction countermeasure in Kori nuclear power plant unit 1 and 2

    International Nuclear Information System (INIS)

    Kim, Jung-Soo

    1991-01-01

    Nuclear power account for 36% of Korea's total electric capacity and provided over 50% of the net electric power supply by June 1991. These plants supply US with the cheapest and most stable electric supply available. However each units capacity is very large and a plant trip due to failure of a component or a human error has a great influence on the nations electric power supply and drastically decreases the reserve margin. This report will analyze the trip causes and measure the trip frequency from the first commercial operation of Kori unit 1 and 2 to the end of June 1991, reflect to the plant operation, management and facility modification, etc. This will minimize the number of trips or urgent power reductions and thus contribute to an increase in plant capacity factor and safety, and stabilize the electric power demand and supply. The safety and the economy of nuclear power plant have to be secured and raised respectably by increasing the capacity factor. Since the prevention of trips plays an important role in the plant safety and economy, we have to do our best to prevent the unexpected trip

  12. Review of the status of geothermal development and operation in Indonesia 1985 to 1990

    International Nuclear Information System (INIS)

    Radja, V.T.

    1990-01-01

    This paper reports that the electric power sector in Indonesia will be expanded by an additional generating capacity of about 1,225 MW at the end of the fifth 5-year development plan (1989/1990 to 1993/1994) from the existing 8,529 MW. At present a 140 MW geothermal condensing plant (one unit of 230 MW and 2 units of 55 MW, all in Kamojang) and two noncondensing nonobloks (2 MW in Dieng and 25 kW in Kamojang) have been operating successfully since 1979. Based on the fifth 5-year development plan the government of Indonesia has decided to install an additional 235 MW on the island of Java and 15 MW on North Sulawesi, for a total installed capacity of 377.25 MW

  13. Denver Radium Site -- Operable Unit I closeout report for the US Environmental Protection Agency

    International Nuclear Information System (INIS)

    1992-08-01

    The Denver Radium Site consists of properties in the Denver, Colorado, area having radioactive contamination left from radium processing in the early 1900s. The properties are divided into 11 gaps or operable units to facilitate remedial action of the Site. Operable Unit I is an 8-acre block bounded by Quivas Street to the east, Shoshone Street to the west, West 12th Avenue to the south, and West 13th Avenue to the north. The primary focus of interest concerning investigations of radiological contamination was a radium, vanadium, and uranium processing facility at 1201 Quivas Street owned by the Pittsburgh Radium Company (PRC) from 1925 until 1926. The Radium Ores Company, which was associated with PRC, operated the facility until 1927. A Remedial investigation (RI) of Operable Unit I was prepared by Jacobs Engineering Group and CH 2 M Hill on behalf of EPA in April 1986. The draft Feasibility Study (FS), prepared by Jacobs Engineering Group and CH 2 M Hill, was issued in July 1987 (the final FS is the Community Relations Responsiveness Summary with an errata to the draft, issued September 1987). The RI focused on radium uranium processing residues discarded in the early 1900s. These residues contained uranium, radium, and thorium. EPA s Community Relations Plan involved the community in the decision-making process relating to the remedy to be implemented at Operable Unit X, and promoted communications among interested parties throughout the course of the project. The remedial action alternative preferred by EPA for Operable Unit I was Off-Site Permanent Disposal. Because a permanent disposal facility was not available at the time the Record of Decision was issued in September 1987, EPA selected the On-Site Temporary Containment (capping) with the Off-Site Permanent Disposal alternative

  14. Effects of Combat Deployment on Anthropometrics and Physiological Status of U.S. Army Special Operations Forces Soldiers.

    Science.gov (United States)

    Farina, Emily K; Taylor, Jonathan C; Means, Gary E; Williams, Kelly W; Murphy, Nancy E; Margolis, Lee M; Pasiakos, Stefan M; Lieberman, Harris R; McClung, James P

    2017-03-01

    U.S. Army Special Operations Forces (SOF) soldiers deploy frequently and conduct military operations through special warfare and surgical strike capabilities. Tasks required to execute these capabilities may induce physical and mental stress and have the potential to degrade soldier physiological status. No investigations have longitudinally characterized whether combat deployment alters anthropometrics or biochemical markers of physiological status in a SOF population of frequent deployers. Effects of modern combat deployment on longitudinal changes in anthropometrics and physiological status of elite U.S. Army SOF soldiers (n = 50) were assessed. Changes in measures of body composition, grip strength, physiological status, and health behaviors from baseline to postdeployment were determined with paired t test and McNemar's statistic. Baseline measures were obtained between 4 and 8 weeks before deployment. Deployment length was a uniform duration of time between 3 and 6 months (all soldiers completed the same length of deployment). Post hoc analyses determined change in body mass within quartiles of baseline body mass with paired t test and associations between change in sex hormone-binding globulin (SHBG) and change in body mass with correlation coefficient. The study was approved by the Human Use Review Committee at the U.S. Army Research Institute of Environmental Medicine, Natick, Massachusetts. In response to deployment, increases in lean mass (77.1 ± 7.6 to 77.8 ± 7.5 kg), maximum grip strength (57.9 ± 7.2 to 61.6 ± 8.8 kg), and conduct of aerobic (156 ± 106 to 250 ± 182 minutes/week) and strength training (190 ± 101 to 336 ± 251 minutes/week) exercise were observed (p < 0.05). Increases in serum SHBG (35.42 ± 10.68 to 38.77 ± 12.26 nmol/L) and decreases in serum cortisol (443.2 ± 79.3 to 381.9 ± 111.6 nmol/L) were also observed (p < 0.05). Body mass changes were dependent on baseline body mass. Soldiers in the lowest quartile of baseline body

  15. 40 CFR 60.2989 - Does this subpart directly affect incineration unit owners and operators in my State?

    Science.gov (United States)

    2010-07-01

    ... incineration unit owners and operators in my State? 60.2989 Section 60.2989 Protection of Environment... SOURCES Emission Guidelines and Compliance Times for Other Solid Waste Incineration Units That Commenced... incineration unit owners and operators in my State? (a) No, this subpart does not directly affect incineration...

  16. 40 CFR 62.15145 - What are the operating practice requirements for my municipal waste combustion unit?

    Science.gov (United States)

    2010-07-01

    ... requirements for my municipal waste combustion unit? 62.15145 Section 62.15145 Protection of Environment... Combustion Units Constructed on or Before August 30, 1999 Good Combustion Practices: Operating Requirements § 62.15145 What are the operating practice requirements for my municipal waste combustion unit? (a) You...

  17. RCRA facility investigation/corrective measures study work plan for the 100-HR-1 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US. Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-1 source operable unit. Source operable units include facilities and unplanned release sites that are potential sources of contamination. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Separate work plans have been initiated for the 100-HR-3 groundwater operable unit (DOE-RL 1992a) and the 100-DR-1 (DOE-RL 1992b) source operable units

  18. Status report on the operation of the cyclotron and on the programs of its practical applications

    International Nuclear Information System (INIS)

    Tarkanyi, F.; Ander, I.; Ando, L.; Ditroi, F.; Fenyvesi, A.; Kiraly, B.; Kormany, Z.; Kovacs, P.; Kovacs, Z.; Mahunka, I.

    2007-01-01

    The main task of the Cyclotron Department is to operate the ATOMKI MGC-20E cyclotron, to support the research in different scientific fields and to use the accelerator in practice related applications. The Cyclotron Laboratory has been installed in a research institute so research is the most important task. Considering that some results of the basic research can be used in different routine applications, the second important task is to help developing systems for this reason. The capacity of the accelerator usually allows making routine applications to ensure the financial background for the service and for the development of the cyclotron. The cyclotron is applied directly for basic nuclear physics research and it indirectly helps the research in other fields via interdisciplinary studies. It is used in broad scale for different practical applications which have direct results in basic sciences in many cases therefore the classification sometimes is not simple. The irradiations at the cyclotron are dedicated to basic research in the field of nuclear structure and nuclear reaction studies and from other side to the so-called practical applications. The cyclotron has been in operation in ATOMKI since 1985. Since then the cyclotron has been reliably running with very short undesired breakdowns and it has been used for a wide range of research and application programs. This overview gives a short summary of the status of cyclotron operation and the practical applications and gives some indications on the future plans. (author)

  19. Hydrologic resources management program and underground test area operable unit fy 1997

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D. F., LLNL

    1998-05-01

    This report present the results of FY 1997 technical studies conducted by the Lawrence Livermore National Laboratory (LLNL) as part of the Hydrology and Radionuclide Migration Program (HRMP) and Underground Test Area Operable Unit (UGTA). The HRMP is sponsored by the US Department of Energy to assess the environmental (radiochemical and hydrologic) consequences of underground nuclear weapons testing at the Nevada Test Site.

  20. Use of the LITEE Lorn Manufacturing Case Study in a Senior Chemical Engineering Unit Operations Laboratory

    Science.gov (United States)

    Abraham, Nithin Susan; Abulencia, James Patrick

    2011-01-01

    This study focuses on the effectiveness of incorporating the Laboratory for Innovative Technology and Engineering Education (LITEE) Lorn Manufacturing case into a senior level chemical engineering unit operations course at Manhattan College. The purpose of using the case study is to demonstrate the relevance of ethics to chemical engineering…

  1. Ambiguity in Units and the Referents: Two Cases in Rational Number Operations

    Science.gov (United States)

    Rathouz, Margaret

    2010-01-01

    I explore the impact of ambiguous referral to the unit on understanding of decimal and fraction operations during episodes in two different mathematics courses for pre-service teachers (PSTs). In one classroom, the instructor introduces a rectangular area diagram to help the PSTs visualize decimal multiplication. A transcript from this classroom…

  2. Qualitative risk assessment for the 100-NR-2 Operable Unit. Revision 1

    International Nuclear Information System (INIS)

    1995-03-01

    This qualitative risk assessment provides information about the 100- NR-2 Groundwater Operable Unit of the Hanford reservation. Topics discussed in this report are: data evaluation; human health risk assessment overview; ecological evaluations; summary of uncertainty; results of both the ecological and human health evaluations; toxicity assessment; risk characterization; and a summary of contaminants of potential concern

  3. Limited field investigation report for the 100-KR-4 Operable Unit

    International Nuclear Information System (INIS)

    1994-07-01

    This limited field investigation (LFI) was conducted to optimize the use of interim remedial measures (IRM) for expediting clean up while maintaining a technically sound and cost-effective program. The 100-KR-4 Operable Unit is one of four operable units associated with the 100 K Area. Operable units KR-1, KR-2 and KR-3 address contaminant sources while 100-KR-4 addresses contamination present in the underlying groundwater. The IRM decision process for groundwater operable units is based on three aspects: (1) Is the concentration greater than Hanford background? (2) Does the concentration present a medium or high human-health risk? (3) Does the concentration exceed an ecologically based applicable, relevant and appropriate requirements (ARAR) or present an environmental hazard quotient > I? The primary methods of investigation used during this LFI were the installation of monitoring wells and sampling of groundwater. The samples collected from the groundwater and soils were submitted for laboratory analysis. Boreholes were surveyed for radiological contamination using downhole geophysical techniques to further delineate the location and degree of contamination. All soil samples were screened to ascertain the presence of volatile organic compounds and radionuclides. Analytical data were subjected to validation; all first round and a minimum of 10% of subsequent round data were validated

  4. Donald C. Cook Nuclear Power Plant, Unit 1. Annual operating report for 1976

    International Nuclear Information System (INIS)

    1977-01-01

    The unit was paralleled to the grid 83.1 percent of the time and 7,073,200 MWH gross was generated. There were six scheduled outages and 14 forced outages/load reductions. Information is presented concerning operations, shutdowns, power reductions, inservice maintenance, personnel radiation exposures, fuel history, and facility changes

  5. Storm water control plan for the Lower East Fork Poplar Creek Operable Unit, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1996-04-01

    This document provides the Environmental Restoration Program with information about the erosion and sediment control, storm water management, maintenance, and reporting and record keeping practices to be employed during Phase II of the remediation project for the Lower East Fork Poplar Creek (LEFPC) Operable Unit

  6. A Moveable Feast--A Progressive Approach to the Unit Operations Laboratory

    Science.gov (United States)

    Conner, Wm. Curtis, Jr.; Hammond, Karl D.; Laurence, Robert L.

    2011-01-01

    The authors describe an alternative format for the senior laboratory in which students are allowed--indeed, expected--to communicate with previous groups and build on their results. The effect is a unit operations laboratory in which students are empowered to propose the experiments they wish to do and in which the cumulative experience of the…

  7. Interim Action Proposed Plan for the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit; FINAL

    International Nuclear Information System (INIS)

    Bradley, J.

    2002-01-01

    The purpose of this Interim Action Proposed Plan (IAPP) is to describe the preferred interim remedial action for addressing the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit and to provide an opportunity for public input into the remedial action selection process

  8. Limited field investigation report for the 100-DR-1 Operable Unit

    International Nuclear Information System (INIS)

    1994-06-01

    This limited field investigation (LFI) report summarizes the data collection and analysis activities conducted during the 100-DR-1 Source Operable Unite LFI and the associated qualitative risk assessment (QRA), and makes recommendations on the continued candidacy of high-priority sites for interim remedial measures (IRM). The results and recommendations presented in this report are generally independent of future land use scenarios. The 100-DR-1 Operable Unit is one of four operable units associated with the 100 D/DR Area at the Hanford Site. The 100-DR-1 Operable Unit encompasses approximately 1.5 km 2 (0.59 mi 2 ) and is located immediately adjacent to the Columbia River shoreline. In general, it contains waste facilities associated with the original plant facilities constructed to support D Reactor facilities, as well as cooling water retention basin systems for both D and DR Reactors. The 100-DR-1 LFI began the investigative phase of the remedial investigation for a select number of high-priority sites. The LFI was performed to provide additional data needed to support selection, design and implementation of IRM, if needed. The LFI included data compilation, nonintrusive investigations, intrusive investigations, summarization of 100 Area aggregate studies, and data evaluation

  9. NSSS design and cycle 1 operating history data for Arkansas Nuclear One, Unit-2. Final report

    International Nuclear Information System (INIS)

    Gagne, P.A.

    1981-03-01

    This report contains design and cycle 1 operating data for the Arkansas Nuclear One, Unit-2 nuclear steam supply system. The design data include descriptions of the reactor core, reactor coolant system, and control systems which are a part of the nuclear steam supply system. Operating history data are provided for the period of December 1978 through January 1980. The most important operating history data provided include reactor power, cumulative fuel burnup, control rod position, primary coolant temperature, and a series of power distribution state points

  10. Qualitative risk assessment for the 100-HR-3 groundwater operable unit

    Energy Technology Data Exchange (ETDEWEB)

    Vukelich, S.E. [Golder Associates, Inc., Richland, WA (United States)

    1994-09-22

    This report provides the qualitative risk assessment for the 100-HR-3 operable unit on the Hanford Reservation. 100-HR-3 is a ground water unit. The purpose of the QRA at the 100-HR-3 operable unit is to focus on a predefined set of human and environmental exposure scenarios in order to provides sufficient information that will assist the Tri-Party signatories (Washington State Department of Ecology, EPA and US DOE) in making defensible decisions on the necessity of Interim Remedial Measures. Frequent- and occasional-use exposure scenarios are evaluated in the human health risk assessment to provide bounding estimates of risk. The ecological risk assessment consists of an evaluation of the risks to riparian and aquatic receptors which live in or near the Columbia River.

  11. Remedial investigation for the 200-BP-1 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    Buckmaster, M.A.

    1991-01-01

    The Hanford Site, Richland, Washington, contains over 1500 identified waste sites that will be characterized and remediated over the next 30 years. In support of the ''Hanford Federal Facility Agreement and Consent Order,'' the US Department of Energy has initiated a remedial investigation/feasibility study (RI/FS) at the 200-BP-1 operable unit. The 200-BP-1 RI is the first Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) investigation on the Hanford Site that involves drilling into highly radioactive and chemically contaminated soils. The initial phase of the site characterization is oriented toward determining the nature and extent of any contamination present in the vicinity of the 200-BP-1 operable unit. The major focus of the Phase I RI is the drilling and sampling of 10 inactive waste disposal units which received low level radioactive liquid waste

  12. Qualitative risk assessment for the 100-HR-3 groundwater operable unit

    International Nuclear Information System (INIS)

    Vukelich, S.E.

    1994-01-01

    This report provides the qualitative risk assessment for the 100-HR-3 operable unit on the Hanford Reservation. 100-HR-3 is a ground water unit. The purpose of the QRA at the 100-HR-3 operable unit is to focus on a predefined set of human and environmental exposure scenarios in order to provides sufficient information that will assist the Tri-Party signatories (Washington State Department of Ecology, EPA and US DOE) in making defensible decisions on the necessity of Interim Remedial Measures. Frequent- and occasional-use exposure scenarios are evaluated in the human health risk assessment to provide bounding estimates of risk. The ecological risk assessment consists of an evaluation of the risks to riparian and aquatic receptors which live in or near the Columbia River

  13. Status and conservation of interior Redband Trout in the western United States

    Science.gov (United States)

    Muhlfeld, Clint C.; Albeke, Shannon E.; Gunckel, Stephanie L; Writer, Benjamin J; Shepard, Bradley B.; May, Bruce E

    2015-01-01

    In this article we describe the current status and conservation of interior (potamodromous) Redband Trout Oncorhynchus mykiss sspp. throughout its range in the western United States using extant data and expert opinion provided by fish managers. Redband Trout historically occupied 60,295 km of stream habitat and 152 natural lakes. Currently, Redband Trout occupy 25,417 km of stream habitat (42% of their historical range) and 124 lakes or reservoirs. Nonhybridized populations are assumed to occupy 11,695 km (46%) of currently occupied streams; however, fish from only 4,473 km (18%) have been genetically tested. Approximately 47% of the streams occupied by Redband Trout occur on private land, 45% on government lands, and 8% in protected areas. A total of 210 Redband Trout populations, occupying 15,252 km of stream habitat (60% of the current distribution) and 95,158 ha of lake habitat (52%), are being managed as “conservation populations.” Most conservation populations have been designated as weakly to strongly connected metapopulations (125; 60%) and occupy much more stream length (14,112 km; 93%) than isolated conservation populations (1,141 km; 7%). The primary threats to Redband Trout include invasive species, habitat degradation and fragmentation, and climate change. Although the historical distribution of interior Redband Trout has declined dramatically, we conclude that the species is not currently at imminent risk of extinction because it is still widely distributed with many populations isolated by physical barriers and active conservation efforts are occurring for many populations. However, the hybridization status of many populations has not been well quantified, and introgression may be more prevalent than documented here. We recommend (1) collecting additional genetic data and estimating distribution and abundance by means of a more rigorous spatial sampling design to reduce uncertainties, (2) collecting additional information to assess and

  14. Monitoring System for Evaluation of Operator Functional Status on Sea Ships

    Directory of Open Access Journals (Sweden)

    Giedrius Varoneckas

    2016-07-01

    Full Text Available This paper introduces the basic concept of a new developed web-based databank for an assessment of seafarers’ functional status during the sea missions. The Web system is based on client-server architecture and the international open source technologies including Apache web server, PHP scripts and MySQL database. The paper focuses on the aspects and first results of the initial practical realization of the web-based databank. The main operational advantage of the developed system is the capability to on-line handle up to a dozen users at the same time. The system includes administrative data and questionnaires. Electronic data entry saves the time and material resources.

  15. Cryosat: ESA's ice Explorer Mission. 7 years in operations: status and future outlook

    Science.gov (United States)

    Parrinello, Tommaso

    2017-04-01

    CryoSat-2 was launched on the 8th April 2010 and it is the first European ice mission dedicated to monitoring precise changes in the thickness of polar ice sheets and floating sea ice over a 3-year period. CryoSat-2 carries an innovative radar altimeter called the Synthetic Aperture Interferometric Altimeter (SIRAL) with two antennas and with extended capabilities to meet the measurement requirements for ice-sheets elevation and sea-ice freeboard. Initial results have shown that data is of high quality thanks to an altimeter that is behaving exceptional well within its design specifications. Since its launch, CryoSat data has been used by different scientific communities on a number of Earth Science topics also beyond its prime mission objectives, cryosphere. Scope of this paper is to describe the current mission status and provide programmatic highlights and information on the next development of the mission in its extended period of operations (2017-2019).

  16. Level 1 shutdown and low power operation of Mochovce NPP, Unit 1, Slovakia

    International Nuclear Information System (INIS)

    Halada, P.; Cillik, I.; Stojka, T.; Kuzma, M.; Prochaska, J.; Vrtik, L.

    2004-01-01

    The paper presents general approach, used methods and form of documentation of the results that have been applied within the shutdown and low power PSA (SPSA) study for Mochovce NPP, Unit 1, Slovakia. The SPSA project was realized by VUJE Trnava Inc., Slovakia in 2001-2002 years. The Level 1 SPSA study for Mochovce NPP Unit 1 covers internal events as well as internal (fires, floods and heavy load drop) and external (aircraft crash, extreme meteorological conditions, seismic event and influence of surrounding industry) hazards. Mochovce NPP consists of two operating units equipped with VVER 440/V213 reactors safety upgraded before construction finishing and operation start. 87 safety measures based on VVER 440 operational experience and international mission insights were implemented to enhance its operational and nuclear safety. The SPSA relates to full power PSA (FPSA) as a continuation of the effort to create a harmonized level 1 PSA model for all operational modes of the plant with the goal to use it for further purposes as follows: Real Time Risk Monitor, Maintenance Optimization, Technical Specifications Optimization, Living PSA. (author)

  17. Pilot-scale treatability test plan for the 200-UP-1 groundwater Operable Unit

    International Nuclear Information System (INIS)

    Wittreich, C.D.

    1994-05-01

    This document presents the treatability test plan for pilot-scale pump and treat testing at the 200-UP-1 Operable Unit. This treatability test plan has been prepared in response to an agreement between the US Department of Energy, the US Environmental Protection Agency, and the Washington State Department of Ecology, as documented in Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1989a) Change Control Form M-13-93-03 (Ecology et al. 1994). The agreement also requires that, following completion of the activities described in this test plan, a 200-UP-1 Operable Unit interim remedial measure (IRM) proposed plan be developed for use in preparing an interim action record of decision (ROD). The IRM Proposed Plan will be supported by the results of the testing described in this treatability test plan, as well as by other 200-UP-1 Operable Unit activities (e.g., limited field investigation, development of a qualitative risk assessment). Once issued, the interim action ROD will specify the interim action for groundwater contamination at the 200-UP-1 Operable Unit. The approach discussed in this treatability test plan is to conduct a pilot-scale pump and treat test for the contaminant plume associated with the 200-UP-1 Operable Unit. Primary contaminants of concern are uranium and technetium-99; the secondary contaminant of concern is nitrate. The pilot-scale treatability testing presented in this test plan has as its primary purpose to assess the performance of aboveground treatment systems with respect to the ability to remove the primary contaminants in groundwater withdrawn from the contaminant plume

  18. Pilot-scale treatability test plan for the 200-BP-5 operable unit

    International Nuclear Information System (INIS)

    1994-08-01

    This document presents the treatability test plan for pilot-scale pump and treat testing at the 200-BP-5 Operable Unit. This treatability test plan has been prepared in response to an agreement between the U.S. Department of Energy (DOE), the U.S. Environmental Protection Agency (EPA), and the State of Washington Department of Ecology (Ecology), as documented in Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et al. 1989a) Change Control Form M-13-93-03 (Ecology et al. 1994) and a recent 200 NPL Agreement Change Control Form (Appendix A). The agreement also requires that, following completion of the activities described in this test plan, a 200-BP-5 Operable Unit Interim Remedial Measure (IRM) Proposed Plan be developed for use in preparing an Interim Action Record of Decision (ROD). The IRM Proposed Plan will be supported by the results of this treatability test plan, as well as by other 200-BP-5 Operable Unit activities (e.g., development of a qualitative risk assessment). Once issued, the Interim Action ROD will specify the interim action(s) for groundwater contamination at the 200-BP-5 Operable Unit. The treatability test approach is to conduct a pilot-scale pump and treat test for each of the two contaminant plumes associated with the 200-BP-5 Operable Unit. Primary contaminants of concern are 99 Tc and 60 Co for underwater affected by past discharges to the 216-BY Cribs, and 90 Sr, 239/240 Pu, and Cs for groundwater affected by past discharges to the 216-B-5 Reverse Well. The purpose of the pilot-scale treatability testing presented in this testplan is to provide the data basis for preparing an IRM Proposed Plan. To achieve this objective, treatability testing must: Assess the performance of groundwater pumping with respect to the ability to extract a significant amount of the primary contaminant mass present in the two contaminant plumes

  19. Limited field investigation report for the 100-HR-3 operable unit

    International Nuclear Information System (INIS)

    1994-09-01

    This limited field investigation (LFI) was conducted to assess the applicability of interim remedial measures (IRM) for reducing human health and environmental risks within the 100-HR-3 Groundwater Operable Unit. The 100-HR-3 Operable Unit is comprised of three subareas; the 100 D Area, the 100 H Area and those portions of the 600 Area between the two reactor areas. The operable unit is one of seven operable units associated with the 100 D and H Areas. Operable units 100-DR-1, 100-DR-2, 100-DR-3, 100-HR-1, 100-HR-2 and 100-IU-4 address contaminant sources while 100-HR-3 addresses contamination present in the underlying groundwater. The primary method of field investigation used during this LFI was the installation and sampling of monitoring wells. Samples were collected from the groundwater and soils, and submitted for laboratory analysis. Boreholes were surveyed for radiological contamination using downhole geophysical techniques to further delineate the locations and levels of contaminants. All samples were screened to ascertain the presence of volatile organic compounds and radionuclides. Analytical data were subjected to validation; all round one, two and three and a minimum of 10% of round four data associated with the LFI were validated. A screening method was used to identify contaminants of potential concern (COPC). This screening method eliminated from further consideration, constituents that were below background. Constituents which are considered non-toxic to humans were eliminated from the human health evaluation. Data consistency and blank contamination were also evaluated in the screening process. These COPC were then evaluated further in the qualitative risk assessment (QRA). A human health QRA was performed using conservative (maximum equilibrated contaminant levels from the LFI) analyses

  20. Limited field investigation report for the 100-HR-2 Operable Unit

    International Nuclear Information System (INIS)

    1994-09-01

    This report summarizes the data collection and analysis activities conducted during the 100-HR-2 Operable Unit investigative phase and the associated qualitative risk assessment (QRA). The 100-HR-2 Operable Unit contains solid waste burial grounds, an ash pit, bum pits, electrical facilities, septic systems, and support facilities. All known and suspected areas of contamination were classified as solid waste burial grounds or low-priority waste sites based on the collective knowledge of the operable unit managers (representatives from the US Department of Energy [DOE], the US Environmental Protection Agency [EPA], and Washington Department of Ecology [Ecology]) during the preparation of the 100-HR-2 Operable Unit work plan (DOE/RL 1993f). Solid waste burial grounds were judged to pose sufficient risk(s), through one or more pathways, to require evaluation for an interim remedial measure (IRM) as per the Hanford Past-Practice Strategy (HPPS) (DOE/RL 1991) and negotiations with DOE, EPA, and Ecology. An IRM is intended to achieve remedies that are likely to lead to a final record of decision. Low-priority sites are those judged not to pose significant risk to require the streamlined evaluation. There were six low-priority waste sites and seven solid waste burial grounds identified. The investigative phase was conducted in accordance with the RCRA Facility Investigation/Corrective Measures Study Work Plan for the 100-HR-2 Operable Unit (DOE/RL 1993f). The QRA was performed in accordance with the Hanford Site Baseline Risk Assessment Methodology (DOE/RL 1993b) and the recommendations incorporate the strategies of the HPPS. The purpose of this report is to: (1) provide a summary of site investigative activities; (2) refine the conceptual exposure model (as needed); (3) identify chemical- and location-specific corrective action requirements; and (4) provide a human health and ecological QRA associated with solid waste burial grounds

  1. Safety Evaluation Report related to the operation of Byron Station, Units 1 and 2 (Dockets Nos. STN 50-454 and STN 50-455)

    International Nuclear Information System (INIS)

    1984-10-01

    Supplement No. 5 to the Safety Evaluation Report related to Commonwealth Edison Company's application for licenses to operate the Byron Station, Units 1 and 2, located in Rockvale Township, Ogle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report. Because of the favorable resolution of the items discussed in this report, the staff concludes that there is reasonable assurance that the facility can be operated by the applicant without endangering the health and safety of the public

  2. Soil washing physical separations test procedure - 300-FF-1 operable unit

    Energy Technology Data Exchange (ETDEWEB)

    Belden, R.D.

    1993-10-08

    This procedure provides the operations approach, a field sampling plan, and laboratory procedures for a soil washing test to be conducted by Alternative Remedial Technologies, Inc. (ART) in the 300-FF-1 area at the Hanford site. The {open_quotes}Quality Assurance Project Plan for the Soil Washing Physical Separations Test, 300-FF-1 Operable Unit,{close_quotes} Hanford, Washington, Alternative Remedial Technologies, Inc., February 1994 (QAPP) is provided in a separate document that presents the procedural and organizational guidelines for this test. This document describes specifications, responsibilities, and general procedures to be followed to conduct physical separation soil treatability tests in the North Process Pond of the 300-FF-1 Operable Unit (OU) at the Hanford Site. These procedures are based on the {open_quotes}300-FF-1 Physical Separations CERCLA Treatability Test Plan, DOE/RL 92-2l,{close_quotes} (DOE-RL 1993).

  3. Soil washing physical separations test procedure - 300-FF-1 operable unit

    International Nuclear Information System (INIS)

    Belden, R.D.

    1993-01-01

    This procedure provides the operations approach, a field sampling plan, and laboratory procedures for a soil washing test to be conducted by Alternative Remedial Technologies, Inc. (ART) in the 300-FF-1 area at the Hanford site. The open-quotes Quality Assurance Project Plan for the Soil Washing Physical Separations Test, 300-FF-1 Operable Unit,close quotes Hanford, Washington, Alternative Remedial Technologies, Inc., February 1994 (QAPP) is provided in a separate document that presents the procedural and organizational guidelines for this test. This document describes specifications, responsibilities, and general procedures to be followed to conduct physical separation soil treatability tests in the North Process Pond of the 300-FF-1 Operable Unit (OU) at the Hanford Site. These procedures are based on the open-quotes 300-FF-1 Physical Separations CERCLA Treatability Test Plan, DOE/RL 92-2l,close quotes (DOE-RL 1993)

  4. Safety evaluation report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323). Suppl. 22

    International Nuclear Information System (INIS)

    1984-03-01

    Supplement 22 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for licenses to operate Diablo Canyon Nuclear Power Plants, Unit 1 and 2 (Docket Nos. 50-275 and 50-323), has been prepared jointly by the Office of Nuclear Reactor Regulation and the Region V Office of the US Nuclear Regulatory Commission. This supplement provides the criteria that were used by the staff to determine which of the allegations that have been evaluated and must be resolved prior to Unit 1 achieving criticality and operating at power level up to 5 percent of rated power (i.e., low power operation). The supplement also reports on the status of the staff's investigation, inspection and evaluation of 219 allegations or concerns that have been identified to the NRC as of March 9, 1984, excluding those recently received under 10 CFR 2.206 petitions

  5. Assess of the Status of the Karaj Operating Rooms in Comparison with International Standards in 2011

    Directory of Open Access Journals (Sweden)

    M.H. Naseri

    2012-10-01

    Full Text Available Background: Because of making money, the operating room (OR is known as the beating heart of any clinical & health center. The effective and regular activity of the operating room guarantees a sustainable income for the hospital. So, in order to provide high quality treatment and care services, and to save the health and safety of OR staff, exploiting standard equipments and spaces as well as employing professional and skilled personnel is necessary. This study was aimed to assess the status of the Karaj operating rooms from physical, safety, sterilization, staffing and equipment aspects in comparison to the International Standards. Methods: This sectional descriptive study was conducted in Alborz University of Medical Sciences in 2011. Samples were 10 operating room wards from 10 surgical hospitals. Data were collected by a 70 items check-list at 5 fields of physical, safety, sterilization, staffing and equipment conditions and then compared to the international standards. The data were recorded in SPSS software and analyzed by statistical methods. Results: The results showed that compared to the international standards, the physical aspect was 60.5%, safety aspect 66%, sterilization aspect 68%, staffing aspect 63%, and equipment aspect was 80% close to the standard criteria. On the whole, in 10 assessed hospitals, equipment aspect with 80% had the best and the physical aspect with 60.5% had the worst conditions respectively. Conclusion: Due to admission in different medical and paramedical programs in Alborz University of Medical Sciences, renovation of the ORs is essential for training skilled students. Considering the results of this study could help the University authorities to improve the current condition.

  6. Safety Evaluation Report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457)

    International Nuclear Information System (INIS)

    1988-06-01

    In November 1983, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1002) regarding the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). The first supplement to NUREG-1002 was issued in September 1986; the second supplement was issued in October 1986; the third supplement was issued in May 1987; the fourth supplement was issued in July 1987 in support of the full power license for Unit 1; the fifth supplement was issued in December 1987 in support of the low power license for Unit 2. This sixth supplement to NUREG-1002 is in support of the full-power license for Unit 2 and provides the status of items that remained unresolved at the time Supplement 5 was published. The facility is located in Reed Township, Will County, Illinois

  7. Remedial investigation/feasibility study work plan for the 100-KR-4 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-KR-4 operable unit. The 100-K Area consists of the 100-KR-4 groundwater operable unit and three source operable units. The 100-KR-4 operable unit includes all contamination found in the aquifer soils and water beneath the 100-K Area. Source operable units include facilities and unplanned release sites that are potential sources of contamination

  8. Remedial investigation/feasibility study work plan for the 100-KR-4 operable unit, Hanford Site, Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency`s (EPA`s) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-KR-4 operable unit. The 100-K Area consists of the 100-KR-4 groundwater operable unit and three source operable units. The 100-KR-4 operable unit includes all contamination found in the aquifer soils and water beneath the 100-K Area. Source operable units include facilities and unplanned release sites that are potential sources of contamination.

  9. Oral Health Status among Children with Cerebral Palsy in Dubai, United Arab Emirates

    Science.gov (United States)

    Al Hashmi, Haifa; Kowash, Mawlood; Hassan, Amar; Al Halabi, Manal

    2017-01-01

    Objectives: The purpose of this study was to assess the oral health status of children with cerebral palsy (CP) in Dubai, United Arab Emirates (UAE). Materials and Methods: Eighty-four CP and 125 healthy children were recruited from special needs centers and private/public schools in Dubai. A dental examination for decayed-missing-filled teeth in primary dentition (dmft)/Decayed-Missing-Filled teeth in permanent dentition (DMFT) indices, simplified oral hygiene index, calculus index (CI), and oral debris index was conducted. In addition, assessments of occlusal, dentofacial, soft tissue anomalies and erosion were conducted. Statistical analysis was conducted using SPSS for Windows, version 20.0 (SPSS Inc., Chicago, IL, USA). Results: DMFT/dmft scores were comparable in both groups. CI was significantly higher among children with CP. CP patients had a significantly higher proportion of anterior open bite, anterior spacing, Class II molar Angle malocclusion, trauma, high-arched palate, tongue thrust, lymphadenopathy, angular cheilitis, macroglossia, drooling, and erosion as compared to controls. Conclusions: The study highlighted peculiar characteristics and needs for the CP patients in Dubai, UAE. PMID:29285470

  10. Point Beach Nuclear Plant, Units 1 and 2. Semiannual operating report No. 10, January--June 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Unit 1 operated at an average capacity factor of 65.2 percent with a net efficiency of 31.41 percent. Unit 2 operted at an average capacity factor of 88.6 lpercent with a net efficiency of 32.28 percent. Unit 1 was essentially base loaded while Unit 2 operated on load follow. Information is presented concerning power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, abnormal occurrences, and environmental monitoring. (FS)

  11. International Earth Science Constellation Mission Operations Working Group: Constellation Coordination System (CCS) Status. [Constellation Coordination System (CCS) Status

    Science.gov (United States)

    Skeberdis, Daniel

    2016-01-01

    This is a presentation at the MOWG fall meeting that will discuss CCS purpose, future status, security enhancements, arbitrary ephemeris mission features, overview of CCS 7.3, approach for the use of NORAD TLEs, account and data security, CCS System virtualization, control box visualization modification and other enhancements.

  12. Implementation of the United States-Russian Highly Enriched Uranium Agreement: Current Status and Prospects

    International Nuclear Information System (INIS)

    R.rutkowski, E; Armantrout, G; Mastal, E; Glaser, J; Benton, J

    2004-01-01

    The National Nuclear Security Administration's (NNSA) Highly Enriched Uranium (HEU) Transparency Implementation Program (TIP) monitors and provides assurance that Russian weapons-grade HEU is processed into low enriched uranium (LEU) under the transparency provisions of the 1993 United States (U.S.)-Russian HEU Purchase Agreement. Meeting the Agreement's transparency provisions is not just a program requirement; it is a legal requirement. The HEU Purchase Agreement requires transparency measures to be established to provide assurance that the nonproliferation objectives of the Agreement are met. The Transparency concept has evolved into a viable program that consists of complimentary elements that provide necessary assurances. The key elements include: (1) monitoring by technical experts; (2) independent measurements of enrichment and flow; (3) nuclear material accountability documents from Russian plants; and (4) comparison of transparency data with declared processing data. In the interest of protecting sensitive information, the monitoring is neither full time nor invasive. Thus, an element of trust is required regarding declared operations that are not observed. U.S. transparency monitoring data and independent instrument measurements are compared with plant accountability records and other declared processing data to provide assurance that the nonproliferation objectives of the 1993 Agreement are being met. Similarly, Russian monitoring of U. S. storage and fuel fabrication operations provides assurance to the Russians that the derived LEU is being used in accordance with the Agreement. The successful implementation of the Transparency program enables the receipt of Russian origin LEU into the United States. Implementation of the 1993 Agreement is proceeding on schedule, with the permanent elimination of over 8,700 warhead equivalents of HEU. The successful implementation of the Transparency program has taken place over the last 10 years and has provided the

  13. Status Report and Research Plan for Cables Harvested from Crystal River Unit 3 Nuclear Generating Plant

    Energy Technology Data Exchange (ETDEWEB)

    Fifield, Leonard S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-09-20

    Harvested cables from operating or decommissioned nuclear power plants present an important opportunity to validate models, understanding material aging behavior, and validate characterization techniques. Crystal River Unit 3 Nuclear Generating Plant is a pressurized water reactor that was licensed to operate from 1976 to 2013. Cable segments were harvested and made available to the Light Water Reactor Sustainability research program through the Electric Power Research Institute. Information on the locations and circuits within the reactor from whence the cable segments came, cable construction, sourcing and installation information, and photographs of the cable locations prior to harvesting were provided. The cable variations provided represent six of the ten most common cable insulations in the nuclear industry and experienced service usage for periods from 15 to 42 years. Subsequently, these cables constitute a valuable asset for research to understand aging behavior and measurement of nuclear cables. Received cables harvested from Crystal River Unit 3 Nuclear Generating Plant consist of low voltage, insulated conductor surrounded by jackets in lengths from 24 to 100 feet each. Cable materials will primarily be used to investigate aging under simultaneous thermal and gamma radiation exposure. Each cable insulation and jacket material will be characterized in its as-received condition, including determination of the temperatures associated with endothermic transitions in the material using differential scanning calorimetry and dynamic mechanical analysis. Temperatures for additional thermal exposure aging will be selected following the thermal analysis to avoid transitions in accelerated laboratory aging that do not occur in field conditions. Aging temperatures above thermal transitions may also be targeted to investigate the potential for artifacts in lifetime prediction from rapid accelerated aging. Total gamma doses and dose rates targeted for each material

  14. Emergency operating instruction improvements at San Onofre Nuclear Generating Station Units 2 and 3

    International Nuclear Information System (INIS)

    Trillo, M.W.; Smith, B.H.

    1989-01-01

    In late 1987, San Onofre nuclear generating station (SONGS) began an extensive upgrade of the units 2 and 3 emergency operating instructions (EOIs). The original intent of this program was to incorporate revised generic guidance and to correct problems that were identified by operators. While this program was in progress, the US Nuclear Regulatory Commission (NRC) conducted a series of audits of emergency operating procedure (EOP) development and maintenance programs as 16 commercial nuclear facilities in the United States. These audits included four stations with Combustion Engineering-designed nuclear steam supply systems. (One of these audits included a review of preupgrade SONGS units 2 and 3 EOIs.) Significant industrywide comments resulted from these audits. The NRC has stated its intent to continue the review and audit of EOIs and the associated maintenance programs at all US commercial nuclear facilities. The units 2 and 3 EOI upgrade program developed procedural improvements and procedural program maintenance improvements that address many of the existing audit comments that have been received by the industry. Other resulting improvements may be useful in minimizing NRC comments in future such audits. Specific improvements are discussed. The upgrade program resulted in benefits that were not originally anticipated. The results of this program can be of significant use by other utilities in addressing the industrywide concerns that have been raised in recent NRC audits of EOP development and maintenance programs

  15. Changes in Nutritional and Functional Status in Longer Stay Patients Admitted to a Geriatric Evaluation and Management Unit.

    Science.gov (United States)

    Whitley, A; Skliros, E; Graven, C; McIntosh, R; Lasry, C; Newsome, C; Bowie, A

    2017-01-01

    Malnutrition and functional decline are common in older inpatients admitted to subacute care settings. However the association between changes in nutritional status and relevant functional outcomes remains under-researched. This study examined changes in nutritional status, function and mobility in patients admitted to a Geriatric Evaluation and Management (GEM) unit who had a length of stay (LOS) longer than 21 days. A prospective, observational study. Two GEM units at St Vincent's Hospital Melbourne, Australia. Patients admitted to the GEM units who stayed longer than 21 days were included in the study. Patients were assessed on admission and prior to discharge using the Subjective Global Assessment (SGA), Functional Independence Measure (FIM) motor domain and the Modified Elderly Mobility Scale (MEMS). Fifty-nine patients (Mean age 84.0 ± 7 years) met the required length of stay and were included in the study. Fifty-four per cent (n=32) were malnourished on admission (SGA B/C) and 44% (n=26) were malnourished on discharge. Twenty-two per cent (n=13) improved SGA category, 75% remained stable (n=44) and 3% deteriorated (n=2) from admission to discharge. Total Motor FIM scores significantly increased from admission to discharge in both the improved (pnutritional status groups. Subjects who improved in nutritional status had a significantly higher MEMS score at discharge (pnutritional status at the time of discharge. Improvement in nutritional status was associated with greater improvement in mobility scores. Further studies are required to investigate the effectiveness of nutrition interventions, which will inform models of care aiming to optimise nutritional, functional, and associated clinical outcomes in patients admitted to GEM units.

  16. Population health status of South Asian and African-Caribbean communities in the United Kingdom

    OpenAIRE

    Calvert, Melanie; Duffy, Helen; Freemantle, Nick; Davis, Russell; Lip, Gregory YH; Gill, Paramjit

    2012-01-01

    Abstract Background Population health status scores are routinely used to inform economic evaluation and evaluate the impact of disease and/or treatment on health. It is unclear whether the health status in black and minority ethnic groups are comparable to these population health status data. The aim of this study was to evaluate health-status in South Asian and African-Caribbean populations. Methods Cross-sectional study recruiting participants aged ≥ 45 years (September 2006 to July 2009) ...

  17. Preservice and inservice requirements for containment structures in the United States - a status report

    International Nuclear Information System (INIS)

    Sammataro, R.F.

    1987-01-01

    Assuring the lifetime integrity of containment structures for nuclear power plants is becoming increasingly important as existing design criteria are reexamined, as new requirements for containment inspection and testing are formulated, and as today's operating nuclear plants are growing older. Section XI of the ASME Code contains separate rules for metal (Class MC) and concrete (Class CC) containments. Requirements for Class MC containments have been published in Subsection IWE, Requirements for Class MC Components of Light-Water Cooled Power Plants, of Section XI. Rules for Class CC containments are currently being developed and will be published in Subsection IWL, Requirements for Class CC Components of Light-Water Cooled Power Plants, of Section XI. First published in 1981, Subsection IWE has been adopted by a number of state jurisdictions in the United States and is presently being reviewed by the United States Nuclear Regulatory Commission. Federal regulations that will require mandatory compliance by nuclear plant owners are forthcoming. When implemented, the requirements in Subsection IWE and Subsection IWL will provide a reasonable and systematic basis for assuring the integrity of metal and concrete containment structures during their service lifetime. This paper presents an overview of the preservice and inservice requirements for containment structures in Section XI of the ASME Code with consideration of the practical factors that should accompany user compliance. (orig./GL)

  18. Green Power Marketing in the United States: A Status Report (2008 Data)

    Energy Technology Data Exchange (ETDEWEB)

    Bird, L.; Kreycik, C.; Friedman, B.

    2009-09-01

    Voluntary consumer decisions to buy electricity supplied from renewable energy sources represent a powerful market support mechanism for renewable energy development. In the early 1990s, a small number of U.S. utilities began offering 'green power' options to their customers. Since then, these products have become more prevalent, both from traditional utilities and from renewable energy marketers operating in states that have introduced competition into their retail electricity markets or offering renewable energy certificates (RECs) online. Today, more than half of all U.S. electricity customers have an option to purchase some type of green power product directly from a retail electricity provider, while all consumers have the option to purchase RECs. This report documents green power marketing activities and trends in the United States including utility green pricing programs offered in regulated electricity markets; green power marketing activity in competitive electricity markets, as well as green power sold to voluntary purchasers in the form of RECs; and renewable energy sold as greenhouse gas offsets in the United States. These sections are followed by a discussion of key market trends and issues. The final section offers conclusions and observations.

  19. Green Power Marketing in the United States. A Status Report (2008 Data)

    Energy Technology Data Exchange (ETDEWEB)

    Bird, Lori [National Renewable Energy Lab. (NREL), Golden, CO (United States); Kreycik, Claire [National Renewable Energy Lab. (NREL), Golden, CO (United States); Friedman, Barry [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2009-09-01

    Voluntary consumer decisions to buy electricity supplied from renewable energy sources represent a powerful market support mechanism for renewable energy development. In the early 1990s, a small number of U.S. utilities began offering 'green power' options to their customers. Since then, these products have become more prevalent, both from traditional utilities and from renewable energy marketers operating in states that have introduced competition into their retail electricity markets or offering renewable energy certificates (RECs) online. Today, more than half of all U.S. electricity customers have an option to purchase some type of green power product directly from a retail electricity provider, while all consumers have the option to purchase RECs. This report documents green power marketing activities and trends in the United States including utility green pricing programs offered in regulated electricity markets; green power marketing activity in competitive electricity markets, as well as green power sold to voluntary purchasers in the form of RECs; and renewable energy sold as greenhouse gas offsets in the United States. These sections are followed by a discussion of key market trends and issues. The final section offers conclusions and observations.

  20. Status of spent nuclear fuel management in the United States of America

    International Nuclear Information System (INIS)

    Williams, J.R.

    1998-01-01

    The United States produces approximately 20% of its electricity in nuclear power reactors, currently generating, approximately 2,000 metric tons of uranium (tU) of spent nuclear fuel annually. Over the past half century, the country has amassed 33,000 tU of commercial spent nuclear fuel that is being stored at 119 operating and shutdown reactors located on 73 sites around the nation. The cumulative discharge of the spent fuel from reactors is estimated to total approximately 87,000 tU by 2035. Many sites have reracked the spent fuel in their storage pool to maximize pool capacity, and a number of reactor sites have been forced to add dry storage to accommodate the growing inventory of fuel in storage. In addition, research and defense programme reactors have produced spent fuel that is being stored in pools at Federal sites. Much of this fuel will be transferred to dry storage in the coming years. Under current plans, the commercial and federally owned fuel will remain in storage at the existing sites until the United States Department of Energy (DOE) begins receipt at a federal receiving facility. (author)

  1. The employment status of 1995 graduates from radiation oncology training programs in the United States

    International Nuclear Information System (INIS)

    Flynn, Daniel F.; Kresl, John J.; Sheldon, John M.

    1999-01-01

    Purpose: To quantify the employment status of 1995 graduates of radiation oncology training programs in the United States. Methods and Materials: All senior residents (149) and fellows (36) who completed training in 1995 were mailed an employment survey questionnaire by the Association of Residents in Radiation Oncology (ARRO). Telephone follow-up of nonrespondents achieved a 100% response rate. Twenty graduates who chose to continue training and five who returned to their home countries were removed from the study. Of the 160 who attempted to enter the U.S. workforce, 106 were men and 54 were women. Initial job status and job status at 6-8 months following graduation were determined. Results: Unemployment was 6.9% at graduation and 4.4% at 6-8 months. Underemployment (part-time employment) was 10.6% at graduation and 11.9% at 6-8 months postgraduation. Of those working part-time 6-8 months after graduation, 63% (12 of 19) did so involuntarily after unsuccessfully seeking full-time employment. For the 20 graduates who chose to continue training with fellowships, seven (35%) did so solely to avoid unemployment, four (20%) were partially influenced by the job market, and nine (45%) were not influenced by the job market. Adverse employment search outcome was defined as being either unemployed as a radiation oncologist or involuntarily working part-time. Excluding those who chose to work part-time, a total of 19 (11.9%) graduates at 6-8 months following graduation, compared to 22 (13.8%) at graduation, were either unemployed or involuntarily working part-time. In terms of gender, this represented 18.5% (10 of 54) of females and 8.6% (9 of 105) of males. In terms of geographic restrictions in the job search, 56% of males and 70% of females with an adverse employment outcome limited their job search to certain parts of the country. This compares to 62% of all graduates in this study with geographic restrictions in their job search. In terms of perceptions of the

  2. The employment status of 1995 graduates from radiation oncology training programs in the United States.

    Science.gov (United States)

    Flynn, D F; Kresl, J J; Sheldon, J M

    1999-03-15

    To quantify the employment status of 1995 graduates of radiation oncology training programs in the United States. All senior residents (149) and fellows (36) who completed training in 1995 were mailed an employment survey questionnaire by the Association of Residents in Radiation Oncology (ARRO). Telephone follow-up of nonrespondents achieved a 100% response rate. Twenty graduates who chose to continue training and five who returned to their home countries were removed from the study. Of the 160 who attempted to enter the U.S. workforce, 106 were men and 54 were women. Initial job status and job status at 6-8 months following graduation were determined. Unemployment was 6.9% at graduation and 4.4% at 6-8 months. Underemployment (part-time employment) was 10.6% at graduation and 11.9% at 6-8 months postgraduation. Of those working part-time 6-8 months after graduation, 63% (12 of 19) did so involuntarily after unsuccessfully seeking full-time employment. For the 20 graduates who chose to continue training with fellowships, seven (35%) did so solely to avoid unemployment, four (20%) were partially influenced by the job market, and nine (45%) were not influenced by the job market. Adverse employment search outcome was defined as being either unemployed as a radiation oncologist or involuntarily working part-time. Excluding those who chose to work part-time, a total of 19 (11.9%) graduates at 6-8 months following graduation, compared to 22 (13.8%) at graduation, were either unemployed or involuntarily working part-time. In terms of gender, this represented 18.5% (10 of 54) of females and 8.6% (9 of 105) of males. In terms of geographic restrictions in the job search, 56% of males and 70% of females with an adverse employment outcome limited their job search to certain parts of the country. This compares to 62% of all graduates in this study with geographic restrictions in their job search. In terms of perceptions of the workforce and employment opportunities, 95% of

  3. Current status and prospect of plasma control system for steady-state operation on QUEST

    International Nuclear Information System (INIS)

    Hasegawa, Makoto; Nakamura, Kazuo; Zushi, Hideki; Hanada, Kazuaki; Fujisawa, Akihide; Tokunaga, Kazutoshi; Idei, Hiroshi; Nagashima, Yoshihiko; Kawasaki, Shoji; Nakashima, Hisatoshi; Higashijima, Aki

    2016-01-01

    Highlights: • Overall configuration of plasma control system on QUEST are presented. • Multi core system and reflective memories are used for the real-time control. • Hall sensors are used for the identification of plasma current and its position. • Repetitive gas fueling with the feed-back control of Hα signal is implemented. - Abstract: The plasma control system (PCS) of QUEST is developed according to the progress of QUEST project. Since one of the critical goals of the project is to achieve the steady-state operation with high temperature vacuum vessel wall, the PCS is also required to have the capability to control the plasma for a long period. For the increase of the loads to processing power of the PCS, the PCS is decentralized with the use of reflective memories (RFMs). The PCS controls the plasma edge position with the real-time identification of plasma current and its position. This identification is done with not only flux loops but also hall sensors. The gas fueling method by piezo valve with monitoring the Hα signal filtered by a digital low-pass filter are proposed and suitable for the steady-state operation on QUEST. The present status and prospect of the PCS are presented with recent topics.

  4. Cryosat: ESA'S Ice Explorer Mission, 6 years in operations: status and achievements

    Science.gov (United States)

    Parrinello, Tommaso; Maestroni, Elia; Krassenburg, Mike; Badessi, Stefano; Bouffard, Jerome; Frommknecht, Bjorn; Davidson, Malcolm; Fornari, Marco; Scagliola, Michele

    2016-04-01

    CryoSat-2 was launched on the 8th April 2010 and it is the first European ice mission dedicated to monitoring precise changes in the thickness of polar ice sheets and floating sea ice over a 3-year period. CryoSat-2 carries an innovative radar altimeter called the Synthetic Aperture Interferometric Altimeter (SIRAL) with two antennas and with extended capabilities to meet the measurement requirements for ice-sheets elevation and sea-ice freeboard. Initial results have shown that data is of high quality thanks to an altimeter that is behaving exceptional well within its design specifications. The CryoSat mission reached its 6th years of operational life in April 2016. Since its launch has delivered high quality products to the worldwide cryospheric and marine community that is increasing every year. Scope of this paper is to describe the current mission status and its main scientific achievements. Topics will also include programmatic highlights and information on the next scientific development of the mission in its extended period of operations.

  5. Cryosat: ESA'S Ice Explorer Mission. Five years in operations: status and achievements

    Science.gov (United States)

    Parrinello, Tommaso; Mardle, Nicola; Krassenburg, Mike; Badessi, Stefano; Bouffard, Jerome; Frommknecht, Bjorn; Fornari, Marco; Scagliola, Michele

    2015-04-01

    CryoSat-2 was launched on the 8th April 2010 and it is the first European ice mission dedicated to monitoring precise changes in the thickness of polar ice sheets and floating sea ice over a 3-year period. CryoSat-2 carries an innovative radar altimeter called the Synthetic Aperture Interferometric Altimeter (SIRAL) with two antennas and with extended capabilities to meet the measurement requirements for ice-sheets elevation and sea-ice freeboard. Initial results have shown that data is of high quality thanks to an altimeter that is behaving exceptional well within its design specifications. The CryoSat mission reached its 5th years of operational life in April 2015. Since its launch has delivered high quality products to the worldwide cryospheric and marine community that is increasing every year. Scope of this paper is to describe the current mission status and the main scientific achievements in the last twelve months. Topics will also include programmatic highlights and information on the next scientific development of the mission in its extended period of operations.

  6. CryoSat: ESA's ice explorer mission. 4 years in operations: status and achievements

    Science.gov (United States)

    Parrinello, T.; Mardle, N.; Ortega, B.; Bouffard, J.; Badessi, S.; Frommknecht, B.; Davidson, M.

    2014-12-01

    CryoSat-2 was launched on the 8th April 2010 and it is the first European ice mission dedicated to monitoring precise changes in the thickness of polar ice sheets and floating sea ice over a 3-year period. CryoSat-2 carries an innovative radar altimeter called the Synthetic Aperture Interferometric Altimeter (SIRAL) with two antennas and with extended capabilities to meet the measurement requirements for ice-sheets elevation and sea-ice freeboard. Initial results have shown that data is of high quality thanks to an altimeter that is behaving exceptional well within its design specifications. The CryoSat mission reached its 4th years of operational life in April 2014. Since its launch has delivered high quality products to the worldwide cryospheric and marine community that is increasing every year. Scope of this paper is to describe the current mission status and the main scientific achievements in the last twelve months. Topics will also include programmatic highlights and information on the next scientific development of the mission in its extended period of operations.

  7. Current status and prospect of plasma control system for steady-state operation on QUEST

    Energy Technology Data Exchange (ETDEWEB)

    Hasegawa, Makoto, E-mail: hasegawa@triam.kyushu-u.ac.jp; Nakamura, Kazuo; Zushi, Hideki; Hanada, Kazuaki; Fujisawa, Akihide; Tokunaga, Kazutoshi; Idei, Hiroshi; Nagashima, Yoshihiko; Kawasaki, Shoji; Nakashima, Hisatoshi; Higashijima, Aki

    2016-11-15

    Highlights: • Overall configuration of plasma control system on QUEST are presented. • Multi core system and reflective memories are used for the real-time control. • Hall sensors are used for the identification of plasma current and its position. • Repetitive gas fueling with the feed-back control of Hα signal is implemented. - Abstract: The plasma control system (PCS) of QUEST is developed according to the progress of QUEST project. Since one of the critical goals of the project is to achieve the steady-state operation with high temperature vacuum vessel wall, the PCS is also required to have the capability to control the plasma for a long period. For the increase of the loads to processing power of the PCS, the PCS is decentralized with the use of reflective memories (RFMs). The PCS controls the plasma edge position with the real-time identification of plasma current and its position. This identification is done with not only flux loops but also hall sensors. The gas fueling method by piezo valve with monitoring the Hα signal filtered by a digital low-pass filter are proposed and suitable for the steady-state operation on QUEST. The present status and prospect of the PCS are presented with recent topics.

  8. Health-promoting lifestyle behaviors and psychological status among Arabs and Koreans in the United Arab Emirates.

    Science.gov (United States)

    Kim, Hee Jun; Choi-Kwon, Smi; Kim, Hyungjin; Park, Yeon-Hwan; Koh, Chin-Kang

    2015-04-01

    Cultural variations among ethnic groups may differentially influence health and health behavior. We explored and compared health-promoting lifestyle behaviors and psychological status, including depression, anxiety, and stress, among Korean migrants (n = 117) and Arab nationals (n = 103) in the United Arab Emirates (UAE). Pender's Health Promotion Model guided this research. The Health-Promoting Lifestyle Profile was used to measure health-promoting lifestyle behaviors and Lovibond and Lovibond's Depression, Anxiety, and Stress Scale to measure psychological status. The data were analyzed using bivariate procedures and multiple linear regression. No group differences were found in total scores for health-promoting lifestyle behaviors or psychological status. Both groups scored high on self-actualization and interpersonal support; Arabs scored low on exercise, and Koreans scored low on health responsibility. Across groups, psychological status (β = -.390, p Arab nationals in the UAE. © 2015 Wiley Periodicals, Inc.

  9. Remedial investigation/feasibility study work plan for the 100-FR-3 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Figure 1-1 shows the location of these areas. Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-FR-3 operable unit. The 100-K Area consists of the 100-FR-3 groundwater operable unit and two source operable units. The 100-FR-3 operable unit includes all contamination found in the aquifer soils and water beneath the 100-F Area. Source operable units include facilities and unplanned release sites that are potential sources of contamination. A separate work plan has been initiated for the 100-FR-1 source operable unit (DOE-RL 1992a)

  10. Remedial investigation/feasibility study work plan for the 100-FR-1 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-08-01

    Four areas of the Hanford Site (the 100, 200,300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. This work plan and the attached supporting project plans establish the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-FR-1 operable unit. The 100-FR-1 source operable unit is one of two source operable units in the 100-F Area. Source operable units include facilities and unplanned release sites that are potential sources of hazardous substance contamination. The groundwater affected or potentially affected by the entire 100-F Area is considered as a separate operable unit, the 100-FR-3 groundwater operable unit. A separate work plan has been initiated for the 100-FR-3 operable unit (DOE/RL 1992a)

  11. Monitoring of operating processes

    International Nuclear Information System (INIS)

    Barry, R.F.

    1981-01-01

    Apparatus is described for monitoring the processes of a nuclear reactor to detect off-normal operation of any process and for testing the monitoring apparatus. The processes are evaluated by response to their paramters, such as temperature, pressure, etc. The apparatus includes a pair of monitoring paths or signal processing units. Each unit includes facilities for receiving on a time-sharing basis, a status binary word made up of digits each indicating the status of a process, whether normal or off-normal, and test-signal binary words simulating the status binary words. The status words and test words are processed in succession during successive cycles. During each cycle, the two units receive the same status word and the same test word. The test words simulate the status words both when they indicate normal operation and when they indicate off-normal operation. Each signal-processing unit includes a pair of memories. Each memory receives a status word or a test word, as the case may be, and converts the received word into a converted status word or a converted test word. The memories of each monitoring unit operate into a non-coincidence which signals non-coincidence of the converted word out of one memory of a signal-processing unit not identical to the converted word of the other memory of the same unit

  12. Surry Power Station, Units 1 and 2. Semiannual operating report, July--December 1974

    International Nuclear Information System (INIS)

    1974-01-01

    Net electric power generated by Surry Unit 1 was 6,930,353 MWH with the generator on line for 10,417.7 hours. Net electric power generated by Unit 2 was 5,699,299 MWH with the generator on line for 8,384.2 hours. Information is presented concerning operation, radioactive effluent releases, solid radioactive wastes, fuel shipments, occurrences in which temperature limitations on the condenser cooling water discharge were exceeded, changes in station organization, occupational personnel radiation exposure, nonradiological monitoring including thermal, physical, and biological programs, and the radiological environmental monitoring program. (U.S.)

  13. Retrofitting and operation solid radwaste system Dresden Station, Units 2 and 3

    International Nuclear Information System (INIS)

    Testa, J.; Homer, J.C.

    1982-01-01

    Units 2 and 3 at Dresden Station are twin 794 MW (net) BWR units that became operational in 1970 and 1971. The waste streams are typical of BWR stations, namely, bead resin and filter sludge (powdered resins and diatomaceous earth), evaporator concentrate containing approximately 25% dissolved solids and dry active waste. The original solid radwaste system utilized cement for solidification in open top 55 gallon drums. Remote handling was provided by means of a monorail with moving platforms supporting the drums. A relatively light-weight compactor was used to compact DAW into 55 gallon drums. Difficulties were experienced with this system

  14. Qualitative risk assessment for the 100-FR-1 source operable unit

    International Nuclear Information System (INIS)

    Corporation, I.T.

    1994-08-01

    This report provides the Qualitative risk assessment (QRA) for the waste sites associated with the 100-FR-1 Operable Unit. The QRA is an evaluation of risk for a predefined set of human and ecological exposure scenarios. It is not intended to replace or be a substitute for a baseline risk assessment. The QRA is streamlined to consider only two human health scenarios (frequent-and occasional-use) with four exposure pathways (soil ingestion, fugitive dust inhalation, inhalation of volatile organics, and external radiation exposure) and a limited ecological evaluation. The use of these scenarios and pathways was agreed to by the 100 Area Tri-Party unit managers

  15. Indian Point Station, Unit 1 and 2. Semiannual operating report No. 24, July--December 1974

    International Nuclear Information System (INIS)

    1975-01-01

    Net electrical power generated by Unit 1 was 519,130 MWH with the reactor critical for 2,400.39 hours and the generator on line for 2,316.14 hours. Unit 2 generated 2,427,828 MWH electrical power, was critical for 3,590.31 hours and the generator was on line for 3,485.41 hours. Operations and maintenance are summarized. Information is presented concerning radioactive effluent releases, occupational personnel radiation protection, primary coolant chemistry, changes, tests, and experiments. Environmental radioactivity is discussed. (U.S.)

  16. Commercial operation and outage experience of ABWR at Kashiwazaki-Kariwa units Nos. 6 and 7

    International Nuclear Information System (INIS)

    Anahara, N.; Yamada, M.; Kataoka, H.

    2000-01-01

    Kashiwazaki-Kariwa Nuclear Power Station Units Nos. 6 and 7, the world's first ABWRs (Advanced Boiling Water Reactor), started commercial operation on November 7, 1996 and July 2, 1997, respectively, and continued their commercial operation with a high capacity factor, low occupational radiation exposure and radioactive waste. Units 6 and 7 were in their 3rd cycle operation until 25th April 1999 and 1st November 1999, respectively. Thermal efficiency was 35.4-35.8% (design thermal efficiency: 34.5%) during these period, demonstrating better performance than that of BWR-5 (design thermal efficiency: 33.4%). Nos. 6 and 7 have experienced 2 annual outages. The first outage of unit No. 6 started on November 20, 1997 and was completed within 61 days (including 6 New Year holidays), and the second outage started on March 13, 1999 and was completed within 44 days. The first annual outage of unit No. 7 started on May 27, 1998, earlier than it would normally have been, to avoid an annual outage during the summer, and was completed within 55 days, and the second outage started on September 18th, 1999 and was completed within 45 days, All annual outages were carried out within a very short time period without any severe malfunctions, including newly designed ABWR systems and equipment. As the first outage in Japan, 55 days is a very short period, despite the fact that the Nos. 6 and 7 are the first ABWRs in the world and the largest capacity units in Japan. The total occupational radiation exposure of No. 6 was 300 man-mSv (1st outage) and 331 man-mSv (2nd outage). That of Unit 7 was 153 man-mSv (1st outage) Those of unit No. 6 were at the same level as those of unit No. 3, which is the latest design 1100MW(e) BWR-5. That of unit No. 7 was the lowest ever at Kashiwazaki-Kariwa nuclear power station. The drums of radioactive waste discharged during the annual outage numbered 54 (1st outage) for No. 6 and 62 (1st outage) for No. 7, which was less than the design target of 100

  17. Automated processing of whole blood units: operational value and in vitro quality of final blood components.

    Science.gov (United States)

    Jurado, Marisa; Algora, Manuel; Garcia-Sanchez, Félix; Vico, Santiago; Rodriguez, Eva; Perez, Sonia; Barbolla, Luz

    2012-01-01

    The Community Transfusion Centre in Madrid currently processes whole blood using a conventional procedure (Compomat, Fresenius) followed by automated processing of buffy coats with the OrbiSac system (CaridianBCT). The Atreus 3C system (CaridianBCT) automates the production of red blood cells, plasma and an interim platelet unit from a whole blood unit. Interim platelet unit are pooled to produce a transfusable platelet unit. In this study the Atreus 3C system was evaluated and compared to the routine method with regards to product quality and operational value. Over a 5-week period 810 whole blood units were processed using the Atreus 3C system. The attributes of the automated process were compared to those of the routine method by assessing productivity, space, equipment and staffing requirements. The data obtained were evaluated in order to estimate the impact of implementing the Atreus 3C system in the routine setting of the blood centre. Yield and in vitro quality of the final blood components processed with the two systems were evaluated and compared. The Atreus 3C system enabled higher throughput while requiring less space and employee time by decreasing the amount of equipment and processing time per unit of whole blood processed. Whole blood units processed on the Atreus 3C system gave a higher platelet yield, a similar amount of red blood cells and a smaller volume of plasma. These results support the conclusion that the Atreus 3C system produces blood components meeting quality requirements while providing a high operational efficiency. Implementation of the Atreus 3C system could result in a large organisational improvement.

  18. Towards harmonised self assessment of research reactor safety status in operating organisations

    International Nuclear Information System (INIS)

    Kirchsteiger, C.; Boeck, H.

    2006-01-01

    The objective of this paper is to describe the development of a methodology and corresponding web-based tool for mapping and cross-comparing the safety approaches in European and other Research Reactor (RR) facilities in order to detect the principal similarities and differences. As an example, the performance of a Probabilistic Safety Assessment (PSA) for RRs is mapped, as follows: is PSA performed at all? (Yes/No); if so, is PSA mandatory or just recommended? (Yes/No); what is the scope of PSA?, its objective? and practical use? (set of more detailed questions), etc. In this way, information on different types of safety verification practices and requirements for RRs from Europe, Argentina, Australia, Canada, South Africa and the USA has been collected in a systematic way and included in the web-based benchmarking tool DARES (DAtabase for REsearch Reactor Safety). DARES has been developed and filled with sample data by the European Commission's Joint Research Centre (JRC) together with members of the European Research Reactors Operator Group (RROG). A systematic mapping by using DARES in parallel to an international Working Group, consisting of both operators and authorities could be the starting point towards harmonisation of RR safety verification on an international level. In addition, the availability of a user-friendly Information System on the Internet such as DARES containing this information is considered a useful mechanism to exchange international experiences and practices in the area among qualified users. This approach is currently considered to be proposed to the International Atomic Energy Agency (IAES) as one possible application of the recently adopted IAEA Code of Conduct on the Safety of Research Reactors. The resulting process would be a self-assessment of the RR safety status in regulatory bodies and operating organisations relative to the guidance in the Code, practically realised and monitored by an Information System similar to DARES. (orig.)

  19. An analysis of post-traumatic stress symptoms in United States Air Force drone operators.

    Science.gov (United States)

    Chappelle, Wayne; Goodman, Tanya; Reardon, Laura; Thompson, William

    2014-06-01

    Remotely piloted aircraft (RPA), commonly referred to as "drones," have emerged over the past decade as an innovative warfighting tool. Given there is a paucity of empirical research assessing drone operators, the purpose of this study was to assess for the prevalence of PTSD symptoms among this cohort. Of the 1084 United States Air Force (USAF) drone operators that participated, a total of 4.3% endorsed a pattern of symptoms of moderate to extreme level of severity meeting criteria outlined in the Diagnostic and Statistical Manual of Mental Disorders-4th edition. The incidence of PTSD among USAF drone operators in this study was lower than rates of PTSD (10-18%) among military personnel returning from deployment but higher than incidence rates (less than 1%) of USAF drone operators reported in electronic medical records. Although low PTSD rates may be promising, limitations to this study are discussed. Copyright © 2014 Elsevier Ltd. All rights reserved.

  20. Current status of nuclear power in the United States and around the world.

    Science.gov (United States)

    McKlveen, J W

    1990-09-01

    Nuclear energy's share of the world electricity market has been growing over the past 35 years. In 1989, eight generating units entered commercial operation abroad and three new units were licensed in the U.S. In early 1990, Mexico became the 26th country to produce electricity from nuclear power. Currently the 426 operating reactors supply one sixth of the world's total electrical capacity. Fourteen countries have now operated nuclear plants for 20 or more years. Since 1980, France has been the leader in the use of nuclear power and currently generates three quarters of its electricity from 54 nuclear plants. The U.S. has 112 nuclear plants, the largest number of any country in the world. These plants satisfy almost 20 percent of U.S. electrical energy requirements. Last year Three Mile Island, the would-be icon for everything that is wrong with the nuclear industry was rated as the most efficient nuclear plant in the world. The worldwide trend toward acceptance of nuclear is improving slightly, but many political and societal issues need to be resolved. Whereas recent polls indicate that a majority of the people realize nuclear must be a major contributor to the energy mix of the future, many are reluctant to support the technology until the issue of waste disposal has been resolved. Fears of another Chernobyl, lack of capital, and a new anti-nuclear campaign by Greenpeace will keep the nuclear debate alive in many countries. Additional stumbling blocks in the U.S. include the need to develop a new generation of improved reactor designs which emphasize passive safety features, standardized designs and a stream-lined federal licensing process. Nuclear power is really not dead. Even environmentalists are starting to give it another look. A nuclear renaissance will occur in the U.S. How soon or under what conditions remain to be seen. The next crisis in the U.S. will not be a shortage of energy, rather a shortage of electricity.(ABSTRACT TRUNCATED AT 250 WORDS)

  1. THE FINANCING OF THE ADMINISTRATIVE TERRITORIAL UNITS IN THE WEST DEVELOPMENT REGION THROUGH THE REGIONAL OPERATIONAL PROGRAMME 2007 - 2013

    Directory of Open Access Journals (Sweden)

    Munteanu Nicolae-Eugen

    2011-07-01

    elaborated and assumed strategies of local development, and also on the experience gained by the administrative-territorial units in accessing the governmental funds and the pre-accession programs, the authorities of the local public administration from the West Development Region knew how to successfully access the non-reimbursable financing opportunities granted through the Regional Operational Programme 2007 - 2013. The status analysis of the implementation of the projects submitted by the administrative-territorial units from the West Development Region and financed through the Regional Operational Programme 2007 - 2013 highlights which are the main areas of interest for the authorities of the public local administration and gives practical solutions for the reduction of the intra-regional development gaps. This article is intended to be a guide for the administrative-territorial units in the systematic mobilization of the existing local energies and resources by means of certain projects which should meet the specific needs for development and which should involve the attraction of non-reimbursable funds with a minimum effort of co-financing.

  2. RCRA facility investigation/corrective measures study work plan for the 200-UP-2 Operable Unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1993-06-01

    The 200-UP-2 Operable Unit is one of two source operable units at the U Plant Aggregate Area at the Hanford Site. Source operable units include waste management units and unplanned release sites that are potential sources of radioactive and/or hazardous substance contamination. This work plan, while maintaining the title RFI/CMS, presents the background and direction for conducting a limited field investigation in the 200-UP-2 Operable Unit, which is the first part of the process leading to final remedy selection. This report discusses the background, prior recommendations, goals, organization, and quality assurance for the 200-UP-2 Operable Unit Work Plan. The discussion begins with a summary of the regulatory framework and the role of the work plan. The specific recommendations leading into the work plan are then addressed. Next, the goals and organization of the report are discussed. Finally, the quality assurance and supporting documentation are presented

  3. Dose rate evaluation of workers on the operation floor in Fukushima-Daiichi Unit 3

    Science.gov (United States)

    Matsushita, Kaoru; Kurosawa, Masahiko; Shirai, Keisuke; Matsuoka, Ippei; Mukaida, Naoki

    2017-09-01

    At Fukushima Daiichi Nuclear Power Plant Unit 3, installation of a fuel handling machine is planned to support the removal of spent fuel. The dose rates at the workplace were calculated based on the source distribution measured using a collimator in order to confirm that the dose rates on the operation floor were within a manageable range. It was confirmed that the accuracy of the source distribution was C/M = 1.0-2.4. These dose rates were then used to plan the work on the operation floor.

  4. Ageing Management of the reactor internals in Belgian nuclear units in view of Long Term Operation

    International Nuclear Information System (INIS)

    Gerard, R.; Bertolis, D.; Vissers, S.

    2012-01-01

    The reactor internals support the reactor core, distribute the coolant flow through the core, and guide and protect the rod control cluster assemblies and in-core instrumentation. Their integrity must be guaranteed in all operating and accident conditions. They are exposed to specific degradation mechanisms linked to the intense neutron irradiation, like Irradiation Assisted Stress Corrosion Cracking (IASCC) or potentially void swelling, in addition to more classical mechanisms like fatigue, wear and stress corrosion cracking. A rigorous follow-up of in-service degradation and an effective ageing management is therefore of crucial importance and contributes to the safe and economical operation of nuclear PWR units. (author)

  5. Development of in-situ product removal strategies in biocatalysis applying scaled-down unit operations

    DEFF Research Database (Denmark)

    Heintz, Søren; Börner, Tim; Ringborg, Rolf Hoffmeyer

    2017-01-01

    different process steps while operating it as a combined system, giving the possibility to test and characterize the performance of novel process concepts and biocatalysts with minimal influence of inhibitory products. Here the capabilities of performing process development by applying scaled-down unit...... operations are highlighted through a case study investigating the asymmetric synthesis of 1-methyl-3-phenylpropylamine (MPPA) using ω-transaminase, an enzyme in the sub-family of amino transferases (ATAs). An on-line HPLC system was applied to avoid manual sample handling and to semi...

  6. Final Status Survey Report for Corrective Action Unit 117 - Pluto Disassembly Facility, Building 2201, Nevada National Security Site, Nevada

    International Nuclear Information System (INIS)

    Gwin, Jeremy; Frenette, Douglas

    2010-01-01

    This document contains the process knowledge, radiological data and subsequent statistical methodology and analysis to support approval for the radiological release of Corrective Action Unit (CAU) 117 - Pluto Disassembly Facility, Building 2201 located in Area 26 of the Nevada National Security Site (NNSS). Preparations for release of the building began in 2009 and followed the methodology described in the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). MARSSIM is the DOE approved process for release of Real Property (buildings and landmasses) to a set of established criteria or authorized limits. The pre-approved authorized limits for surface contamination values and corresponding assumptions were established by DOE O 5400.5. The release criteria coincide with the acceptance criteria of the U10C landfill permit. The U10C landfill is the proposed location to dispose of the radiologically non-impacted, or ''clean,'' building rubble following demolition. However, other disposition options that include the building and/or waste remaining at the NNSS may be considered providing that the same release limits apply. The Final Status Survey was designed following MARSSIM guidance by reviewing historical documentation and radiological survey data. Following this review a formal radiological characterization survey was performed in two phases. The characterization revealed multiple areas of residual radioactivity above the release criteria. These locations were remediated (decontaminated) and then the surface activity was verified to be less than the release criteria. Once remediation efforts had been successfully completed, a Final Status Survey Plan (10-015, ''Final Status Survey Plan for Corrective Action Unit 117 - Pluto Disassembly Facility, Building 2201'') was developed and implemented to complete the final step in the MARSSIM process, the Final Status Survey. The Final Status Survey Plan consisted of categorizing each individual room into one

  7. Coordinating bifurcated remediation of soil and groundwater at sites containing multiple operable units

    International Nuclear Information System (INIS)

    Laney, D.F.

    1996-01-01

    On larger and/or more complex sites, remediation of soil and groundwater is sometimes bifurcated. This presents some unique advantages with respect to expedited cleanup of one medium, however, it requires skillful planning and significant forethought to ensure that initial remediation efforts do not preclude some long-term options, and/or unduly influence the subsequent selection of a technology for the other operable units and/or media. this paper examines how the decision to bifurcate should be approached, the various methods of bifurcation, the advantages and disadvantages of bifurcation, and the best methods to build flexibility into the design of initial remediation systems so as to allow for consideration of a fuller range of options for remediation of other operable units and/or media at a later time. Pollutants of concern include: metals; petroleum hydrocarbons; and chlorinated solvents

  8. Development of Regulatory Audit Programs for Wolsong Unit 1 Continued Operation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hong Key; Nho, Seung Hwan; Song, Myung Ho [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2012-05-15

    Wolsong Unit 1 (PHWR type) design life expires on November 20, 2010. In relation to it, KHNP submitted its application to get approval of the MEST on December 30, 2009 and KINS is under review to confirm the appropriateness of continued operation. For the comprehensive review of Wolsong Unit 1 continued operation, KINS has developed the review guidelines for PHWR type reactor including a total of 39 aging management program (AMP) items and 7 time limited aging analysis (TLAA) items. Evaluations or calculations to verify the integrity of nuclear components are required for plant specific AMP and TLAA items as well as the ones specified in the guidelines. In this paper, audit calculation programs developed for KINS staff use in reviewing applicant's submitted evaluation results are presented

  9. Computer Drawing Method for Operating Characteristic Curve of PV Power Plant Array Unit

    Science.gov (United States)

    Tan, Jianbin

    2018-02-01

    According to the engineering design of large-scale grid-connected photovoltaic power stations and the research and development of many simulation and analysis systems, it is necessary to draw a good computer graphics of the operating characteristic curves of photovoltaic array elements and to propose a good segmentation non-linear interpolation algorithm. In the calculation method, Component performance parameters as the main design basis, the computer can get 5 PV module performances. At the same time, combined with the PV array series and parallel connection, the computer drawing of the performance curve of the PV array unit can be realized. At the same time, the specific data onto the module of PV development software can be calculated, and the good operation of PV array unit can be improved on practical application.

  10. Main problems experienced on diesel generators of French 900 MWe operating units

    Energy Technology Data Exchange (ETDEWEB)

    Dredemis, Geoffroy; Jude, Francois [Commissariat a l' Energie Atomique, centre d' Etudes Nucleaires de Fontenay-aux-Roses, Institut de Protection et Surete Nucleaire, Departement d' Analyse de Surete, B.P. No. 6, 92260 Fontenay-aux-Roses (France)

    1986-02-15

    Each unit of all the French nuclear power plant is equipped with two diesel emergency generator sets., For the totality of standards PWRs of 900 MWe, they are identical. We present in this communication the most significative failures met with diesel engines on operating units, such as rupture of fuel injection pipes, breaking of the connecting rods, and cylinder lubrication failures. All these incidents, which affected the emergency power sources of concerned units, had generic characteristics. In view of their potential consequences, it was proceeded in each case to an immediate control of the components concerned of all PWR 900 MWe diesel engines. At the same time, studies were started as to what modifications would permit to solve rapidly each one of the problems met with. (authors)

  11. Start up and commercial operation of Laguna Verde nuclear power plant. Unit 1

    International Nuclear Information System (INIS)

    Torres Ramirez, J.F.

    1991-01-01

    Prior to start up of Laguna Verde nuclear power plant preoperational tests and start tests were performed and they are described in its more eminent aspects. In relation to commercial operation of nuclear station a series of indicator were set to which allow the measurement of performance in unit 1, in areas of plant efficiency and personal safety. Antecedents. Laguna Verde station is located in Alto Lucero municipality in Veracruz state, 70 kilometers north-northeast from port of Veracruz and a 290 kilometers east-northeast from Mexico city. The station consist of two units manufactured by General Electric, with a nuclear system of vapor supply also called boiling water (BWR/5), and with a system turbine-generator manufactured by Mitsubishi. Each unit has a nominal power of 1931 MWt and a level design power of 675 Mwe and a net power of 654 Electric Megawatts

  12. 200-ZP-1 operable unit borehole summary report for FY 1995 and FY 1996

    International Nuclear Information System (INIS)

    Darrach, M.E.

    1996-10-01

    This document details the well construction, sampling, analyses, and geologic character of the Ringold Formation fluvial unit E gravels as encountered in 16 boreholes in the 200-ZP-1 Operable Unit. These boreholes were drilled by Water Development Hanford Corporation during fiscal years 1995 and 1996. Two of the sixteen boreholes were abandoned; the remaining 14 boreholes were completed as functioning production and compliance wells. The borehole logs and well summary sheets included as Appendices A and B of this document, respectively, depict and describe the vadose zone stratigraphic units encountered during the course of drilling. Appendix C contains the results of sieve analyses conducted on samples obtained via resonant sonic coring and standard split-spoon methods. The sieve analyses were the driver behind the majority of the well designs. Also, for completeness, Appendices D and E contain the well design calculations and the well development process

  13. Aquatic studies at the 100-HR-3 and 100-NR-1 operable units

    International Nuclear Information System (INIS)

    Cushing, C.E.

    1993-04-01

    Pacific Northwest Laboratory initiated a program to characterize selected aquatic biological populations to determine (1) existing levels of inorganic chemical and radionuclide contamination, and (2) the populations' suitability as indicators of chemical releases during cleanup activities at the US Department of Energy's Hanford Site. Following work plans for the ground-water operable units, lower trophic levels in the aquatic habitat (periphyton and caddisfly larvae) were evaluated for contaminants at the 100-HR-3 Operable Unit and 100-NR-1 Operable Unit. The results were evaluated to determine the need for further sampling. If the results showed no significant contamination compared to upriver levels, sampling would be discontinued. The periphyton community appears to be suitable for determining contamination levels. Baseline concentrations for stable chromium were established and will be useful for comparing samples collected when contaminant release is expected. Concentrations of 60 Co, 90 Sr, and 137 Cs in periphyton were essentially below detectable limits, which will also make this community useful in detecting potential releases of radionuclides during cleanup activities. Levels for both stable chromium and radionuclides were essentially below detection limits for caddisfly larvae. Thus, these organisms may be used to monitor suspected contaminant releases from cleanup activities; if concentrations exceed detection limits, they may be related to these activities. Two candidate threatened and endangered species of molluscs occur in the Hanford Reach of the Columbia River. These are the shortface lanx (Fisherola nuttalli), which is a Washington State candidate species, and the Columbia pebblesnail (Fluminicola columbiana), which is both a state and federal candidate species. Specimens of the shortface lanx were observed in the vicinity of N Springs (100-NR-1 Operable Unit); they likely occur throughout this area

  14. Condition based monitoring, diagnosis and maintenance on operating equipments of a hydraulic generator unit

    International Nuclear Information System (INIS)

    Liu, X T; Feng, F Z; Si, A W

    2012-01-01

    According to performance characteristics of operating equipments in a hydraulic generator unit (HGU), the relative techniques on condition monitoring and fault diagnosis (CMFD) are introduced in this paper, especially the key technologies are emphasized, such as equipment monitoring, expert system (ES), intelligent diagnosis and condition based maintenance (CBM). Meanwhile, according to the instructor on CBM proposed by State electric power corporation, based on integrated mode, the main steps on implementation of CBM are discussed in this paper.

  15. INEL Operable Unit 7-13 containment and stabilization configuration option

    International Nuclear Information System (INIS)

    Raivo, B.D.; Richardson, J.G.; Nickelson, D.F.

    1993-05-01

    A containment and stabilization configuration option has been developed for the Idaho National Engineering Laboratory's Subsurface Disposal Area Operable Unit 7-13, the transuranic (TRU)-contaminated waste pits and trenches. The configuration option is presented as an end-to-end system block diagram. Functional subelements are separately discussed, and technical background information, assumptions, input, high-level subelement requirements, and output are presented for each option

  16. Baseline groundwater model update for p-area groundwater operable unit, NBN

    Energy Technology Data Exchange (ETDEWEB)

    Ross, J. [Savannah River Site (SRS), Aiken, SC (United States); Amidon, M. [Savannah River Site (SRS), Aiken, SC (United States)

    2015-09-01

    This report documents the development of a numerical groundwater flow and transport model of the hydrogeologic system of the P-Area Reactor Groundwater Operable Unit at the Savannah River Site (SRS) (Figure 1-1). The P-Area model provides a tool to aid in understanding the hydrologic and geochemical processes that control the development and migration of the current tritium, tetrachloroethene (PCE), and trichloroethene (TCE) plumes in this region.

  17. Black Fox Station, Units 1 and 2. Application for construction permits and operating licenses

    International Nuclear Information System (INIS)

    1975-01-01

    An application to construct and operate Black Fox Station, Units 1 and 2, is presented. The two BWR type reactors will have a rated core thermal power of 3579 MW(t) and a net electrical power of approximately 1150 MW(e). The facility will be located in Inola Township, 23 miles east of Tulsa on the east side of the Verdigris River in Rogers County, Oklahoma

  18. The new local control systems for operating gaseous diffusion plant units at Pierrelatte

    International Nuclear Information System (INIS)

    Delacroix, C.

    1990-01-01

    The development of a local control network for operating gaseous diffusion plant units is presented. The objective of the control system up date was to replace all the information network hardware. The new generation HP1000 calculators and a network architecture were chosen. The validation tests performed in laboratory and in situ, and the management policies towards the personnel during the technical changes are summarized [fr

  19. Limited field investigation report for the 100-HR-2 Operable Unit

    International Nuclear Information System (INIS)

    1995-07-01

    This report summarizes the data collection and analysis activities conducted during the 100-HR-2 Operable Unit investigative phase and the associated qualitative risk assessment. The 100-HR-2 Operable Unit contains solid waste burial grounds, an ash pit, burn pits, electrical facilities, septic systems, and support facilities. All known and suspected areas of contamination were classified as solid waste burial grounds or low-priority waste sites based on the collective knowledge of the operable unit managers (representatives from the US Department of Energy, the US Environmental Protection Agency, and Washington State Department of Ecology during the preparation of the 100-HR-2 Operable Unit Work Plan (DOE-RL 1993f). Solid waste burial grounds were judged to pose sufficient risk(s), through one or more pathways, to require evaluation for an interim remedial measure as per the Hanford Past-Practice Strategy (DOE-RL 1991) and negotiations with the Department of Energy, US Environmental Protection Agency, and Washington State Department of Ecology. An interim remedial measure is intended to achieve remedies that are likely to lead to a final record of decision. Low-priority sites are those judged not to pose significant risk to require the streamlined evaluation. There were six low-priority waste sites and seven solid waste burial grounds identified. The purpose of this report is to: (1) provide a summary of site investigative activities; (2) refine the conceptual exposure model (as needed); (3) identify chemical- and location-specific corrective action requirements; and 4) provide a human health and ecological QRA associated with solid waste burial grounds

  20. Site-specific waste management instruction for the 100-KR-4 Operable Unit drilling

    International Nuclear Information System (INIS)

    Hadley, J.T.

    1996-07-01

    This site-specific waste management instruction provides guidance for the management of waste generated as a result of groundwater well installations in the 100-KR-4 Operable Unit (OU). The well installations are necessary to implement the Remedial Action (RA) option (pump-and-treat using ion exchange) to prevent discharge of hexavalent chromium at levels above those considered protective of aquatic life in the Columbia River and riverbed sediments