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  1. Standard Technical Specifications, Babcock and Wilcox plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The unproved STS were developed based on the, criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop proved plant-specific technical specifications. This report contains three volumes. This document, Volume 1 contains the Specifications for all chapters and sections of the improved STS

  2. Standard Technical Specifications, Babcock and Wilcox Plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) plants and documents the positions of the Nuclear Regulatory Commission (NRC) based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council. The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for developing improved plant-specific technical specifications by individual nuclear power plant licensees. This volume contains sections 3.4--3.9 which cover: Reactor coolant systems, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations

  3. Standard technical specifications: Babcock and Wilcox Plants. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Babcock & Wilcox Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS.

  4. Standard technical specifications: Babcock and Wilcox Plants. Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Babcock ampersand Wilcox Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  5. Standard technical specifications for Babcock and Wilcox pressurized water reactors

    International Nuclear Information System (INIS)

    1978-06-01

    The Standard Technical Specification (STS) has been structured for the broadest possible use on B and W NSSS plants currently being reviewed for an Operating License. Two separate and discrete containment specification sections are provided for each of the following containment types: Atmospheric, and Dual. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences. The format of the STS addresses the categories required by 10 CFR 50 and consists of six sections covering the areas of: Definitions, Safety Limits and Limiting Safety System Settings, Limiting Conditions for Operation, Surveillance Requirements, Design Features, and Administrative Controls

  6. Standard technical specifications for Babcock and Wilcox pressurized water reactors

    International Nuclear Information System (INIS)

    Virgilio, M.

    1979-07-01

    This Standard Technical Specification (STS) has been structured for the broadest possible use on B and W NSSS plants currently being reviewed for an Operating License. Two separate and discrete containment specification sections are provided for each of the following containment types: Atmospheric and Dual. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences. This revision of STS does not typically include requirements which may be added or revised as a result of the NRC staff's further review of the Three Mile Island incident

  7. Standard technical specifications - Babcock and Wilcox Plants: Bases (Sections 2.0-3.3). Volume 2, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This NUREG contains the improved Standard Technical Specifications (STS) for Babcock and Wilcox (B&W) plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the B&W Owners Group (BWOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency.

  8. Standard technical specifications: Babcock and Wilcox plants. Volume 3, Revision 1: Bases (Sections 3.4--3.9)

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Babcock and Wilcox Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  9. Review of technical specifications

    International Nuclear Information System (INIS)

    Bedrich, M.; Scholz, D.

    1980-01-01

    The present paper deals with position and function of technical specifications before and during the manufacturing of reactor components, their structure and reasons for specific regulations due to safety philosophy and explains the cooperation of supplier, manufacturer, utilities and supervisory organizations. (RW)

  10. HPCG Benchmark Technical Specification

    Energy Technology Data Exchange (ETDEWEB)

    Heroux, Michael Allen [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Dongarra, Jack [Univ. of Tennessee, Knoxville, TN (United States); Luszczek, Piotr [Univ. of Tennessee, Knoxville, TN (United States)

    2013-10-01

    The High Performance Conjugate Gradient (HPCG) benchmark [cite SNL, UTK reports] is a tool for ranking computer systems based on a simple additive Schwarz, symmetric Gauss-Seidel preconditioned conjugate gradient solver. HPCG is similar to the High Performance Linpack (HPL), or Top 500, benchmark [1] in its purpose, but HPCG is intended to better represent how today’s applications perform. In this paper we describe the technical details of HPCG: how it is designed and implemented, what code transformations are permitted and how to interpret and report results.

  11. ATR Technical Specification Upgrade Program

    International Nuclear Information System (INIS)

    McCracken, R.T.; Durney, J.L.; Freund, G.A.

    1990-01-01

    The Advanced Test Reactor (ATR) is a 250 MW, uranium-aluminum fueled test reactor which began full power operation in 1969. The initial operation was controlled by an Operating Limits document based on the original Safety Analysis Report. Additional safety bases were later developed to support Technical Specifications which were approved and implemented in 1977. The Technical Specifications which were initially developed with content and format specified in ANSI/ANS--15.1, ''The Development of Technical Specifications for Research Reactors.'' The safety basis documentation and the Technical Specifications have been updated as required to maintain them current with the ATR facility configuration. All revisions have been made with a content, format and style consistent with the original. A major, two-phase program to upgrade the content, format and style is in progress. This paper describes the first phase of this program

  12. ATR technical specification upgrade program

    International Nuclear Information System (INIS)

    McCraken, R.T.; Durney, J.L.; Freund, G.A.

    1990-01-01

    The Advanced Test Reactor (ATR) is a 250 MW, uranium-aluminum fueled test reactor which began full power operation in 1969. The initial operation was controlled by an Operating Limits document based on the original Safety Analysis Report. Additional safety bases were later developed to support Technical Specifications which were approved and implemented in 1977. The Technical Specifications were initially developed with the content and format specified in ANSI/ANS-15.1, The Development of Technical Specifications for Research Reactors. The safety basis documentation and the Technical Specifications have been updated as required to maintain them current with the ATR facility configuration. All revisions have been made with a content, format and style consistent with the original. A major, two-phase program to upgrade the content, format and style is in progress. This paper describes the first phase of this program

  13. Standard Technical Specifications, Westinghouse plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  14. Technical specifications, Hanford production reactors

    Energy Technology Data Exchange (ETDEWEB)

    Gilbert, W.D. [comp.

    1962-06-25

    These technical specifications are applicable to the eight operating production reactor facilities, B, C, D, DR, F, H, KE, and KW. Covered are operating and performance restrictions and administrative procedures. Areas covered by the operating and performance restrictions are reactivity, reactor control and safety elements, power level, temperature and heat flux, reactor fuel loadings, reactor coolant systems, reactor confinement, test facilities, code compliance, and reactor scram set points. Administrative procedures include process control procedures, training programs, audits and inspections, and reports and records.

  15. Babcock and Wilcox advanced PWR development

    International Nuclear Information System (INIS)

    Kulynych, G.E.; Lemon, J.E.

    1986-01-01

    The Babcock and Wilcox 600 MWe PWR design is discussed. Main features of the new B-600 design are improvements in reactor system configuration, glandless coolant pumps, safety features, core design and steam generators

  16. Technical specification improvement through safety margin considerations

    International Nuclear Information System (INIS)

    Howard, R.C.; Jansen, R.L.

    1986-01-01

    Westinghouse has developed an approach for utilizing safety analysis margin considerations to improve plant operability through technical specification revision. This approach relies on the identification and use of parameter interrelations and sensitivities to identify acceptable operating envelopes. This paper summarizes technical specification activities to date and presents the use of safety margin considerations as another viable method to obtain technical specification improvement

  17. Central Solenoid Insert Technical Specification

    Energy Technology Data Exchange (ETDEWEB)

    Martovetsky, Nicolai N [ORNL; Smirnov, Alexandre [ORNL

    2011-09-01

    The US ITER Project Office (USIPO) is responsible for the ITER central solenoid (CS) contribution to the ITER project. The Central Solenoid Insert (CSI) project will allow ITER validation the appropriate lengths of the conductors to be used in the full-scale CS coils under relevant conditions. The ITER Program plans to build and test a CSI to verify the performance of the CS conductor. The CSI is a one-layer solenoid with an inner diameter of 1.48 m and a height of 4.45 m between electric terminal ends. The coil weight with the terminals is approximately 820 kg without insulation. The major goal of the CSI is to measure the temperature margin of the CS under the ITER direct current (DC) operating conditions, including determining sensitivity to load cycles. Performance of the joints, ramp rate sensitivity, and stability against thermal or electromagnetic disturbances, electrical insulation, losses, and instrumentation are addressed separately and therefore are not major goals in this project. However, losses and joint performance will be tested during the CSI testing campaign. The USIPO will build the CSI that will be tested at the Central Solenoid Model Coil (CSMC) Test Facility at the Japan Atomic Energy Agency (JAEA), Naka, Japan. The industrial vendors (the Suppliers) will report to the USIPO (the Company). All approvals to proceed will be issued by the Company, which in some cases, as specified in this document, will also require the approval of the ITER Organization. Responsibilities and obligations will be covered by respective contracts between the USIPO, called Company interchangeably, and the industrial Prime Contractors, called Suppliers. Different stages of work may be performed by more than one Prime Contractor, as described in this specification. Technical requirements of the contract between the Company and the Prime Contractor will be covered by the Fabrication Specifications developed by the Prime Contractor based on this document and approved by

  18. Improved technical specifications for Korean NPP

    International Nuclear Information System (INIS)

    Ryu, J. D.; Lee, D. H.; Seong, C. K.

    2002-01-01

    PWRs use Technical Specifications(Tech. Spec.) to ensure safe operation of the plant. Recently, many efforts were made to improve Tech. Spec. and as a result, Improved Standard Technical Specifications(ISTS) have been developed. Korean NPP technical specifications were converted to ISTS format. KAERI also provided supporting documents for technical specification conversion including mark-up's and description of changes. This paper describes and summarizes the results of implementation of ISTS for Korean NPP. The new Tech. Spec. will improve safety of Korean NPP

  19. Standard technical specifications combustion engineering plants

    International Nuclear Information System (INIS)

    1992-09-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS) for Combustion Engineering Plants. The improved STS wee developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Sections 3.4--3.9 of the improved STS

  20. Technical specification optimization program - engineered safety features

    International Nuclear Information System (INIS)

    Andre, G.R.; Jansen, R.L.

    1986-01-01

    The Westinghouse Technical Specification Program (TOP) was designed to evaluate on a quantitative basis revisions to Nuclear Power Plant Technical Specifications. The revisions are directed at simplifying plant operation, and reducing unnecessary transients, shutdowns, and manpower requirements. In conjunction with the Westinghouse Owners Group, Westinghouse initiated a program to develop a methodology to justify Technical Specification revisions; particularly revisions related to testing and maintenance requirements on plant operation for instrumentation systems. The methodology was originally developed and applied to the reactor trip features of the reactor protection system (RPS). The current study further refined the methodology and applied it to the engineered safety features of the RPS

  1. Technical specification for vacuum systems

    International Nuclear Information System (INIS)

    Khaw, J.

    1987-01-01

    The vacuum systems at the Stanford Linear Accelerator Center (SLAC) are primarily of all-metal construction and operate at pressures from 10 -5 to 10 -11 Torr. The primary gas loads during operation result from thermal desorption and beam-induced desorption from the vacuum chamber walls. These desorption rates can be extremely high in the case of hydrocarbons and other contaminants. These specifications place a major emphasis on eliminating contamination sources. The specifications and procedures have been written to insure the cleanliness and vacuum integrity of all SLAC vacuum systems, and to assist personnel involved with SLAC vacuum systems in choosing and designing components that are compatible with existing systems and meet the quality and reliability of SLAC vacuum standards. The specification includes requirements on design, procurement, fabrication, chemical cleaning, clean room practices, welding and brazing, helium leak testing, residual gas analyzer testing, bakeout, venting, and pumpdown. Also appended are specifications regarding acceptable vendors, isopropyl alcohol, bakeable valve cleaning procedure, mechanical engineering safety inspection, notes on synchrotron radiation, and specifications of numerous individual components

  2. Technical specification for vacuum systems

    Energy Technology Data Exchange (ETDEWEB)

    Khaw, J. (ed.)

    1987-01-01

    The vacuum systems at the Stanford Linear Accelerator Center (SLAC) are primarily of all-metal construction and operate at pressures from 10/sup -5/ to 10/sup -11/ Torr. The primary gas loads during operation result from thermal desorption and beam-induced desorption from the vacuum chamber walls. These desorption rates can be extremely high in the case of hydrocarbons and other contaminants. These specifications place a major emphasis on eliminating contamination sources. The specifications and procedures have been written to insure the cleanliness and vacuum integrity of all SLAC vacuum systems, and to assist personnel involved with SLAC vacuum systems in choosing and designing components that are compatible with existing systems and meet the quality and reliability of SLAC vacuum standards. The specification includes requirements on design, procurement, fabrication, chemical cleaning, clean room practices, welding and brazing, helium leak testing, residual gas analyzer testing, bakeout, venting, and pumpdown. Also appended are specifications regarding acceptable vendors, isopropyl alcohol, bakeable valve cleaning procedure, mechanical engineering safety inspection, notes on synchrotron radiation, and specifications of numerous individual components. (LEW)

  3. Technical requirements specification for tank waste retrieval

    Energy Technology Data Exchange (ETDEWEB)

    Lamberd, D.L.

    1996-09-26

    This document provides the technical requirements specification for the retrieval of waste from the underground storage tanks at the Hanford Site. All activities covered by this scope are conducted in support of the Tank Waste Remediation System (TWRS) mission.

  4. Technical specifications: Health Physics Research Reactor

    International Nuclear Information System (INIS)

    1986-03-01

    These technical specifications define the key limitations that must be observed for safe operation of the Health Physics Research Reactor (HPRR) and an envelope of operation within which there is assurance that these limits will not be exceeded

  5. Technical specifications for the bulk shielding reactor

    International Nuclear Information System (INIS)

    1986-05-01

    This report provides information concerning the technical specifications for the Bulk Shielding Reactor. Areas covered include: safety limits and limiting safety settings; limiting conditions for operation; surveillance requirements; design features; administrative controls; and monitoring of airborne effluents. 10 refs

  6. Standard technical specifications, Westinghouse Plants: Specifications. Volume 1, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency.

  7. Procedures for evaluating technical specifications (PETS)

    International Nuclear Information System (INIS)

    Samanta, P.K.; Boccio, J.L.; Vesely, W.E.

    1987-01-01

    In this paper, aspects of technical specifications relating to Generic Issues B-56 and B-61 are discussed from a risk-standpoint. These primarily deal with the risk issues associated with (1) adaptive diesel test requirements/surveillance test intervals, and (2) the effectiveness of cumulative outage time requirements for controlling downtime risk. Risk and reliability approaches are presented which (1) allow risk-acceptable test intervals to be determined for any diesel and (2) show the potential risk-control capability of prescribed allowed cumulative outage times. This work was conducted through NRC's Procedures for Evaluating Technical Specifications (PETS) Program. The overall objective of this program is to develop and demonstrate methodologies that utilize risk insights and reliability techniques for evaluating the scope, detailed requirements, and safety impact of plant technical specifications

  8. Technical specifications for PWR secondary water chemistry

    International Nuclear Information System (INIS)

    Weeks, J.R.; van Rooyen, D.

    1977-08-01

    The bases for establishing Technical Specifications for PWR secondary water chemistry are reviewed. Whereas extremely stringent control of secondary water needs to be maintained to prevent denting in some units, sound bases for establishing limits that will prevent stress corrosion, wastage, and denting do not exist at the present time. This area is being examined very thoroughly by industry-sponsored research programs. Based on the evidence available to date, short term control limits are suggested; establishment of these or other limits as Technical Specifications is not recommended until the results of the research programs have been obtained and evaluated

  9. Risk management through dynamic technical specifications

    International Nuclear Information System (INIS)

    Klopp, George T.; Petersen, Thomas A.

    2004-01-01

    The wide deployment of plant specific probabilistic risk assessments for nuclear power plants has provided the means to effect a fresh risk management perspective and a fresh, risk based, regulatory outlook on nuclear power. There has been a great deal of conversation on risk based regulation within the U. S. nuclear power industry but, curiously, very little on effective risk management. This paper proposes a means to link the two subjects through the plant Technical Specifications. A revised concept for Technical Specifications is suggested which is based on deterministic analyses and probabilistic risk assessments for each plant. The revised Technical Specifications would consider, on a real-time basis, the exact state of the plant in terms of the status of key components and systems. It would depict current plant risk levels and compare those levels to the desired and limiting (alert/action) levels. It would advise the plant operator on the risk impact of proposed actions through a simple query system and illustrate the impact of such actions on plant status relative to designated risk values. The basis for the proposed approach lies in realistic deterministic plant analyses and probabilistic risk assessment (PRA) deployment tools being developed, in parallel, by a number of parties in the U.S. today. These PRAs are based primarily on the existing plant responses to Generic Letter 88-20, 'Individual Plant Examinations' (IPEs). Each of these tools allows the plant operator to input, on a real-time basis, the status of key equipment and systems. The tools then provide explicit illustrations of dependency effects; updated, 'real-time' risk status indications such as core damage frequency; and, in some cases, allow the operator to assess the risk impact of removing from service selected components for maintenance or testing. These systems generally operate on personal computers and provide nearly instantaneous responses to plant queries. Moving from these tools to

  10. RELAP5/MOD2 assessment at Babcock and Wilcox

    International Nuclear Information System (INIS)

    Nithianandan, C.K.; Shah, N.H.; Schomaker, R.J.; Turk, C.

    1986-01-01

    Babcock and Wilcox (B and W) has been working with the code developers at EG and G Idaho, Inc. and the NRC assessing the RELAP5/MOD2 computer code by simulating selected separate effects tests. The purpose of this B and W Owners Group-sponsored assessment was to evaluate RELAP5/MOD2 for use in design calculations for the MIST and OTIS integral system tests and in predicting pressurized water reactor (PWR) transients. B and W evaluated various versions of the code and made recommendations to improve code performance. As a result, the currently released version (Cycle 36.1) has been improved considerably over earlier versions. However, further refinements to some of the constitutive models may still be needed to further improve specific predictive capabilities of RELAP5/MOD2

  11. Technical specifications for the Pajarito Site Critical Experiments Facility

    International Nuclear Information System (INIS)

    Malenfant, R.E.; Paxton, H.C.

    1980-12-01

    This document is to satisfy the requirement for technical specifications spelled out in DOE Manual Chapter 0540, Safety of DOE-Owned Reactors. Technical specifications are defined in Sec. 0540-048, and the requirement for them appears in Sec. 0540-015. The following technical specifications update the document, Technical Specifications for the Pajarito Site Critical Experiments Facility

  12. Obituary: Horace Welcome Babcock, 1912-2003

    Science.gov (United States)

    Vaughan, Arthur Harris

    2003-12-01

    Horace Welcome Babcock died in Santa Barbara, California on 29 August 2003, fifteen days short of his ninety-first birthday. An acclaimed authority on solar and stellar magnetism and the originator of ingenious advances in astronomical instrumentation in his earlier career, he served as Director of Mount Wilson and Palomar (later Hale) Observatories from 1964 until his retirement in 1978. The founding of the Carnegie Institution of Washington's Las Campanas Observatory in Chile was the culmination of his directorship. Horace was born in Pasadena California on 13 September 1912, the only child of Harold Delos Babcock and Mary G. Henderson. His father, an electrical engineer and physicist by training, had been hired by George Ellery Hale to work at the recently founded Mount Wilson Solar Observatory beginning in 1909. Thus Horace spent much of his boyhood on Mount Wilson in the company of astronomers. Horace developed an early interest in astronomy, worked as a volunteer solar observer at Mount Wilson and published his first paper in 1932, with his father. He was fascinated by fine mechanisms and by optical and electrical instruments. After graduating from Caltech with a degree in structural engineering in 1934, he earned his PhD in astronomy at Lick Observatory in 1938. His dissertation provided the first measurement of the rotational velocity curve and a derivation of the mass-to-luminosity ratio for M31; this work is still cited in reviews of the study of ``dark matter." Horace served as a research assistant at Lick Observatory (1938 39) and an Instructor at the University of Chicago's McDonald and Yerkes Observatories (1939--41) under Otto Struve. He undertook radar-related wartime electronics work at the MIT Radiation Laboratory (1941 42) and then worked on aircraft rocket launchers as part of the Caltech Rocket Project (1942 45). This project brought him into contact with Ira S. Bowen, head of the project's Photographic Division. Impressed with his knowledge of

  13. Optimisation of technical specifications using probabilistic methods

    International Nuclear Information System (INIS)

    Ericsson, G.; Knochenhauer, M.; Hultqvist, G.

    1986-01-01

    During the last few years the development of methods for modifying and optimising nuclear power plant Technical Specifications (TS) for plant operations has received increased attention. Probalistic methods in general, and the plant and system models of probabilistic safety assessment (PSA) in particular, seem to provide the most forceful tools for optimisation. This paper first gives some general comments on optimisation, identifying important parameters and then gives a description of recent Swedish experiences from the use of nuclear power plant PSA models and results for TS optimisation

  14. Technical Specification action statements requiring shutdown

    International Nuclear Information System (INIS)

    Mankamo, T.; Kim, I.S.; Samanta, P.K.

    1993-11-01

    When safety systems fail during power operation, the limiting conditions for operation (LCOs) and associated action statements of technical specifications typically require that the plant be shut down within the limits of allowed outage time (AOT). However, when a system needed to remove decay heat, such as the residual heat removal (RHR) system, is inoperable or degraded, shutting down the plant may not necessarily be preferable, from a risk perspective, to continuing power operation over a usual repair time, giving priority to the repairs. The risk impact of the basic operational alternatives, i.e., continued operation or shutdown, was evaluated for failures in the RHR and standby service water (SSW) systems of a boiling-water reactor (BWR) nuclear power plant. A complete or partial failure of the SSW system fails or degrades not only the RHR system but other front-line safety systems supported by the SSW system. This report presents the methodology to evaluate the risk impact of LCOs and associated AOT; the results of risk evaluation from its application to the RHR and SSW systems of a BWR; the findings from the risk-sensitivity analyses to identify alternative operational policies; and the major insights and recommendations to improve the technical specifications action statements

  15. Uranium silicide activities at Babcock and Wilcox

    International Nuclear Information System (INIS)

    Noel, W.W.; Freim, J.B.

    1983-01-01

    Babcock and Wilcox, Naval Nuclear Fuel Division (NNFD) in conjunction with Argonne National Laboratory (ANL) is actively involved in the Reduced Enrichment Research Test Reactor (RERTR) Program to produce low enriched fuel elements for research reactors. B and W and ANL have undertaken a joint effort in which NNFD will fabricate two low enriched uranium (LEU), Oak Ridge Reactor (ORR) elements with uranium silicide fuel furnished by ANL. These elements are being fabricated for irradiation testing at Oak Ridge National Laboratory (ORNL). Concurrently with this program, NNFD is developing and implementing the uranium silicide and uranium aluminide fuel fabrication technology. NNFD is fabricating the uranium silicide ORR elements in a two-phase program, Development and Production. To summarize: 1. Full size fuel plates can be made with U 3 SiAl but the fabricator must prevent oxidation of the compact prior to hot roll bonding; 2. Providing the ANL U 3 Si x irradiation results are successful, NNFD plans to provide two ORR elements during February 1983; 3. NNFD is developing and implementing U 3 Si x and UAI x fuel fabrication technology to be operational in 1983; 4. NNFD can supply U 3 O 8 high enriched uranium (HEU) or low enriched uranium (LEU) research reactor elements; 5. NNFD is capable of providing high quality, cost competitive LEU or HEU research reactor elements to meet the needs of the customer

  16. Risk-informed approach in US-APWR technical specifications

    International Nuclear Information System (INIS)

    Saji, Etsuro; Tanaka, Futoshi; Kuroiwa, Katsuya; Kawai, Katsunori

    2009-01-01

    The Risk-Managed Technical Specifications and the Surveillance Frequency Control Program have been adopted in the US-APWR Technical Specifications. These risk-informed approaches are unique among the technical specifications for the advanced light water reactor designs adopted by planned nuclear power stations in the United States. (author)

  17. Technical specifications report. Auditing and financial system

    Energy Technology Data Exchange (ETDEWEB)

    Feldmiller, W.H.

    1980-01-01

    The U.S. Geological Survey's Conservation Division is responsible for regulating the development of mineral resources on Federal leased lands and Indian reservations and for collecting the rents and royalties due from these lands. The objective of the Division is to reduce the regulatory burden on industry while effectively and efficiently discharging its responsibility. The development of the Improved Royalty Management Program (IRMP) is a major step in accomplishing these goals. The completion of the technical design of the first phase in the development of the IRMP is reported. How the Auditing and Financial System (AFS) will operate from a data-processing viewpoint is described, as well as how the system will perform the functions identified in the AFS Functional Specifications Report. Information is provided on the following: Systems Components (hardware, software, organizations, and security; Data Base Design; Overall System Flow; Batch Processes; On-line Processes; System Testing; Conversion; and Resource Requirements (performance, computer storage; timings, terminals, transmission, datapoint configuration; personnel).

  18. Babcock Redux: An Amendment of Babcock's Schematic of the Sun's Magnetic Cycle

    Science.gov (United States)

    Moore, Ronald L.; Cirtain, Jonathan W.; Sterling, Alphonse C.

    2017-08-01

    We amend Babcock's original scenario for the global dynamo process that sustains the Sun's 22-year magnetic cycle. The amended scenario fits post-Babcock observed features of the magnetic activity cycle and convection zone, and is based on ideas of Spruit & Roberts (1983, Nature, 304, 401) about magnetic flux tubes in the convection zone. A sequence of four schematic cartoons lays out the proposed evolution of the global configuration of the magnetic field above, in, and at the bottom of the convection zone through sunspot Cycle 23 and into Cycle 24. Three key elements of the amended scenario are: (1) as the net following-polarity magnetic field from the sunspot-region Ω-loop fields of an ongoing sunspot cycle is swept poleward to cancel and replace the opposite-polarity polar-cap field from the previous sunspot cycle, it remains connected to the ongoing sunspot cycle's toroidal source-field band at the bottom of the convection zone; (2) topological pumping by the convection zone's free convection keeps the horizontal extent of the poleward-migrating following-polarity field pushed to the bottom, forcing it to gradually cancel and replace old horizontal field below it that connects the ongoing-cycle source-field band to the previous-cycle polar-cap field; (3) in each polar hemisphere, by continually shearing the poloidal component of the settling new horizontal field, the latitudinal differential rotation low in the convection zone generates the next-cycle source-field band poleward of the ongoing-cycle band. The amended scenario is a more-plausible version of Babcock's scenario, and its viability can be explored by appropriate kinematic flux-transport solar-dynamo simulations. A paper giving a full description of our dynamo scenario is posted on arXiv (http://arxiv.org/abs/1606.05371).This work was funded by the Heliophysics Division of NASA's Science Mission Directorate through the Living With a Star Targeted Research and Technology Program and the Hinode

  19. Technical Submission Form: Technical Specification of a Wave Energy Farm.

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, Jesse D.; Kim Nielsen; Ben Kennedy; Bull, Diana L; Costello, Ronan Patrick; Jochem Weber

    2017-04-01

    The Wave - SPARC project developed the Technology Performance Level (TPL) assessment procedure based on a rigorous Systems Engineering exercise. The TPL assessment allows a whole system evaluation of Wave Energy Conversion Technology by measuring it against the requirements determined through the Systems Engineering exercise. The TPL assessment is intended to be useful in technology evaluation; in technology innovation; in allocation of public or priva te investment, and; in making equipment purchasing decisions. This Technical Submission Form (TSF) serves the purpose of collecting relevant and complete information, in a technology agnostic way, to allow TPL assessment s to be made by third party assessor s. The intended usage of this document is that the organization or people that are performing the role of developers or promoters of a particular technology will use this form to provide the information necessary for the organization or people who are perf orming the assessor role to use the TPL assessment.

  20. BABCOCK & WILCOX CYCLONE VITRIFICATION TECHNOLOGY FOR CONTAMINATED SOIL

    Science.gov (United States)

    The Babcock & Wilcox 6 million Btu/hr pilot cyclone furnace was successfully used in a 2-yr Superfund Innovative Technology Evaluation (SITE) Emerging Technology project to melt and vitrify an EPA Synthetic Soil Matrix (SSM) spiked with 7,000 ppm lead, 1,000 ppm cadmium, and 1,5...

  1. Superconducting performance of CEBAF/Cornell prototype cavities fabricated by Babcock and Wilcox

    International Nuclear Information System (INIS)

    Bensiek, W.; Dateo, J.; Hager, J.; Pruitt, W.; Williams, P.; Padamsee, H.

    1987-01-01

    Babcock and Wilcox (B and W) is participating in the development of an industrial production capability for CEBAF superconducting rf accelerator cavities. Five-cell elliptical cavities of the Cornell design (operating frequency 1500 MHz) have been fabricated at B and W and tested at the Cornell Laboratory of Nuclear Studies (LNS). Performance specifications (accelerating field of 5 MeV/m at a residual quality factor of 3 x 10 9 ) have been exceeded by comfortable margins in the first two prototypes. A comparison between the performance of cavities fabricated from niobium of different purities is presented

  2. Probabilistic safety assessment improves surveillance requirements in technical specifications

    International Nuclear Information System (INIS)

    Cepin, M.; Mavko, B.

    1997-01-01

    Probabilistic Safety Assessment is widely becoming the standard method for assessing, maintaining, assuring and improving the nuclear power plant safety. To achieve one of its many potential benefits, the optimization approach of surveillance requirements in technical specifications was developed. Surveillance requirements in technical specifications define the surveillance test intervals for the equipment to be tested and the testing strategy. This optimization approach based mainly on probabilistic safety assessment results consists of three levels: component level, system level and plant level. The application of this optimization approach on system level has shown that the risk based surveillance requirements differ from existing ones in technical specifications

  3. HFBR: Review of the technical specifications against the FSAR

    International Nuclear Information System (INIS)

    Rao, D.V.; Boss, S.B.; Claiborne, E.R.; Darby, J.L.; Clark, R.A.

    1990-01-01

    The purpose of this review is to determine the adequacy of the High Flux Beam Reactor (HFBR) Technical Specifications for 40 MW operation by comparison with the HFBR Final Safety Analysis Report, particularly the accident analyses chapter. Specifically, the Technical Specifications were compared against the Design Basis Accident (DBA) Analyses presented in the Addendum to the HFBR FSAR for 60 MW Operation. The 60 MW DBA analyses was used since it is more current and complete than the analyses presented in the original FSAR which is considered obsolete. A listing of the required systems and equipment was made for each of the accidents analyzed. Additionally, the Technical Specification instrument setpoints were compared to the DBA analyses parametric values. Also included in this review was a comparison of the Technical Specification Bases against the FSAR and the identification of any differences. The HFBR Operations Procedures Manual (OPM) was also reviewed for any inconsistencies between the FSAR or the Technical Specifications. Upon completion of this review it was determined that the Technical Specifications are well written and the items commented on should not delay the low power restart (40 MW). Additionally, the OPM is also well written and does not require further modification before restart

  4. Production of leu high density fuels at Babcock and Wilcox

    International Nuclear Information System (INIS)

    Freim, J.B.

    1983-01-01

    A large number of fuel elements of all types are produced for both international and domestic customers by Nuclear Fuel Division of Babcock and Wilcox. A brief history of the division, included previous and present research reactor fuel element fabrication experience is discussed. The manufacturing facilities are briefly described. The fabrication of LEU fuels and economic analysis of the production are included. (A.J.)

  5. Babcock and Wilcox Canada steam generators past, present and future

    International Nuclear Information System (INIS)

    Smith, J.C.

    1998-01-01

    The steam generators in all of the domestic CANDU Plants, and most of the foreign CANDU plants, were supplied by Babcock and Wilcox Canada, either on their own or in co-operation with local manufacturers. More than 200 steam generators have been supplied. In addition, Babcock and Wilcox Canada has taken the technology which evolved out of the CANDU steam generators and has adapted the technology to supply of replacement steam generators for PWR's. There is enough history and operating experience, plus laboratory experience, to point to the future directions which will be taken in steam generator design. This paper documents the steam generators which have been supplied, the experience in operation and maintenance, what has worked and not worked, and how the design, materials, and operating and maintenance philosophy have evolved. The paper also looks at future requirements in the market, and the continuing research and product development going on at Babcock and Wilcox to address the future steam generator requirements. (author)

  6. Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

    International Nuclear Information System (INIS)

    Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L.

    1978-10-01

    The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems

  7. Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

    Energy Technology Data Exchange (ETDEWEB)

    Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L. (eds.)

    1978-10-01

    The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems.

  8. Methodology for risk-based analysis of technical specifications

    International Nuclear Information System (INIS)

    Vesely, W.E.; Gaertner, J.P.; Wagner, D.P.

    1985-01-01

    Part of the effort by EPRI to apply probabilistic risk assessment methods and results to the solution of utility problems involves the investigation of methods for risk-based analysis of technical specifications. The culmination of this investigation is the SOCRATES computer code developed by Battelle's Columbus Laboratories to assist in the evaluation of technical specifications of nuclear power plants. The program is designed to use information found in PRAs to re-evaluate risk for changes in component allowed outage times (AOTs) and surveillance test intervals (STIs). The SOCRATES program is a unique and important tool for technical specification evaluations. The detailed component unavailability model allows a detailed analysis of AOT and STI contributions to risk. Explicit equations allow fast and inexpensive calculations. Because the code is designed to accept ranges of parameters and to save results of calculations that do not change during the analysis, sensitivity studies are efficiently performed and results are clearly displayed

  9. Risk-based technical specifications program: Site interview results

    International Nuclear Information System (INIS)

    Andre, G.R.; Baker, A.J.; Johnson, R.L.

    1991-08-01

    The Electric Power Research Institute and Pacific Gas and Electric Company are sponsoring a program directed at improving Technical Specifications using risk-based methods. The major objectives of the program are to develop risk-based approaches to improve Technical Specifications and to develop an Interactive Risk Advisor (IRA) prototype. The IRA is envisioned as an interactive system that is available to plant personnel to assist in controlling plant operation. Use of an IRA is viewed as a method to improve plant availability while maintaining or improving plant safety. In support of the program, interviews were conducted at several PWR and BWR plant sites, to elicit opinions and information concerning risk-based approaches to Technical Specifications and IRA requirements. This report presents the results of these interviews, including the functional requirements of an IRA. 2 refs., 6 figs., 2 tabs

  10. Operating experience feedback report: Technical specifications: Commercial power reactors

    International Nuclear Information System (INIS)

    O'Reilly, P.D.; Plumlee, G.L. III.

    1989-03-01

    This report documents a trends and patterns analysis of technical specification (TS)-related licensee event reports (LERs) conducted by the Nuclear Regulatory Commission's (NRC's) Office for Analysis and Evaluation of Operational Data (AEOD). The objectives of this analysis were (1) to identify and catalog technical specification-related LERs, (2) to categorize and evaluate the events reported in these a LERs, (3) to identify any issues arising from the evaluation which appear to have generic safety significance, or which relate to the on-going Technical Specification Improvement Program, and (4) to trend the results obtained from the analysis of the data obtained in (1) through (3). 9 refs., 9 figs., 22 tabs

  11. Status of LEU programs at Babcock and Wilcox

    International Nuclear Information System (INIS)

    McCormick, G.L.

    1995-01-01

    The primary focus of Babcock and Wilcox's (B and W) Research and Test Reactor Fuel Element Facility's (RTRFE) most recent activities is to continue to improve its successful LEU fuel element production process. This is being done by expanding its R and D efforts (expenditures for CFY 92 are twice that of CFY 91) and applying statistical process control to its production processes. B and W's total commitment to quality and integrity has led to the successful fabrication of silicide production elements for five (5) reactors and development/qualification elements for four (4) other reactors. The results of B and W's recent production and development efforts are highlighted in this report. (author)

  12. Standard Technical Specifications, General Electric plants, BWR/4

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

  13. Standard Technical Specifications, General Electric Plants, BWR/6

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  14. Standard Technical Specifications, General Electric plants, BWR/4

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  15. 33 CFR 157.12d - Technical specifications.

    Science.gov (United States)

    2010-07-01

    ... must be designed so a discharge of dirty-ballast or other oil-contaminated water from the cargo tank...) POLLUTION RULES FOR THE PROTECTION OF THE MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING OIL IN BULK Design, Equipment, and Installation § 157.12d Technical specifications. (a) Oil discharge monitoring and...

  16. 75 FR 50009 - Babcock & Wilcox Nuclear Operations Group, Inc.; Establishment of Atomic Safety and Licensing Board

    Science.gov (United States)

    2010-08-16

    ... COMMISSION Babcock & Wilcox Nuclear Operations Group, Inc.; Establishment of Atomic Safety and Licensing... Safety and Licensing Board (Board) is being established to preside over the following proceeding: Babcock & Wilcox Nuclear Operations Group, Inc. (Lynchburg, VA Facility). This proceeding concerns an Order...

  17. The Role of Magnetic Buoyancy in a Babcock-Leighton Type Solar ...

    Indian Academy of Sciences (India)

    tribpo

    J. Astrophys. Astr. (2000) 21, 381-385. The Role of Magnetic Buoyancy in a Babcock-Leighton. Type Solar Dynamo. Dibyendu Nandy* & Arnab Rai Choudhuri, ... model of the solar dynamo—which draws inspiration from the Babcock- .... are still of rather exploratory nature, since none of the authors have succeeded yet.

  18. Standard technical specifications for General Electric boiling water reactors

    International Nuclear Information System (INIS)

    1979-08-01

    This Standard Technical Specification (STS) has been structured for the broadest possible use on General Electric plants currently being reviewed for an Operating License. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. This revision of the GE-STS does not typically include requirements which may be added or revised as a result of the NRC staff's further review of the Three Mile Island incident

  19. Technical specifications for mechanical recycling of agricultural plastic waste.

    Science.gov (United States)

    Briassoulis, D; Hiskakis, M; Babou, E

    2013-06-01

    Technical specifications appropriate for the recycling of agricultural plastic wastes (APWs), widely accepted by the recycling industry were developed. The specifications establish quality standards to be met by the agricultural plastics producers, users and the agricultural plastic waste management chain. They constitute the base for the best economical and environmental valorisation of the APW. The analysis of the APW streams conducted across Europe in the framework of the European project "LabelAgriWaste" revealed the inherent characteristics of the APW streams and the inherent constraints (technical or economical) of the APW. The APW stream properties related to its recycling potential and measured during pilot trials are presented and a subsequent universally accepted simplified and expanded list of APW recycling technical specifications is proposed and justified. The list includes two sets of specifications, applied to two different quality categories of recyclable APW: one for pellet production process ("Quality I") and another one for plastic profile production process ("Quality II"). Parameters that are taken into consideration in the specifications include the APW physical characteristics, contamination, composition and degradation. The proposed specifications are focused on polyethylene based APW that represents the vast majority of the APW stream. However, the specifications can be adjusted to cover also APW of different materials (e.g. PP or PVC) that are found in very small quantities in protected cultivations in Europe. The adoption of the proposed specifications could transform this waste stream into a labelled commodity traded freely in the market and will constitute the base for the best economical and environmental valorisation of the APW. Copyright © 2013 Elsevier Ltd. All rights reserved.

  20. Standard technical specifications for Westinghouse pressurized water reactors

    International Nuclear Information System (INIS)

    Wagner, P.C.

    1979-07-01

    This Standard Technical Specification (STS) has been structured for the broadest possible use on Westinghouse plants currently being reviewed for an Operating License. Accordingly, the document contains specifications applicable to plants with (1) either 3 or 4 loops and (2) with and without loop stop valves. In addition, four separate and discrete containment specification sections are provided for each of the following containment types: Atmospheric, Ice Condenser, Sub-Atmospheric, and Dual. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences. This revision of the STS does not typically include requirements which may be added or revised as a result of the NRC staff's further review of the Three Mile Island incident

  1. Savannah River Site production reactor technical specifications. K Production Reactor

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    These technical specifications are explicit restrictions on the operation of the Savannah River Site K Production Reactor. They are designed to preserve the validity of the plant safety analysis by ensuring that the plant is operated within the required conditions bounded by the analysis, and with the operable equipment that is assumed to mitigate the consequences of an accident. Technical specifications preserve the primary success path relied upon to detect and respond to accidents. This report describes requirements on thermal-hydraulic limits; limiting conditions for operation and surveillance for the reactor, power distribution control, instrumentation, process water system, emergency cooling and emergency shutdown systems, confinement systems, plant systems, electrical systems, components handling, and special test exceptions; design features; and administrative controls.

  2. USER SPECIFICATIONS FOR PRESSURE VESSELS AND TECHNICAL INTEGRITY

    Directory of Open Access Journals (Sweden)

    K.S. Johnston

    2012-01-01

    Full Text Available

    ENGLISH ABSTRACT: Specifications translated from user requirements are prescribed in an attempt to capture and incorporate best practices with regards to the design, fabrication, testing, and operation of pressure vessels. The question as to whether these requirements affect the technical integrity of pressure vessels is often a subjective matter. This paper examines typical user requirement specifications against technical integrity of pressure vessels.
    The paper draws on a survey of a convenience sample of practising engineers in a diversified petrochemical company. When compared with failures on selected pressure vessels recorded by Phillips and Warwick, the respondent feedback confirms the user specifications that have the highest impact on technical integrity.

    AFRIKAANSE OPSOMMING: Gebruikersbehoeftes word saamgevat in spesifikasies wat lei tot goeie praktyk vir ontwerp, vervaarding, toetsing en bedryf van drukvate. Subjektiwiteit van die gebruikersbehoeftes mag soms die tegniese integriteit van ‘n drukvat beinvloed.
    Die navorsing maak by wyse van monsterneming gebruik van die kennis van ingenieurs wat werk in ‘n gediversifiseerde petrochemiese bedryf. Die terugvoering bevestig dat bogenoemde spesifikasies inderdaad die grootste invloed het op tegniese integriteit.

  3. Standard technical specifications: Combustion engineering plants. Volume 1, Revision 1: Specifications

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Combustion Engineering Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS.

  4. Standard technical specifications: General Electric plants, BWR/4. Volume 1, Revision 1: Specifications

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS.

  5. Technical and quality assurance specifications for dosimetry services

    International Nuclear Information System (INIS)

    1989-01-01

    The Canadian Atomic Energy Control Board (AECB) requires its licensees to establish a program to determine or estimate the radiation doses received by workers exposed to radiation as a result of the licensee's activities. The determination of radiation dose is a two-part process. First a measurement is made; then this measurement is used in a dosimetric model to calculate the dose. This document is concerned only with the first step of the process. It gives guidance on the technical specifications for dosimetry services and the quality assurance program that provides confidence that these specifications are achieved. (L.L.)

  6. Optimization of technical specifications by use of probabilistic methods

    International Nuclear Information System (INIS)

    Laakso, K.

    1990-01-01

    The Technical Specifications of a nuclear power plant specify the limits for plant operation from the safety point of view. These operational safety rules were originally defined on the basis of deterministic analyses and engineering judgement. As experience has accumulated, it has proved necessary to consider problems and make specific modifications in these rules. Developments in probabilistic safety assessment have provided a new tool to analyse, present and compare the risk effects of proposed rule modificatons. The main areas covered in the project are operational decisions in failure situations, preventive maintenance during power operation and surveillance tests of standby safety systems. (author)

  7. Mental Fatigue Impairs Soccer-Specific Physical and Technical Performance.

    Science.gov (United States)

    Smith, Mitchell R; Coutts, Aaron J; Merlini, Michele; Deprez, Dieter; Lenoir, Matthieu; Marcora, Samuele M

    2016-02-01

    To investigate the effects of mental fatigue on soccer-specific physical and technical performance. This investigation consisted of two separate studies. Study 1 assessed the soccer-specific physical performance of 12 moderately trained soccer players using the Yo-Yo Intermittent Recovery Test, Level 1 (Yo-Yo IR1). Study 2 assessed the soccer-specific technical performance of 14 experienced soccer players using the Loughborough Soccer Passing and Shooting Tests (LSPT, LSST). Each test was performed on two occasions and preceded, in a randomized, counterbalanced order, by 30 min of the Stroop task (mentally fatiguing treatment) or 30 min of reading magazines (control treatment). Subjective ratings of mental fatigue were measured before and after treatment, and mental effort and motivation were measured after treatment. Distance run, heart rate, and ratings of perceived exertion were recorded during the Yo-Yo IR1. LSPT performance time was calculated as original time plus penalty time. LSST performance was assessed using shot speed, shot accuracy, and shot sequence time. Subjective ratings of mental fatigue and effort were higher after the Stroop task in both studies (P soccer-specific running, passing, and shooting performance.

  8. Standard technical specifications for Westinghouse pressurized water reactors (revision issued Fall 1981). Technical report

    International Nuclear Information System (INIS)

    Virgilio, M.J.

    1981-11-01

    The Standard Technical Specifications for Westinghouse Pressurized Water Reactors (W-STS) is a generic document prepared by the U.S. NRC for use in the licensing process of current Westinghouse Pressurized Water Reactors. The W-STS sets forth the Limits, Operating Conditions and other requirements applicable to nuclear reactor facility operation as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  9. Standard Technical Specifications for Westinghouse pressurized water reactors

    International Nuclear Information System (INIS)

    Virgilio, M.J.

    1980-09-01

    The Standard Technical Specifications for Westinghouse Pressurized Water Reactors (W-STS) is a generic document prepared by the U.S. NRC for use in the licensing process of current Westinghouse Pressurized Water Reactors. The W-STS sets forth the Limits, Operating Conditions and other requirements applicable to nuclear reactor facility operation as set forth in by Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public. This document is revised periodically to reflect current licensing requirements

  10. Standard Technical Specifications for Combustion Engineering Pressurized Water Reactors

    International Nuclear Information System (INIS)

    Vito, D.J.

    1980-12-01

    The Standard Technical Specifications for Combustion Engineering Pressurized Water Reactors (CE-STS) is a generic document prepared by the US NRC for use in the licensing process of current Combustion Engineering Pressurized Water Reactors. The CE-STS sets forth the limits, operating conditions, and other requirements applicable to nuclear reactor facility operation as set forth by Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public. The document is revised periodically to reflect current licensing requirements

  11. A THREE-DIMENSIONAL BABCOCK-LEIGHTON SOLAR DYNAMO MODEL

    International Nuclear Information System (INIS)

    Miesch, Mark S.; Dikpati, Mausumi

    2014-01-01

    We present a three-dimensional (3D) kinematic solar dynamo model in which poloidal field is generated by the emergence and dispersal of tilted sunspot pairs (more generally bipolar magnetic regions, or BMRs). The axisymmetric component of this model functions similarly to previous 2.5 dimensional (2.5D, axisymmetric) Babcock-Leighton (BL) dynamo models that employ a double-ring prescription for poloidal field generation but we generalize this prescription into a 3D flux emergence algorithm that places BMRs on the surface in response to the dynamo-generated toroidal field. In this way, the model can be regarded as a unification of BL dynamo models (2.5D in radius/latitude) and surface flux transport models (2.5D in latitude/longitude) into a more self-consistent framework that builds on the successes of each while capturing the full 3D structure of the evolving magnetic field. The model reproduces some basic features of the solar cycle including an 11 yr periodicity, equatorward migration of toroidal flux in the deep convection zone, and poleward propagation of poloidal flux at the surface. The poleward-propagating surface flux originates as trailing flux in BMRs, migrates poleward in multiple non-axisymmetric streams (made axisymmetric by differential rotation and turbulent diffusion), and eventually reverses the polar field, thus sustaining the dynamo. In this Letter we briefly describe the model, initial results, and future plans

  12. Computer Support of Semantic Text Analysis of a Technical Specification on Designing Software

    OpenAIRE

    Zaboleeva-Zotova, Alla; Orlova, Yulia

    2009-01-01

    The given work is devoted to development of the computer-aided system of semantic text analysis of a technical specification. The purpose of this work is to increase efficiency of software engineering based on automation of semantic text analysis of a technical specification. In work it is offered and investigated a technique of the text analysis of a technical specification is submitted, the expanded fuzzy attribute grammar of a technical specification, intended for formaliza...

  13. Rigorous Specification and Low-Latency Implementation of Technical Market Indicators

    OpenAIRE

    Bakanov, Konstantin; Spence, Ivor; Vandierendonck, Hans; Gillan, Charles J

    2014-01-01

    Technical market indicators are tools used by technical an- alysts to understand trends in trading markets. Technical (market) indicators are often calculated in real-time, as trading progresses. This paper presents a mathematically- founded framework for calculating technical indicators. Our framework consists of a domain specific language for the un- ambiguous specification of technical indicators, and a run- time system based on Click, for computing the indicators. We argue that our soluti...

  14. Evaluation of River Bend Station Unit 1 Technical Specifications

    International Nuclear Information System (INIS)

    Baxter, D.E.; Bruske, S.J.

    1985-08-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the River Bend Station Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the requirements of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the River Bend T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The River Bend Station Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  15. Evaluation of Perry Nuclear Power Plant Unit 1 technical specifications

    International Nuclear Information System (INIS)

    Baxter, D.E.; Bruske, S.J.

    1985-11-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Perry Nuclear Power Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the requirements of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Perry T/S. Several discrepancies were identified and subsequently resolved through telephone conversations with the staff reviewer and the utility representative. Pending completion of the resolutions noted in Parts 3 and 4 of this report, the Perry Nuclear Power Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  16. Optimization Strategy of the APR+ BOP Technical Specifications

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Yoon Sang; Lee, Jae Gon; Han, Sung Heum [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    The BOP is one of the key factors for successful project implementation of NPP. In constructing the APR1400 NPP, the BOP procurement has been one of the biggest concerns. Due to the design changes and increased capacity of equipment in NPP, lots of BOPs should be ‘first supplied equipment’ [hereinafter, ‘FSE’]. The manufacture-ability, and the performances of FSEs have not been fully proved and tested, manufacturers and suppliers are requested to submit Reports for Equipment Qualification Evaluation in accordance with 10 CFR 50.49, IEEE 323. They need at least 1-2 years’ tests for Environment Qualification (EQ) and Seismic Qualification (SQ). This study is focused how to prepare the BOP purchase specifications in order to control the FSEs, especially in safety class equipment. With the optimization plan for BOP packages of this study, the FSEs’ occurrence can be reasonably controlled as low as possible. For successful NPP project, the concerns in procuring BOPs shall be fully analyzed beforehand. Now Korea is preparing new era of APR+, with closing the time of APR1400. The technical specification of APR+ BOPs can be developed and prepared successfully and very effectively according to this optimization plan. This will be a great contribution not only in constructing APR+ in time, but also in exporting APR+ overseas, all over the world in the future.

  17. Recommendations for the treatment of aging in standard technical specifications

    International Nuclear Information System (INIS)

    Orton, R.D.; Allen, R.P.

    1995-09-01

    As part of the US Nuclear Regulatory Commission's Nuclear Plant Aging Research Program, Pacific Northwest Laboratory (PNL) evaluated the standard technical specifications for nuclear power plants to determine whether the current surveillance requirements (SRs) were effective in detecting age-related degradation. Nuclear Plant Aging Research findings for selected systems and components were reviewed to identify the stressors and operative aging mechanisms and to evaluate the methods available to detect, differentiate, and trend the resulting aging degradation. Current surveillance and testing requirements for these systems and components were reviewed for their effectiveness in detecting degraded conditions and for potential contributions to premature degradation. When the current surveillance and testing requirements appeared ineffective in detecting aging degradation or potentially could contribute to premature degradation, a possible deficiency in the SRs was identified that could result in undetected degradation. Based on this evaluation, PNL developed recommendations for inspection, surveillance, trending, and condition monitoring methods to be incorporated in the SRs to better detect age- related degradation of these selected systems and components

  18. Assessment of ISLOCA risk: Methodology and application to a Babcock and Wilcox nuclear power plant

    International Nuclear Information System (INIS)

    Galyean, W.J.; Gertman, D.I.

    1992-04-01

    This report presents information essential to understanding the risk associated with inter-system loss-of-coolant accidents (ISLOCAs). The methodology developed and presented in the report provides a state-of-the-art method for identifying and evaluating plant-specific hardware design, human performance issues, and accident consequence factors to relevant to the prediction of the ISLOCA risk. This ISLOCA methodology was developed and then applied to a Babcock and Wilcox (B ampersand W) nuclear power plants. The results from this application are described in detail. For this particular B ampersand W reference plant, the assessment indicated that the probability of a severe ISLOCA is approximately 2.2E-06/reactor-year. This document Volume 3 provides appendices A--H of the report. Topics are: Historical experience related to ISLOCA events; component failure rates; reference B ampersand W plant system descriptions; reference B ampersand W plant ISLOCA event trees; Human reliability analysis for the B ampersand W ISLOCA probabilistic risk assessment; thermal hydraulic calculations; bounding core uncovery time calculations; and system rupture probability

  19. Babcock and Wilcox Owners' Group program: Trip reduction and transient response improvement

    International Nuclear Information System (INIS)

    O'Connor, W.T.; Mercado, A.L.; Ganthner, R.W.

    1989-01-01

    In 1985, the average trip frequency for the industry was 4.3 trips per plant per year while Babcock ampersand Wilcox (B ampersand W)-designed plants had 4.5 trips. In early 1986, the B ampersand W Owners' Group (B ampersand WOG) established goals to reduce trip frequency and improve posttrip transient response. Through the recommendations of the B ampersand WOG Trip Reduction and Transient Response Improvement Program (TR/TRIP) and other utility initiatives, the trip frequency for the B ampersand WOG plants has been on a progressive downward trend and has been consistently below the industry average since 1986. The successful results in trip reduction for the B ampersand WOG plants are shown. The B ampersand WOG has implemented several programs that have resulted in fewer trips per plant. This success can be attributed to the following: (1) a comprehensive program to evaluate each trip and transient for root-cause determination, define corrective actions, share information, and peer reviews; (2) a broad program to review systems and components that contribute to trips and transients, identify specific recommendations to correct deficiencies, utility commitment to implementation, conduct internal monitoring and indirectly exert peer pressure; (3) an awareness of the goals at all levels in the organization coupled with strong executive-level involvement; and (4) timely implementation of recommendations

  20. McMunn, et al. v. Babcock and Wilcox Power Generation Group, Inc., et al.: The long road to dismissal

    International Nuclear Information System (INIS)

    Berger, Marjorie

    2016-01-01

    McMunn, et al. v Babcock and Wilcox Power Generation Group, Inc., et al. was one of 17 related public liability actions filed between 2010 and 2015 by individuals living and/or working in the vicinity of two former fuel fabrication facilities who alleged that releases of radioactive materials from those facilities contaminated the air, soil, surface water and groundwater in the surrounding communities, causing them personal injury and property damage. The plaintiffs in all 17 cases claimed they had contracted various cancers and their property was contaminated with uranium. Plaintiffs brought their claims pursuant to the Price-Anderson Amendments Act (PAA) and the Atomic Energy Act of 1954, as amended (AEA), and also asserted related state law claims of negligence, negligence per se, strict liability, civil conspiracy, and wrongful death and survival. The defendants, Babcock and Wilcox Power Generation Group, Inc., B and W Technical Services, Inc. and Atlantic Richfield Company (ARCO), were unrelated companies who, at different times, owned and operated those facilities. The PAA, which became law on 2 September 1957, is a federal statute that governs claims for personal injury and property damage 'arising from the activities of NRC licensees and DOE contractors'. These claims are defined in the PAA as public liability actions. In order to prevail in a public liability action, plaintiffs must establish through expert evidence that the defendants released radiation into the environment in excess of the limits then permitted by federal regulations and that the plaintiffs were exposed to those releases. They must also establish that their respective exposures to radionuclides were capable of causing their illnesses and that the doses of radiation they received did in fact cause their illnesses

  1. TECHNICAL BASIS FOR VENTILATION REQUIREMENTS IN TANK FARMS OPERATING SPECIFICATIONS DOCUMENTS

    Energy Technology Data Exchange (ETDEWEB)

    BERGLIN, E J

    2003-06-23

    This report provides the technical basis for high efficiency particulate air filter (HEPA) for Hanford tank farm ventilation systems (sometimes known as heating, ventilation and air conditioning [HVAC]) to support limits defined in Process Engineering Operating Specification Documents (OSDs). This technical basis included a review of older technical basis and provides clarifications, as necessary, to technical basis limit revisions or justification. This document provides an updated technical basis for tank farm ventilation systems related to Operation Specification Documents (OSDs) for double-shell tanks (DSTs), single-shell tanks (SSTs), double-contained receiver tanks (DCRTs), catch tanks, and various other miscellaneous facilities.

  2. The key to technical translation, v.1 concept specification

    CERN Document Server

    Hann, Michael

    1992-01-01

    This handbook for German/English/German technical translators at all levels from student to professional covers the root terminologies of the spectrum of scientific and engineering fields. The work is designed to give technical translators direct insight into the main error sources occurring in their profession, especially those resulting from a poor understanding of the subject matter and the usage of particular terms to designate different concepts in different branches of technology. The style is easy to read and suitable for nonnative English speakers and translators with no engineering ex

  3. 10 CFR 50.36a - Technical specifications on effluents from nuclear power reactors.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Technical specifications on effluents from nuclear power...; Ineligibility of Certain Applicants § 50.36a Technical specifications on effluents from nuclear power reactors..., including expected occurrences, as low as is reasonably achievable, each licensee of a nuclear power reactor...

  4. Comparison of methods applicable to evaluation of nuclear power plant technical specifications

    International Nuclear Information System (INIS)

    Cho, N.Z.; Bozoki, G.E.; Youngblood, R.W.

    1986-01-01

    This study compares three probabilistic methods based on the static fault tree analysis, time-dependent unavailability analysis, and Markov analysis, which can be used to evaluate technical specifications in nuclear power plants. They are tested on a sample problem which was devised to closely represent the important and essential characteristics that should be addressed in determination and evaluation of the technical specifications

  5. Analysis of Technical Specifications of the Egyptian and French Electronic Storybooks (e-Storybook)

    Science.gov (United States)

    Atta, Mohammed Mahmoud; Abd El Wahab, Shaimaa Mahmoud

    2015-01-01

    This research aims at analysing technical specifications in a sample of Egyptian and French electronic storybooks (e-storybooks), to identify similarities and differences in technical specifications of children's e-storybooks and create a verified analysis list to be used for evaluation of e-storybooks. For this purpose, 32 e-storybooks in CD…

  6. 77 FR 45282 - NRC Position on the Relationship Between General Design Criteria and Technical Specification...

    Science.gov (United States)

    2012-07-31

    ... Position on the Relationship Between General Design Criteria and Technical Specification Operability AGENCY... relationship between the general design criteria (GDC) for nuclear power plants and technical specification... Communications Branch, Division of Policy and Rulemaking, Office Nuclear Reactor Regulation, Mail Stop: OWFN-12-D...

  7. 76 FR 189 - Notice of Availability of the Models for Plant-Specific Adoption of Technical Specifications Task...

    Science.gov (United States)

    2011-01-03

    ... [pressurized water reactor] Operability Requirements and Actions for RCS [reactor coolant system] Leakage...) and non- concurrence, are available electronically under ADAMS Accession Numbers ML101340278 and... FURTHER INFORMATION CONTACT: Mr. Matthew Hamm, Reactor Systems Engineer, Technical Specifications Branch...

  8. Feasibility assessment of a risk-based approach to technical specifications

    International Nuclear Information System (INIS)

    Atefi, B.; Gallagher, D.W.

    1991-05-01

    To assess the potential use of risk and reliability techniques for improving the effectiveness of the technical specifications to control plant operational risk, the Technical Specifications Branch of the Nuclear Regulatory Commission initiated an effort to identify and evaluate alternative risk-based approaches that could bring greater risk perspective to these requirements. In the first phase four alternative approaches were identified and their characteristics were analyzed. Among these, the risk-based approach to technical specifications is the most promising approach for controlling plant operational risk using technical specifications. The second phase of the study concentrated on detailed characteristics of the real time risk-based approach. It is concluded that a real time risk-based approach to technical specifications has the potential to improve both plant safety and availability. 33 figs., 5 figs., 6 tabs

  9. Technical specifications on the welding in fuel reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

    Karino, Motonobu; Uryu, Mitsuru; Matsui, N.; Nakazawa, Fumio; Imanishi, Makoto; Koizumi; Kazuhiko; Sugawara, Junichi; Tanaka, Hideo

    1999-04-01

    The past specifications SGN of the welding in JNC was reexamined for the reprocessing plants in order to further promote the quality control. The specification first concerns the quality of raw materials, items of the quality tests, material management, and qualification standards of the welders. It extends over details of the welding techniques, welding design, welding testings, inspection and the judgment standards. (H. Baba)

  10. Dowel Bar Retrofit Mix Design and Specification : Technical Report

    Science.gov (United States)

    2012-01-01

    Current INDOT specifications for repair materials to be used in dowel bar retrofit (DBR) applications (Sections 507.08 and 901.07 of INDOTs Book of Specifications) are based, in large part, on the requirements of ASTM C 928 and the manufacturer-pr...

  11. A study on decision-making framework for developing risk-informed technical specifications

    International Nuclear Information System (INIS)

    Kim, Beom Seock

    2002-02-01

    The utility and the nuclear research institutes in Korea have conduct research for improving inefficient requirements in technical specifications using the results of probability risk assessments and information associated with risk. However, the guidance for reviewing the improved technical specifications has not been developed. Thus, the objective of this study is to develop a decision-making framework for investigating and reviewing the documents associated with the changes of technical specifications. This work has been done for helping the regulation agency to review the improved technical specifications as well as to make decisions whether the remedy is accepted or not. The contents of this study include: 1. Surveys on Technical Specification regulations in foreign countries as well as those in Korea 2. Surveys on the state- of- the- art methodology for Risk Informed Technical Specifications and their uses in Korea 3. Development of a decision-making framework in both the licensee and the regulation agency position 4. Development and applications of a decision-making framework using Influence Diagrams. The decision-making framework for RITS using Influence Diagrams are developed and applied to an example problem in this study. This work might contribute to developing the risk informed regulation guidance for improving the quality of the current technical specifications

  12. Study of the technical specifications for the diesels generator of Juragua NPP

    International Nuclear Information System (INIS)

    Vilaragut Llanes, J.J.

    1996-01-01

    The Technical Specifications of a nuclear power plant specify the limits for plant operation from the safety point of view. These operational safety rules were originally defined on the basis of deterministic analysis and engineering judgement. The Probabilistic safety Assessment, constitutes a tool to analyze of the risk effect in the Technical Specifications Rules, and makes possible a relative comparison of the rules from the risk point of view. This paper studies the technical specifications for the diesels generators of Juragua Nuclear Power Plant and for that was used the probabilistic methodology . It is presented the evaluation of the some parameters as surveillance testing, test interval, repairs time, diesel degradation and AOT

  13. UXO Engineering Design. Technical Specification and ConceptualDesign

    Energy Technology Data Exchange (ETDEWEB)

    Beche, J-F.; Doolittle, L.; Greer, J.; Lafever, R.; Radding, Z.; Ratti, A.; Yaver, H.; Zimmermann, S.

    2005-04-23

    The design and fabrication of the UXO detector has numerous challenges and is an important component to the success of this study. This section describes the overall engineering approach, as well as some of the technical details that brought us to the present design. In general, an array of sensor coils is measuring the signal generated by the UXO object in response to a stimulation provided by the driver coil. The information related to the location, shape and properties of the object is derived from the analysis of the measured data. Each sensor coil is instrumented with a waveform digitizer operating at a nominal digitization rate of 100 kSamples per second. The sensor coils record both the large transient pulse of the driver coil and the UXO object response pulse. The latter is smaller in amplitude and must be extracted from the large transient signal. The resolution required is 16 bits over a dynamic range of at least 140 dB. The useful signal bandwidth of the application extends from DC to 40 kHz. The low distortion of each component is crucial in order to maintain an excellent linearity over the full dynamic range and to minimize the calibration procedure. The electronics must be made as compact as possible so that the response of its metallic parts has a minimum signature response. Also because of a field system portability requirement, the power consumption of the instrument must be kept as low as possible. The theory and results of numerical and experimental studies that led to the proof-of-principle multitransmitter-multireceiver Active ElectroMagnetic (AEM) system, that can not only accurately detect but also characterize and discriminate UXO targets, are summarized in LBNL report-53962: ''Detection and Classification of Buried Metallic Objects, UX-1225''.

  14. Understanding the technical content of requirements in specification document

    DEFF Research Database (Denmark)

    Sudin, Mohd Nizam Bin; Ahmed-Kristensen, Saeema

    2011-01-01

    in practice, 97 statements from 2 specification documents were analyzed in detail and the results are reported in this paper. These statements were analyzed quantitatively and qualitatively based on a pre-defined coding scheme. The results of the study show that the majority of requirements were related...

  15. Technical specification for transferring tank construction data to the Oak Ridge Environmental Information System (OREIS)

    International Nuclear Information System (INIS)

    1996-06-01

    The primary goal of this technical specification is to meet the consolidated environmental data requirements defined by the Federal Facility Agreement (FFA) and the Tennessee Oversight Agreement as they pertain to tank construction data maintained in Oak Ridge, Tennessee, by the US Department of Energy's Maintenance and Operations contractor Lockheed Martin Energy Systems, Inc., and prime contractors to the Department of Energy. This technical specification describes the organizational responsibilities for loading tank construction data into OREIS, describes the logical and physical data transfer files, addresses business rules and submission rules, addresses configuration control of this technical specification, and addresses required changes to the current OREIS data base structure based on site requirements. This technical specification addresses the tank construction data maintained by the Y-12, K-25, and ORNL sites that will be sent to OREIS. The initial submission of data will include only inactive Environmental Restoration tanks as specified by the FFA

  16. Technical specification for a 25 MV tandem electrostatic accelerator

    International Nuclear Information System (INIS)

    Jones, C.M.; Biggerstaff, J.A.; Blair, J.K.; Ball, J.B.; Larson, J.D.; Martin, J.A.; McConnell, J.W.; Milner, W.T.; Murray, J.A.; Ziegler, N.F.

    1975-08-01

    Specifications are given for an accelerator system to consist of a 25 MV tandem electrostatic accelerator and specified ancillary equipment, including an injector, a beam transport system, a vacuum system, a control system, and a system for storage of the insulating gas and transport of the gas to and from the accelerator. The insulating gas shall be SF 6 . The tandem electrostatic accelerator shall be vertical in orientation and of folded construction, and shall be installed in a new structure adjacent to the Oak Ridge Isochronous Cyclotron. (auth)

  17. Feasibility assessment of a risk-based approach to technical specifications

    International Nuclear Information System (INIS)

    Atefi, B.; Gallagher, D.W.

    1991-05-01

    The first phase of the assessment concentrates on (1) identification of selected risk-based approaches for improving current technical specifications, (2) appraisal of characteristics of each approach, including advantages and disadvantages, and (3) recommendation of one or more approaches that might result in improving current technical specification requirements. The second phase of the work concentrates on assessment of the feasibility of implementation of a pilot program to study detailed characteristics of the preferred approach. The real time risk-based approach was identified as the preferred approach to technical specifications for controlling plant operational risk. There do not appear to be any technical or institutional obstacles to prevent initiation of a pilot program to assess the characteristics and effectiveness of such an approach. 2 tabs

  18. Rotary ATPases: models, machine elements and technical specifications.

    Science.gov (United States)

    Stewart, Alastair G; Sobti, Meghna; Harvey, Richard P; Stock, Daniela

    2013-01-01

    Rotary ATPases are molecular rotary motors involved in biological energy conversion. They either synthesize or hydrolyze the universal biological energy carrier adenosine triphosphate. Recent work has elucidated the general architecture and subunit compositions of all three sub-types of rotary ATPases. Composite models of the intact F-, V- and A-type ATPases have been constructed by fitting high-resolution X-ray structures of individual subunits or sub-complexes into low-resolution electron densities of the intact enzymes derived from electron cryo-microscopy. Electron cryo-tomography has provided new insights into the supra-molecular arrangement of eukaryotic ATP synthases within mitochondria and mass-spectrometry has started to identify specifically bound lipids presumed to be essential for function. Taken together these molecular snapshots show that nano-scale rotary engines have much in common with basic design principles of man made machines from the function of individual "machine elements" to the requirement of the right "fuel" and "oil" for different types of motors.

  19. Standard technical specifications General Electric plants, BWR/6. Volume 1, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/6 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS.

  20. Use of probabilistic safety assessment to evaluate nuclear power plant technical specifications

    International Nuclear Information System (INIS)

    1991-04-01

    The meeting was organized to promote the use of risk and reliability techniques to improve safety and operational flexibility of nuclear power plants. The 43 participants from 17 countries and IAEA took part in the meeting. The 23 papers which were presented indicated that there was a worldwide recognition that risk and reliability techniques could be a useful tool to optimize technical specification requirements. A separate abstract was prepared for each of these papers. This TECDOC, prepared by the meeting participants, summarizes the insights from the various papers presented and the plenary discussions. It also presents a regulatory perspective for the use of PSA-based Technical Specifications in Member States. Finally, the proposal of a pilot study programme on the use of risk and reliability methods for technical specifications optimization to be undertaken by Member States under the coordination of the IAEA was discussed. Refs, figs and tabs

  1. The impact of technical specification surveillance requirements and allowable outage times on plant availability

    International Nuclear Information System (INIS)

    Webster, S.A.; Finnicum, D.J.

    1985-01-01

    Surveillances required to be conducted by a plant's Technical Specifications have resulted in plant shutdowns and lost availability. This paper looks at shutdowns which have occurred due to required surveillance testing and insufficient repair time allowed by Technical Specifications. A loss of plant availability of almost 3% per plant year was found for U.S. pressurized water reactors during the five year period, 1979 to 1984. This figure excludes major problems which required plant shutdown whether or not mandated by the Technical Specifications. In addition to their affect on availability, such shutdowns can add to the challenges to plant safety systems and can affect plant aging by increasing the thermal cycles on plant components

  2. Comparison of licensing activities for operating plants designed by Babcock and Wilcox

    International Nuclear Information System (INIS)

    Thoma, J.O.

    1985-01-01

    This report provides a comparison of a number of licensing activities for the operating Babcock and Wilcox (B and W) plants with emphasis on Rancho Seco. The factors selected were a comparison of staff resources expended in FY84, active licensing action reviews, implementation of NUREG-0737 modifications, exemptions to regulations, SALP reports, enforcement actions, and Licensee Event Reports (LERs). The eight licensed operating plants examined are as follows: Arkansas Nuclear One Unit 1 (ANO-1), Crystal River Unit 3, Davis Besse, Oconee Units 1, 2, and 3, Rancho Seco, and Three Mile Island Unit 1 (TMI-1)

  3. Risk based optimization of technical specifications for operation of nuclear power plants

    International Nuclear Information System (INIS)

    1993-12-01

    The objective of the report is to present an overview of the risk and reliability based approaches (using a probabilistic safety assessment (PSA)) for improving nuclear power plant technical specifications (TS). In that case, it will provide an information base to the Member States in seeking PSA based applications to enhance the effectiveness of their technical specifications. To achieve this objective, the report discusses the basic objectives and reasons for seeking TS changes, the methods, data requirements and uses of different types of applications, and an overview of different applications that have been completed, including detailed descriptions of selected applications. Refs, figs and tabs

  4. Technical specification improvements to containment heat removal and emergency core cooling systems: Final report

    International Nuclear Information System (INIS)

    Sullivan, W.P.; Ha, C.; Pentzien, D.C.; Visweswaran, S.

    1988-07-01

    This report presents the results of an analysis for technical specification improvements to the emergency core cooling systems (ECCS) and containment heat removal systems (EPRI Research Project 2142-3). The objective of this project is to further develop a reliability- and risk-based methodology to provide improvements by considering groups of surveillance test intervals and allowed out-of-service times jointly. This was done for the technical specifications for the ECCS, containment heat removal equipment, and supporting systems of a boiling water reactor plant. The project (1) developed a methodology for optimizing groups of surveillance test intervals and allowed out-of-service times jointly, (2) applied the methodology in a case study of a specific operating plant, Hatch-2, and (3) evaluated benefits of the application. The results of the case study demonstrate that beneficial technical specification improvements can be realized with application of the methodology. By tightening a small group of sensitive surveillance test intervals (STIs) and allowed out-of-service times (AOTs), a larger group of less sensitive STIs and AOTs can be extended resulting in an overall plant operating cost improvement without reducing the plant safety. The reliability- and risk-based methodology and results from this project can be effectively applied for technical specification improvements at other operating plants

  5. 78 FR 33863 - Relationship Between General Design Criteria and Technical Specification Operability

    Science.gov (United States)

    2013-06-05

    ... No: 2013-13352] NUCLEAR REGULATORY COMMISSION [NRC-2012-0179] Relationship Between General Design... Issue Summary (RIS) 2013-05, ``NRC Position on the Relationship Between General Design Criteria and Technical Specification Operability.'' This RIS clarifies the NRC staff's position on the relationship...

  6. Technical specifications: Seabrook Station, Unit 1 (Docket No. 50-443)

    International Nuclear Information System (INIS)

    1990-03-01

    The Seabrook Station, Unit 1 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  7. 78 FR 12063 - Meeting for Software Developers on the Technical Specifications for Common Formats for Patient...

    Science.gov (United States)

    2013-02-21

    ... disability is needed, please contact the Food and Drug Administration (FDA) Office of Equal Employment... Medicare & Medicaid Services, Food and Drug Administration, Health Resources and Services Administration... patient safety event data. The technical specifications consist of the following: [cir] Data dictionary...

  8. 77 FR 9252 - Meeting for Software Developers on the Technical Specifications for Common Formats for Patient...

    Science.gov (United States)

    2012-02-16

    ... other reasonable accommodation for a disability is needed, please contact the Food and Drug...)--the Centers for Disease Control and Prevention, Centers for Medicare & Medicaid Services, Food and... technical specifications consist of the following: Data dictionary--defines data elements and their...

  9. 78 FR 22554 - Document to Support Submission of an Electronic Common Technical Document-Specifications for File...

    Science.gov (United States)

    2013-04-16

    ... Types Using Electronic Common Technical Document Specifications; Availability AGENCY: Food and Drug... the electronic Common Technical Document (eCTD) specifications: ``Specifications for File Format Types... acceptance of advertising and promotional labeling in the eCTD format, it has become necessary to expand the...

  10. Waste management issues and their potential impact on technical specifications of CANDU fuel materials

    International Nuclear Information System (INIS)

    Tait, J.C.; Johnson, L.H.

    1997-01-01

    The technical specifications for the composition of nuclear fuels and materials used in Canada's CANDU reactors have been developed by AECL and materials manufacturers, taking into account considerations specific to their manufacture and the effect of minor impurities on fuel behaviour in reactor. Nitrogen and chlorine are examples of UO 2 impurities, however, where there is no technical specification limit. These impurities are present in the source materials or introduced in the fabrication process and are neutron activated to 14 C and 36 C1, which after 129 I , are the two most significant contributors to dose in safety assessments for the disposal of used fuel. For certain impurities, environmental factors, particularly the safety of the disposal of used fuels, should be taken into consideration when deriving 'allowable' impurity limits for nuclear fuel materials. (author)

  11. Improved technical specifications and related improvements to safety in commercial Nuclear power plants

    International Nuclear Information System (INIS)

    Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C.

    2004-01-01

    Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

  12. Technical specifications for the successful fabrication of laminated seismic isolation bearings

    International Nuclear Information System (INIS)

    Kulak, R.F.

    1992-01-01

    High damping laminated elastomeric bearings are becoming one of the preferred devices for isolating large buildings and structures. IN the United States, the current reference design for the Advanced Liquid Metal Reactor uses laminated bearings for seismic isolation. These bearing are constructed from alternating layers of rubber and steel plates. They are typically designed for shear strains between 50 to 100 percent and expected to sustain two to three times these levels for beyond design basis loading considerations. The technical specifications used to procure these bearings are an important factor in assuring that the bearings that are installed under nuclear structures meet the performance requirements of the design. The key aspects of the current version of the Technical Specifications are discussed in this paper

  13. Technical specifications for the successful fabrication of laminated seismic isolation bearings

    International Nuclear Information System (INIS)

    Kulak, R.F.

    1992-01-01

    High damping steel-laminated elastomeric seismic isolation bearings are becoming a preferred device for isolating large buildings and structures. In the United States, the current reference design for the Advanced Liquid Metal Reactor uses laminated bearings for seismic isolation. These bearings are constructed from alternating layers of rubber and steel plates. They are typically designed for shear strains between 50 to 100 percent and expected to sustain two to three times these levels for beyond design basis loading considerations. The technical specifications used to procure these bearings are an important factor in assuring that the bearings meet the performance requirements of the design. The key aspects of the current version of the Technical Specifications are discussed in this paper. (author)

  14. Technical specifications for the successful fabrication of laminated seismic isolation bearings

    Energy Technology Data Exchange (ETDEWEB)

    Kulak, R.F.

    1992-05-01

    High damping laminated elastomeric bearings are becoming one of the preferred devices for isolating large buildings and structures. IN the United States, the current reference design for the Advanced Liquid Metal Reactor uses laminated bearings for seismic isolation. These bearing are constructed from alternating layers of rubber and steel plates. They are typically designed for shear strains between 50 to 100 percent and expected to sustain two to three times these levels for beyond design basis loading considerations. The technical specifications used to procure these bearings are an important factor in assuring that the bearings that are installed under nuclear structures meet the performance requirements of the design. The key aspects of the current version of the Technical Specifications are discussed in this paper.

  15. Technical specifications for the successful fabrication of laminated seismic isolation bearings

    Energy Technology Data Exchange (ETDEWEB)

    Kulak, R.F.

    1992-01-01

    High damping laminated elastomeric bearings are becoming one of the preferred devices for isolating large buildings and structures. IN the United States, the current reference design for the Advanced Liquid Metal Reactor uses laminated bearings for seismic isolation. These bearing are constructed from alternating layers of rubber and steel plates. They are typically designed for shear strains between 50 to 100 percent and expected to sustain two to three times these levels for beyond design basis loading considerations. The technical specifications used to procure these bearings are an important factor in assuring that the bearings that are installed under nuclear structures meet the performance requirements of the design. The key aspects of the current version of the Technical Specifications are discussed in this paper.

  16. Development of Integral Effect Test Facility P and ID and Technical Specification for SMART Fluid System

    International Nuclear Information System (INIS)

    Lee, Sang Il; Jung, Y. H.; Yang, H. J.; Song, S. Y.; Han, O. J.; Lee, B. J.; Kim, Y. A.; Lim, J. H.; Park, K. W.; Kim, N. G.

    2010-01-01

    SMART integral test loop is the thermal hydraulic test facility with a high pressure and temperature for simulating the major systems of the prototype reactor, SMART-330. The objective of this project is to conduct the basic design for constructing SMART ITL. The major results of this project include a series of design documents, technical specifications and P and ID. The results can be used as the fundamental materials for making the detailed design which is essential for manufacturing and installing SMART ITL

  17. Critical evaluation of the nonradiological environmental technical specifications. Program description, summary, and recommendations. Vol. 1

    International Nuclear Information System (INIS)

    Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.; Witten, A.J.

    1976-01-01

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for eight nuclear power plants was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory commission. This report includes a summary of the screening phase in which the adequacy of the hydrothermal and ecological monitoring data for each plant were evaluated, and the summary and recommendations resulting from a detailed examination of the three nuclear power plants selected in the initial screening

  18. Results of a neutron flux perturbation experiment with Babcock and Wilcox Owners Group surveillance capsules

    International Nuclear Information System (INIS)

    Snidow, N.L.; Hassler, L.A.

    1989-01-01

    The Babcock and Wilcox Owners Group (B and WOG) Flux Perturbation Experiment in the Oak Ridge National Laboratory Poolside Facility simulated the thermal shield, downcomer, pressure vessel, and cavity region of a B and W-designed 177-fuel assembly reactor by an arrangement of steel slabs and a void box. Two simulated surveillance capsules located in the downcomer were irradiated as part of the NRC-sponsored Light Water Reactor Pressure Vessel Surveillance Dosimetry Improvement Pregram. The capsules contained extensive dosimetry provided B and W and the Hanford Engineering Development Laboratory (HEDL). Dosimeters were also located outside of the capsules in the downcomer region. Flux distributions were calculated throughout the test configuration using the two-dimensional DOT 4.3 transport theory code. The calculated and measured data are compared in this paper

  19. Summary description of the Babcock and Wilcox integrated nuclear design system

    International Nuclear Information System (INIS)

    Wittkopf, W.A.

    1976-03-01

    The Babcock and Wilcox integrated nuclear design system is divided into three broad areas: basic nuclear data processing, applications data processing, and nuclear design calculations. In basic nuclear data processing, basic nuclear data are collected, evaluated, and processed into a specified fine-energy mesh multigroup data file called a Master Library. In applications data processing, data for selected materials are retrieved from the Master Library and processed into an optimally structured, multigroup Production Library. Using these data and input descriptions of cells or regions, neutron spectra are generated and few-group constants are computed and fitted as a function of fuel burnup, initial enrichment, temperature, etc. In nuclear design calculations, few-group cross-section fits and descriptions of each core region and core geometry are input to a diffusion-depletion program or a nodal program that computes core reactivity, core power distribution, control rod worth, fuel cycle studies, core operating limitations, etc

  20. Health hazard evaluation report No. HETA-81-003-980, Babcock and Wilcox Co. , Milwaukee, Wisconsin

    Energy Technology Data Exchange (ETDEWEB)

    Zey, J.N.; Ahrenholz, S.; Klemme, J.C.

    1981-10-01

    On October 1, 1980, the National Institute for Occupational Safety and Health (NIOSH) received a request from the International Brotherhood of Boilermakers Union, Local 1849, for a Health Hazard Evaluation of the Babcock and Wilcox Co., Tubular Products Division, Milwaukee, Wisconsin. The request involved the potential for employee exposure to biocides, dispersant and anti-scaling agents as they are added to four separate circulating water systems which cool four annealing furnaces, two reheat furnaces and one air compressor. NIOSH conducted a combined environmental and medical survey at the Milwaukee facility on November 19-20, 1980. While conducting a walk-through survey on November 19, 1980, NIOSH observed that furnace operators working near cooling systems were potentially exposed to cooling system chemicals. The furnace operators were included in employee monitoring on November 20, 1980. All concentrations obtained were below current environmental criteria. Medical interview data suggested that workers may have been exposed to potentially hazardous levels of DMF in the past.

  1. Seismic risk analysis for the Babcock and Wilcox facility, Leechburg, Pennsylvania

    International Nuclear Information System (INIS)

    1977-01-01

    The results of a detailed seismic risk analysis of the Babcock and Wilcox Plutonium Fuel Fabrication facility at Leechburg, Pennsylvania are presented. This report focuses on earthquakes; the other natural hazards, being addressed in separate reports, are severe weather (strong winds and tornados) and floods. The calculational method used is based on Cornell's work (1968); it has been previously applied to safety evaluations of major projects. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases. Because of the aseismicity of the region around the site, an analysis different from the conventional closest approach in a tectonic province was adapted. Earthquakes as far from the site as 1,000 km were included, as were the possibility of earthquakes at the site. In addition, various uncertainties in the input were explicitly considered in the analysis. The results of the risk analysis, which include a Bayesian estimate of the uncertainties, are presented, expressed as return period accelerations. The best estimate curve indicates that the Babcock and Wilcox facility will experience 0.05 g every 220 years and 0.10 g every 1400 years. The bounding curves roughly represent the one standard deviation confidence limits about the best estimate, reflecting the uncertainty in certain of the input. Detailed examination of the results show that the accelerations are very insensitive to the details of the source region geometries or the historical earthquake statistics in each region and that each of the source regions contributes almost equally to the cumulative risk at the site. If required for structural analysis, acceleration response spectra for the site can be constructed by scaling the mean response spectrum for alluvium in WASH 1255 by these peak accelerations

  2. Standard technical specifications combustion engineering plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/6 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes.

  3. Differential and Integral Calculus in careers of technical sciences. Specificities of their teaching

    Directory of Open Access Journals (Sweden)

    Iván Javier Villamar-Alvarado

    2017-12-01

    Full Text Available The Differential and Integral Calculus has great relevance for the professionals of the technical sciences since it provides them with a solid theoretical-conceptual body to process information, to use models that simulate real processes, to solve technical problems, to work in multidisciplinary projects and to communicate with precision. In spite of this relevance, there are numerous international dissatisfactions related to their learning by training engineers. The objective was to unveil the specificities of the teaching-learning process of this discipline that favor a successful appropriation of its content by the future engineers. The result was to unveil the didactic need to resolve the dialectical contradiction that manifests itself between the systematization of the engineering functionality of the aforementioned content and its contextualized interdisciplinary generalization. As a consequence, the need arises to create new didactic proposals that overcome this contradiction, as a way to perfect the teaching-learning process of this discipline in the engineering careers.

  4. Procurement in the Imaging Department: The Need for Understanding Technical Specifications

    International Nuclear Information System (INIS)

    Bwonya, N.S.M.

    2015-01-01

    Procurement is the function responsible for the acquisition of goods, works or services in an Organization. The Governments has three main ways of purchasing: Cash Imprest, Invitation of Quotation and Open National Tender. A Tenderer is a domestic, foreign, legal or natural person offering to supply goods, services or perform work assignments. Procurement involves needs identified by users, the procurement will seek approval from the AIE holder after which Preparation of specifications, Identifification of supplier (source) for delivering of the item to be stored after proper marking and verification. Specifications or Specs is a term mainly used in the acquisition of many items and in a Radiology department these include equipment, supplies and contrast media. A specification is a technical standard, tailored to perform certain functions and It is a set of requirements satisfied by a material, design, product or service. A technical evaluation team sets specifications and ideally will comprise of the following; a Radiologist, Senior Radiographer; an Engineer, Supplies professional and a Senior person (Nurse) whose department will need Radiological Services

  5. Technical specification: Mixed-oxide pellets for the light-water reactor irradiation demonstration test

    International Nuclear Information System (INIS)

    Cowell, B.S.

    1997-06-01

    This technical specification is a Level 2 Document as defined in the Fissile Materials Disposition Program Light-Water Reactor Mixed-oxide Fuel Irradiation Test Project Plan. It is patterned after the pellet specification that was prepared by Atomic Energy of Canada, Limited, for use by Los Alamos National Laboratory in fabrication of the test fuel for the Parallex Project, adjusted as necessary to reflect the differences between the Canadian uranium-deuterium reactor and light-water reactor fuels. This specification and the associated engineering drawing are to be utilized only for preparation of test fuel as outlined in the accompanying Request for Quotation and for additional testing as directed by Oak Ridge National Laboratory or the Department of Energy

  6. Impact of shutdown risk on risk-based assessment of technical specifications

    International Nuclear Information System (INIS)

    Deriot, S.

    1992-10-01

    This paper describes the current work performed by the Research and Development Division of EDF concerning risk-based assessment of Operating Technical Specifications (OTS). The current risk-based assessment of OTS at EDF is presented. Then, the level 1 Probabilistic Safety Assessment of unit 3 of the Paluel nuclear power station (called PSA 1300) is described. It is fully computerized and takes into account the risk in shutdown states. A case study is presented. It shows that the fact of considering shutdown risk suggests that the current OTS should be modified

  7. Risk-based configuration control: Application of PSA in improving technical specifications and operational safety

    International Nuclear Information System (INIS)

    Samanta, P.K.; Kim, I.S.; Vesely, W.E.

    1992-01-01

    Risk-based configuration control is the management of component configurations using a risk perspective to control risk and assure safety. A configuration, as used here, is a set of component operability statuses that define the state of a nuclear power plant. If the component configurations that have high risk implications do not occur, then the risk from the operation of nuclear power plants would be minimal. The control of component configurations, i.e., the management of component statuses, to minimize the risk from components being unavailable, becomes difficult, because the status of a standby safety system component is often not apparent unless it is tested. Controlling plant configuration from a risk-perspective can provide more direct risk control and also more operational flexibility by allowing looser controls in areas unimportant to risk. Risk-based configuration control approaches can be used to replace parts of nuclear power plant Technical Specifications. With the advances in probabilistic safety assessment (PSA) technology, such approaches to improve Technical Specifications and operational safety are feasible. In this paper, we present an analysis of configuration risks, and a framework for risk-based configuration control to achieve the desired control of risk-significant configurations during plant operation

  8. Risk-based configuration control: Application of PSA in improving technical specifications and operational safety

    Energy Technology Data Exchange (ETDEWEB)

    Samanta, P.K.; Kim, I.S. [Brookhaven National Lab., Upton, NY (United States); Vesely, W.E. [Science Applications International Corp., Dublin, OH (United States)

    1992-11-01

    Risk-based configuration control is the management of component configurations using a risk perspective to control risk and assure safety. A configuration, as used here, is a set of component operability statuses that define the state of a nuclear power plant. If the component configurations that have high risk implications do not occur, then the risk from the operation of nuclear power plants would be minimal. The control of component configurations, i.e., the management of component statuses, to minimize the risk from components being unavailable, becomes difficult, because the status of a standby safety system component is often not apparent unless it is tested. Controlling plant configuration from a risk-perspective can provide more direct risk control and also more operational flexibility by allowing looser controls in areas unimportant to risk. Risk-based configuration control approaches can be used to replace parts of nuclear power plant Technical Specifications. With the advances in probabilistic safety assessment (PSA) technology, such approaches to improve Technical Specifications and operational safety are feasible. In this paper, we present an analysis of configuration risks, and a framework for risk-based configuration control to achieve the desired control of risk-significant configurations during plant operation.

  9. Risk-based configuration control: Application of PSA in improving technical specifications and operational safety

    Energy Technology Data Exchange (ETDEWEB)

    Samanta, P.K.; Kim, I.S. (Brookhaven National Lab., Upton, NY (United States)); Vesely, W.E. (Science Applications International Corp., Dublin, OH (United States))

    1992-01-01

    Risk-based configuration control is the management of component configurations using a risk perspective to control risk and assure safety. A configuration, as used here, is a set of component operability statuses that define the state of a nuclear power plant. If the component configurations that have high risk implications do not occur, then the risk from the operation of nuclear power plants would be minimal. The control of component configurations, i.e., the management of component statuses, to minimize the risk from components being unavailable, becomes difficult, because the status of a standby safety system component is often not apparent unless it is tested. Controlling plant configuration from a risk-perspective can provide more direct risk control and also more operational flexibility by allowing looser controls in areas unimportant to risk. Risk-based configuration control approaches can be used to replace parts of nuclear power plant Technical Specifications. With the advances in probabilistic safety assessment (PSA) technology, such approaches to improve Technical Specifications and operational safety are feasible. In this paper, we present an analysis of configuration risks, and a framework for risk-based configuration control to achieve the desired control of risk-significant configurations during plant operation.

  10. Technical specifications manual for the MARK-1 pulsed ionizing radiation detection system

    International Nuclear Information System (INIS)

    Lawrence, R.S.; Harker, Y.D.; Jones, J.L.; Hoggan, J.M.

    1993-03-01

    The MARK-1 detection system was developed by the Idaho National Engineering Laboratory for the US Department of Energy Office of Arms Control and Nonproliferation. The completely portable system was designed for the detection and analysis of intense photon emissions from pulsed ionizing radiation sources. This manual presents the technical design specifications for the MARK-1 detection system and was written primarily to assist the support or service technician in the service, calibration, and repair of the system. The manual presents the general detection system theory, the MARK-1 component design specifications, the acquisition and control software, the data processing sequence, and the system calibration procedure. A second manual entitled: Volume 2: Operations Manual for the MARK-1 Pulsed Ionizing Radiation Detection System (USDOE Report WINCO-1108, September 1992) provides a general operational description of the MARK-1 detection system. The Operations Manual was written primarily to assist the field operator in system operations and analysis of the data

  11. Manual of engineering drawing technical product specification and documentation to British and international standards

    CERN Document Server

    Simmons, Colin H; Simmons, Colin

    2012-01-01

    Manual of Engineering Drawing is a comprehensive guide for experts and novices for producing engineering drawings and annotated 3D models that meet the recent BSI and ISO standards of technical product documentation and specifications. This fourth edition of the text has been updated in line with recent standard revisions and amendments. The book has been prepared for international use, and includes a comprehensive discussion of the fundamental differences between the ISO and ASME standards, as well as recent updates regarding legal components, such as copyright, patents, and other legal considerations. The text is applicable to CAD and manual drawing, and it covers the recent developments in 3D annotation and surface texture specifications. Its scope also covers the concepts of pictorial and orthographic projections, geometrical, dimensional and surface tolerancing, and the principle of duality. The text also presents numerous examples of hydraulic and electrical diagrams, applications, bearings, adhesives, ...

  12. Technical specifications manual for the MARK-1 pulsed ionizing radiation detection system. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Lawrence, R.S.; Harker, Y.D.; Jones, J.L.; Hoggan, J.M.

    1993-03-01

    The MARK-1 detection system was developed by the Idaho National Engineering Laboratory for the US Department of Energy Office of Arms Control and Nonproliferation. The completely portable system was designed for the detection and analysis of intense photon emissions from pulsed ionizing radiation sources. This manual presents the technical design specifications for the MARK-1 detection system and was written primarily to assist the support or service technician in the service, calibration, and repair of the system. The manual presents the general detection system theory, the MARK-1 component design specifications, the acquisition and control software, the data processing sequence, and the system calibration procedure. A second manual entitled: Volume 2: Operations Manual for the MARK-1 Pulsed Ionizing Radiation Detection System (USDOE Report WINCO-1108, September 1992) provides a general operational description of the MARK-1 detection system. The Operations Manual was written primarily to assist the field operator in system operations and analysis of the data.

  13. Technical specification for the Quality Information Management System (QIMS) Pilot Project

    Energy Technology Data Exchange (ETDEWEB)

    Hall, R.C.; Claussen, L.M.; Thurston, I.

    1992-01-01

    This document contains implementation details for the Quality Information Management System (QIMS) Pilot Project, which has been released for VAX/VMS systems using the INGRES RDBMS. The INGRES Applications-By-Forms (ABF) software development tool was used to define the modules and screens which comprise the QIMS Pilot application. These specifications together with the QIMS information model and corresponding database definition constitute the QIMS technical specification and implementation description presented herein. The QIMS Pilot Project represents a completed software product which has been released for production use. Further extension projects are planned which will release new versions for QIMS. These versions will offer expanded and enhanced functionality to meet further customer requirements not accommodated by the QIMS Pilot Project.

  14. Handbook of methods for risk-based analysis of technical specifications

    International Nuclear Information System (INIS)

    Samanta, P.K.; Kim, I.S.; Mankamo, T.; Vesely, W.E.

    1996-01-01

    Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operations (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements are based on deterministic analyses and engineering judgments. Improvements in these requirements are facilitated by the availability of plant-specific Probabilistic Risk Assessments (PRAs). The US Nuclear Regulatory Commission (USNRC) Office of Research sponsored research to develop systematic, risk-based methods to improve various aspects of TS requirements. A handbook of methods summarizing such risk-based approaches has been completed in 1994. It is expected that this handbook will provide valuable input to NRC's present work in developing guidance for using PRA in risk-informed regulation. The handbook addresses reliability and risk-based methods for evaluating allowed outage times (AOTs), action statements requiring shutdown where shutdown risk may be substantial, surveillance test intervals (STIs), managing plant configurations, and scheduling maintenance

  15. Interpretation of the results of the technical indicators of agriculture-specific economic”

    OpenAIRE

    Olteanu, Victor

    2014-01-01

    The passage of a technological process is carried out only in circumstances where the process is efficient in economic terms. Assessment of technological processes can be done by means of indicators which can be: economic, technical, economic and technical. Technical-economic indicators used in assessing technological processes are scalars with or without dimensions, which characterizes a substance, a technical device, a system, or a technological process both technically and economically.

  16. Case study on the use of PSA methods: Assessment of technical specifications for the reactor protection system instrumentation

    International Nuclear Information System (INIS)

    1992-10-01

    This case study presents a methodology for the probabilistic evaluation of alternative plant technical specifications regarding system surveillance frequencies and out-of-service times. The methodology is applied to the reactor protection systems of a 4 loop BWR-RESAR-3S type nuclear power plant. The effect of the statistical characteristics of the system on the relative comparison of various sets of technical specifications is examined through sensitivity studies and an uncertainty analysis. Refs, figs and tabs

  17. Safety evaluation report related to Babcock and Wilcox Owners Group Plant Reassessment Program: [Final report

    International Nuclear Information System (INIS)

    1987-11-01

    After the accident of Three Mile Island, Unit 2, nuclear power plant owners made a number of improvements to their nuclear facilities. Despite these improvements, the US Nuclear Regulatory Commission (NRC) staff is concerned that the number and complexity of events at Babcock and Wilcox (B and W) nuclear plants have not decreased as expected. This concern was reinforced by the June 9, 1985 total-loss-of-feedwater event at Davis-Besse Nuclear Power Station and the December 26, 1985 overcooling transient at Rancho Seco Nuclear Generating Station. By letter dated January 24, 1986, the Executive Director for Operations (EDO) informed the Chairman of the B and W Owners Group (BWOG) that a number of recent events at B and W-designed reactors have led the NRC staff to conclude that the basic requirements for B and W reactors need to be reexamined. In its February 13, 1986 response to the EDO's letter, the BWOG committed to lead an effort to define concerns relative to reducing the frequency of reactor trips and the complexity of post-trip response in B and W plants. The BWOG submitted a description of the B and W program entitled ''Safety and Performance Improvement Program'' (BAW-1919) on May 15, 1986. Five revisions to BAW-1919 have also been submitted. The NRC staff has reviewed BAW-1919 and its revisions and presents its evaluation in this report. 2 figs., 34 tabs

  18. Technical specifications for the provision of heat and steam sources for INPP and Visaginas. Final report

    International Nuclear Information System (INIS)

    2003-01-01

    In October 1999, the National Energy Strategy was approved by the Lithuanian Parliament. The National Energy Strategy included the decision to close Unit-1 of INPP before 2005. Later is has been decided to close Unit 2 before the end of 2009 as well. The closure and decommissioning will have heavy impact on the heat supply for the city of Visaginas. Unit 1 and Unit 2 of INPP supplies hot water and steam to INPP for process purposes and for space heating of residential and commercial buildings. When Unit 1 is permanently shut down, reliable heat and steam sources independent of the power plants own heat and steam generation facilities are required for safety reasons in the event of shutdown of the remaining unit for maintenance or in an emergency. These steam and heat sources must be operational before single unit operation is envisaged. Provision of a reliable independent heat and steam source is therefore urgent. After both reactors are shut down permanently, a steam source will be needed at the plant for radioactive waste storage and disposal. INPP and DEA has performed a feasibility study for the provision of a reliable heat source for Ignalina Nuclear Power Plant and Visaginas, and the modernisation of Visaginas district heating system. The objective of this project is to prepare technical specifications for the provision of new heat and steam sources for INPP and Visaginas, and for rehabilitation of the heat transmission pipeline between INPP, the back-up boiler station and Visaginas City. The results of the study are presented in detail in the reports and technical specifications: 1. Transient analysis for Visaginas DH system, 2. Non-destructive testing of boiler stations, pump stations and transmission lines, 3. Conceptual design, 4. Technical specifications, Package 1 to 6. The study has suggested: 1. Construction of new steam boiler station, 2. Construction of new heat only boiler station, 3. Renovation of existing back-up heat only boiler station, 4

  19. Risk-based technical specifications: Development and application of an approach to the generation of a plant specific real-time risk model

    International Nuclear Information System (INIS)

    Puglia, B.; Gallagher, D.; Amico, P.; Atefi, B.

    1992-10-01

    This report describes a process developed to convert an existing PRA into a model amenable to real time, risk-based technical specification calculations. In earlier studies (culminating in NUREG/CR-5742), several risk-based approaches to technical specification were evaluated. A real-time approach using a plant specific PRA capable of modeling plant configurations as they change was identified as the most comprehensive approach to control plant risk. A master fault tree logic model representative of-all of the core damage sequences was developed. Portions of the system fault trees were modularized and supercomponents comprised of component failures with similar effects were developed to reduce the size of the model and, quantification times. Modifications to the master fault tree logic were made to properly model the effect of maintenance and recovery actions. Fault trees representing several actuation systems not modeled in detail in the existing PRA were added to the master fault tree logic. This process was applied to the Surry NUREG-1150 Level 1 PRA. The master logic mode was confirmed. The model was then used to evaluate frequency associated with several plant configurations using the IRRAS code. For all cases analyzed computational time was less than three minutes. This document Volume 2, contains appendices A, B, and C. These provide, respectively: Surry Technical Specifications Model Database, Surry Technical Specifications Model, and a list of supercomponents used in the Surry Technical Specifications Model

  20. Technical evaluation report on the proposed design modifications and technical specification changes on grid voltage degradation for the Millstone Nuclear Power Station, Unit 1

    International Nuclear Information System (INIS)

    Selan, J.C.

    1982-01-01

    This report documents the technical evaluation of the proposed design modifications and Technical Specification change for protection of Class 1E equipment from grid voltage degradation for the Millstone Nuclear Power Station, Unit 1. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation finds that the licensee has not provided sufficient information on the undervoltage protection system to allow a complete evaluation into the adequacy of protecting the Class 1E equipment from sustained voltage degradation

  1. The critical care nurse. Specific expertise to form in the Superior Technical Nursing

    Directory of Open Access Journals (Sweden)

    Víctor Hugo Rodríguez-Medrano

    2016-06-01

    Full Text Available Higher Technical career in Nursing (TSE meets the need of human resources of the health system, making qualified technicians to be part of multidisciplinary teams in the health care network, applying nursing care throughout the life cycle, with orientation to promotion, prevention, recovery and rehabilitation of health. However inconsistencies are evident in the formative praxis that limit demonstrate the knowledge, skills and attitudes for students in providing nursing service and solving various health problems in users with a specialized nature, in line with current social needs humanist. Why this paper aims to draft pedagogical nature reflections that allow understand the formation of the specific competence nursing care critical in the student user. This result of the doctoral research carried out on this subject, with the application of empirical and theoretical methods which set the proposals that contribute to the solution of this problem.

  2. Catalogue of EDF`s technical specifications (HN reference). Centre of standardization; Catalogue des specifications techniques EDF (reference HN). Centre de normalisation

    Energy Technology Data Exchange (ETDEWEB)

    1998-12-31

    This document edited by Electricite de France (EdF), is a catalogue of the French standard documents relative to any type of electrical material and equipment and which contain the technical specifications of these materials and equipments. A brief description of these specifications is given for each type of material or equipment listed. (J.S.)

  3. Facilitating Site Specific and Citizens Advisory Boards: Running Effective Meetings that Involve Complex Technical Issues

    International Nuclear Information System (INIS)

    Freeman, J.

    2009-01-01

    Environmental cleanup issues at federal sites are more often than not on the agendas of meetings of the Site Specific Advisory Boards (SSABs), also called Citizens Advisory Boards (CABs), that exist at most U.S. Department of Energy (DOE) sites with an Environmental Management (EM) mission. In 1994, when Congress established these committees comprised of local citizens, it enabled community stakeholders to become more directly involved in DOE EM cleanup decisions. This involvement is to help the agency make cost-effective and environmentally sound decisions which lead to faster, safer cleanups. Eight local Boards that fall under the Federal Advisory Committee Act-chartered EM SSAB charter are found in Hanford, Washington; Idaho; Northern New Mexico; Nevada; Oak Ridge, Tennessee; Paducah, Kentucky; Portsmouth, Ohio; and at the Savannah River Site in South Carolina. These boards provide advice and recommendations about EM site-specific issues such as cleanup standards (how clean is clean?), environmental restoration, waste management, the stabilization and disposal of non-stockpile nuclear materials, future land use and long-term stewardship, risk assessment and management, and cleanup science and technology activities. These issues are, by their very nature, loaded with complicated technical terms and strategies, scientific data and interpretations, and long histories of studies and reports. The members of SSABs and CABs rotate on and off the Boards according to defined terms of office, thereby routinely opening the Boards' ranks to new members, many of whom are new to the issues. In addition, members of the public who have access to public comment periods at each Board meeting run up against the same daunting menu of obscure acronyms, scientific terms and notations, and an historical trail which is not always evident except to those involved with the issues over many years. How does a facilitator effectively guide such a group of citizens, each of whom arrives to

  4. Domain-Specific Mappings as Conceptual Categorisers for Scientific and Technical Vocabularies

    Directory of Open Access Journals (Sweden)

    Pilar Durán-Escribano

    2017-10-01

    Full Text Available The analysis of metaphorical lexical units in science and technology provides evidence for their existence either as separate cases or as part of a corresponding conceptual metaphor. In conceptual metaphor, metaphorical expressions constitute productive patterns that unveil the mental mappings that support technical and scientific thought, proving to be a powerful device for conceptualization and a prolific driving force for language growth (Lakoff & Johnson, 1980. Although conceptual metaphor cannot account for all types of linguistic metaphor (Evans, 2013, in this paper we have focused on the former because it implies a systematic set of correspondences between different domains of science and technology supporting the role of conceptual metaphor as a powerful theory constitutive element. The study is based on the qualitative analysis of the metaphorical lexical units included in eight widely accepted specific dictionaries, totalling over 790.000 entries. Attention is focused on domain-specific mappings, in which not only the target but also the source domain pertain to scientific fields, and where the corresponding linguistic expressions keep their univocal meaning in each field. Thus, providing examples from two apparently unrelated fields, earth sciences and telecommunications engineering, the role of domain-specific mappings as conceptual categorisers is studied, underlying the different degrees of categorization involved in the building of new theories (Boyd, 1993, in definitions, and in the expression of new concepts.

  5. Standard Technical Specifications General Electric plants, BWR/4:Bases (Sections 3.4-3.10). Volume 3, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the specifications for all chapters and sections of the improved STS. Volume 2 contains he Bases for Chapters 2.0 and 3.0, and Sections 3.1-3.3 of the improved STS. This document, Volume 3, contains the Bases for Sections 3.4-3.10 of the improved STS

  6. Solar Cycle Variability Induced by Tilt Angle Scatter in a Babcock-Leighton Solar Dynamo Model

    Science.gov (United States)

    Karak, Bidya Binay; Miesch, Mark

    2017-09-01

    We present results from a three-dimensional Babcock-Leighton (BL) dynamo model that is sustained by the emergence and dispersal of bipolar magnetic regions (BMRs). On average, each BMR has a systematic tilt given by Joy’s law. Randomness and nonlinearity in the BMR emergence of our model produce variable magnetic cycles. However, when we allow for a random scatter in the tilt angle to mimic the observed departures from Joy’s law, we find more variability in the magnetic cycles. We find that the observed standard deviation in Joy’s law of {σ }δ =15^\\circ produces a variability comparable to the observed solar cycle variability of ˜32%, as quantified by the sunspot number maxima between 1755 and 2008. We also find that tilt angle scatter can promote grand minima and grand maxima. The time spent in grand minima for {σ }δ =15^\\circ is somewhat less than that inferred for the Sun from cosmogenic isotopes (about 9% compared to 17%). However, when we double the tilt scatter to {σ }δ =30^\\circ , the simulation statistics are comparable to the Sun (˜18% of the time in grand minima and ˜10% in grand maxima). Though the BL mechanism is the only source of poloidal field, we find that our simulations always maintain magnetic cycles even at large fluctuations in the tilt angle. We also demonstrate that tilt quenching is a viable and efficient mechanism for dynamo saturation; a suppression of the tilt by only 1°-2° is sufficient to limit the dynamo growth. Thus, any potential observational signatures of tilt quenching in the Sun may be subtle.

  7. Handbook of methods for risk-based analysis of Technical Specification requirements

    International Nuclear Information System (INIS)

    Samanta, P.K.; Vesely, W.E.

    1993-01-01

    Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements were based on deterministic analysis and engineering judgments. Experiences with plant operation indicate that some elements of the requirements are unnecessarily restrictive, while others may not be conducive to safety. Improvements in these requirements are facilitated by the availability of plant specific Probabilistic Safety Assessments (PSAs). The use of risk and reliability-based methods to improve TS requirements has gained wide interest because these methods can: quantitatively evaluate the risk impact and justify changes based on objective risk arguments. Provide a defensible basis for these requirements for regulatory applications. The United States Nuclear Regulatory Commission (USNRC) Office of Research is sponsoring research to develop systematic risk-based methods to improve various aspects of TS requirements. The handbook of methods, which is being prepared, summarizes such risk-based methods. The scope of the handbook includes reliability and risk-based methods for evaluating allowed outage times (AOTs), action statements requiring shutdown where shutdown risk may be substantial, surveillance test intervals (STIs), defenses against common-cause failures, managing plant configurations, and scheduling maintenances. For each topic, the handbook summarizes methods of analysis and data needs, outlines the insights to be gained, lists additional references, and presents examples of evaluations

  8. Handbook of methods for risk-based analysis of technical specification requirements

    International Nuclear Information System (INIS)

    Samanta, P.K.; Vesely, W.E.

    1994-01-01

    Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements were based on deterministic analysis and engineering judgments. Experiences with plant operation indicate that some elements of the requirements are unnecessarily restrictive, while others may not be conducive to safety. Improvements in these requirements are facilitated by the availability of plant specific Probabilistic Safety Assessments (PSAs). The use of risk and reliability-based methods to improve TS requirements has gained wide interest because these methods can: Quantitatively evaluate the risk and justify changes based on objective risk arguments; Provide a defensible basis for these requirements for regulatory applications. The US NRC Office of Research is sponsoring research to develop systematic risk-based methods to improve various aspects of TS requirements. The handbook of methods, which is being prepared, summarizes such risk-based methods. The scope of the handbook includes reliability and risk-based methods for evaluating allowed outage times (AOTs), action statements requiring shutdown where shutdown risk may be substantial, surveillance test intervals (STIs), defenses against common-cause failures, managing plant configurations, and scheduling maintenances. For each topic, the handbook summarizes methods of analysis and data needs, outlines the insights to be gained, lists additional references, and presents examples of evaluations

  9. Technical specification for transferring National Pollutant Discharge Elimination System water data to the Oak Ridge Environmental Information System

    International Nuclear Information System (INIS)

    1996-11-01

    The primary goal of this technical specification is to meet the consolidated environmental data requirements defined by the Federal Facility (FFA) and the Tennessee Oversight Agreement (TOA) as they pertain to NPDES surface water data maintained in Oak Ridge, Tennessee, by the Department of Energy's Maintenance and Operations (M ampersand O) contractor Martin Marietta Energy Systems and prime contractors to DOE. This technical specification describes the organizational responsibilities for getting NPDES data into OREIS, describes the logical data transfer file required from NPDES, addresses business rules and submission rules, describes the physical data transfer file, addresses configuration control of this technical specification, and addresses required changes to the current OREIS data base structure due to the requirements of NPDES

  10. The water treatment in the dual-purpose nuclear plants of Babcock and Wilcox with straight pipes

    International Nuclear Information System (INIS)

    Martynova, O.I.

    1978-01-01

    A report is given on water processing and water chemistry in the dual-purpose nuclear power plants (as compared to the single-purpose nuclear power plants) of Babcock and Wilcox, with flow steam generators with straight pipes. The most important materials, especially regarding their corrosion resistance, and the water composition during 'hot' start-up of the Okonie-I power plant, the quality factors of the feedwater, the water quality factors of the steam generator with fast start-up and the experience with numerous corrosion-caused defects in steam generator pipes are dealt with from the aspect of optimum water processing and successful continuous operation. (HK) [de

  11. PSA-based optimization of technical specifications for the Borssele nuclear power plant

    International Nuclear Information System (INIS)

    Seebregts, A.J.; Schoonakker, H.A.

    1996-01-01

    The Borssele Nuclear Power Plant (NPP) is a Siemens/KWU 472 MWe Pressurized Water Reactor which has been in operation since 1973. In 1989, a Probabilistic Safety Assessment (PSA) program was initiated to complement deterministic safety studies and operational experience in forming a plant safety concept. In 1993, the PSA-MER model was completed and used to determine the effects a package of proposed modifications would have on plant safety and risks to the environment. This model was used to start retrospective risks profile and allowed outage times (AOTs) analyses, which both concerned the calculation of the change in total core damage frequency (TCDF) given a change in configuration. The main problems identified and reported in this paper are: (i) How to calculate the change in TCDF (ΔTCDF)? (section 3); and (ii) How to set practical decision criteria and how to use the PSA as extension to Technical Specifications (TS) AOTs? (section 4). Finally, a pilot study was conducted in order to optimize surveillance test intervals (STIs) which are also part of the TS (section 5). (orig.)

  12. Technical specification action requirements for AFW system failures: Method development and application to four PWR plants

    International Nuclear Information System (INIS)

    Mankamo, T.; Kim, I.S.; Yang, Ji Wu; Samanta, P.K.

    1996-01-01

    Failures in the auxiliary feedwater (AFW) system of pressurized water reactors (PWRs) are considered to involve substantial risk whether a decision is made to either continue power operation while repair is being done, or to shut down the plant to undertake repairs. Technical specification action requirements usually require immediate plant shutdown in the case of multiple failures in the system (in some cases, immediate repair of one train is required when all AFW trains fail). This paper presents a probabilistic risk assessment-based method to quantitatively evaluate and compare both the risks of continued power operation and of shutting the plant down, given known failures in the system. The method is applied to the AFW system for four different PWRs. Results show that the risk of continued power operation and plant shutdown both are substantial, but the latter is larger than the former over the usual repair time. This was proven for four plants with different designs: two operating Westinghouse plants, one operating Asea-Brown Boveri Combustion Engineering Plant, and one of evolutionary design. The method can be used to analyze individual plant design and to improve AFW action requirements using risk-informed evaluations

  13. Reviewing PSA-based analyses to modify technical specifications at nuclear power plants

    International Nuclear Information System (INIS)

    Samanta, P.K.; Martinez-Guridi, G.; Vesely, W.E.

    1995-12-01

    Changes to Technical Specifications (TSs) at nuclear power plants (NPPs) require review and approval by the United States Nuclear Regulatory Commission (USNRC). Currently, many requests for changes to TSs use analyses that are based on a plant's probabilistic safety assessment (PSA). This report presents an approach to reviewing such PSA-based submittals for changes to TSs. We discuss the basic objectives of reviewing a PSA-based submittal to modify NPP TSs; the methodology of reviewing a TS submittal, and the differing roles of a PSA review, a PSA Computer Code review, and a review of a TS submittal. To illustrate this approach, we discuss our review of changes to allowed outage time (AOT) and surveillance test interval (STI) in the TS for the South Texas Project Nuclear Generating Station. Based on this experience gained, a check-list of items is given for future reviewers; it can be used to verify that the submittal contains sufficient information, and also that the review has addressed the relevant issues. Finally, recommended steps in the review process and the expected findings of each step are discussed

  14. Handbook of methods for risk-based analyses of technical specifications

    International Nuclear Information System (INIS)

    Samanta, P.K.; Kim, I.S.; Mankamo, T.; Vesely, W.E.

    1994-12-01

    Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements are based on deterministic analysis and engineering judgments. Experiences with plant operation indicate that some elements of the requirements are unnecessarily restrictive, while a few may not be conducive to safety. The US Nuclear Regulatory Commission (USNRC) Office of Research has sponsored research to develop systematic risk-based methods to improve various aspects of TS requirements. This handbook summarizes these risk-based methods. The scope of the handbook includes reliability and risk-based methods for evaluating allowed outage times (AOTs), scheduled or preventive maintenance, action statements requiring shutdown where shutdown risk may be substantial, surveillance test intervals (STIs), and management of plant configurations resulting from outages of systems, or components. For each topic, the handbook summarizes analytic methods with data needs, outlines the insights to be gained, lists additional references, and gives examples of evaluations

  15. Technical support for the Ukrainian State Committee for Nuclear Radiation Safety on specific waste issues

    International Nuclear Information System (INIS)

    Little, C.A.

    1995-01-01

    The government of Ukraine, a now-independent former member of the Soviet Union, has asked the United States to assist its State Committee for Nuclear and Radiation Safety (SCNRS) in improving its regulatory control in technical fields for which it has responsibility. The US Nuclear Regulatory Commission (NRC) is providing this assistance in several areas, including management of radioactive waste and spent fuel. Radioactive wastes resulting from nuclear power plant operation, maintenance, and decommissioning must be stored and ultimately disposed of appropriately. In addition, radioactive residue from radioisotopes used in various industrial and medical applications must be managed. The objective of this program is to provide the Ukrainian SCNRS with the information it needs to establish regulatory control over uranium mining and milling activities in the Zheltye Vody (Yellow Waters) area and radioactive waste disposal in the Pripyat (Chernobyl) area among others. The author of this report, head of the Environmental Technology Section, Health Sciences Research Division of Oak Ridge National Laboratory, accompanied NRC staff to Ukraine to meet with SCNRS staff and visit sites in question. The report highlights problems at the sites visited and recommends license conditions that SCNRS can require to enhance safety of handling mining and milling wastes. The author's responsibility was specifically for the visit to Zheltye Vody and the mining and milling waste sites associated with that facility. An itinerary for the Zheltye Vody portion of the trip is included as Appendix A

  16. Technical specifications: Hope Creek Generating Station (Docket No. 50-354). Appendix A to License No. NPF-50

    International Nuclear Information System (INIS)

    1986-04-01

    Information is provided on the technical specifications for the Hope Creek Nuclear Power Station. Areas of interest discussed in this report include: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  17. On-Line Monitoring of Instrument Channel Performance: Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation

    International Nuclear Information System (INIS)

    Davis, E.; Rasmussen, B.

    2004-01-01

    This report is a guide for a technical specification change submittal and subsequent implementation of on-line monitoring for safety-related applications. This report is the third in a three-volume set. Volume 1, ''Guidelines for Model Development and Implementation'', presents the various tasks that must be completed to prepare models for and to implement an on-line monitoring system

  18. Technical Specifications, Seabrook Station, Unit 1 (Docket No. 50-443): Appendix ''A'' to License No. NPF-67

    International Nuclear Information System (INIS)

    1989-05-01

    The Seabrook Station, Unit 1 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  19. Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the Millstone Nuclear Power Station, Unit 2 (Docket No. 50-336)

    International Nuclear Information System (INIS)

    Selan, J.C.

    1983-01-01

    This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the Millstone Nuclear Power Station, Unit 2. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

  20. Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the James A. Fitzpatrick Nuclear Power Plant (Docket No. 50-333)

    International Nuclear Information System (INIS)

    Selan, J.C.

    1983-01-01

    This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the James A. FitzPatrick Nuclear Power Plant. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

  1. A nuclear power unit with a Babcock type steam generating system-analysis of the break-down in the Three Mile Island power plant

    International Nuclear Information System (INIS)

    Werner, A.

    1980-01-01

    Installations of the primary and the secondary circuits and basic automatic control and protection systems for a nuclear power unit with Babcock type vertical, once-through steam generator are described. On this background the course of the break-down in the Three Mile Island power plant at Harrisburg is presented and analysed. (author)

  2. NPSAG/NKS: Interpretation and evaluation of the technical specification criteria

    Energy Technology Data Exchange (ETDEWEB)

    Baeckstroem, O.; Haeggstroem, A. (Relcon Scandpower AB, Sundbyberg (Sweden)); Simola, K. (VTT (Finland))

    2008-07-15

    The use of risk-informed methods has been discussed since the late 1980s. in the Nordic countries. However, at that time the industry and authorities were not ready for the use of these methods and the use of them have been limited. The common understanding right now is that the industry and authorities are ready for adoption of risk-informed strategies, and the use of risk informed methods in daily operation at the nuclear power plants (NPPs) as well as for long term evaluation and definition of rules and regulations is increasing. The authorities are strengthening the rules and regulations with regard to redundancy and diversification in the safety systems. There are several ongoing projects at the NPPs, such as modernization, power upgrade etc. These projects will require modification of the Technical Specifications (TS). The requirements on a risk analysis to verify exceptions will be a natural part of the TS update. To summarize; there are both activities and trends at the plants that will result in TS changes (modernizations, increase of electrical power, risk informed strategies). At the same time, authorities are increasing the requirements on risk informed evaluation of the TS. TS evaluation from a risk point of view raises several questions: 1) How shall the TS conditions be evaluated? 2) What aspects shall be taken into consideration? 3) Can a prolonged/shortened surveillance test interval (STI) or allowed outage time (AOT) affect the experienced importance of the equipment? 4) What do the conditions in the TS with regard to AOT really represent? Are they conditions that shall be used when spare part storage and/or maintenance strategies are developed or do they represent how a real situation (unavailable component) shall be managed? To form an idea of the opinion on these questions phase 1 of the project is based on a literature study and interviews with persons at the Swedish and Finnish utilities and authorities. A short background to the current TS

  3. Guidance to risk-informed evaluation of technical specifications using PSA

    Energy Technology Data Exchange (ETDEWEB)

    Baeckstroem, O.; Haeggstroem, A. (Scandpower AB, Stockholm (Sweden)); Maennistoe, I. (VTT, Helsingfors (Finland))

    2010-04-15

    This report presents guidance for evaluation of Technical Specification conditions with PSA. It covers quality in PSA, how to verify that the PSA model is sufficiently robust and sufficiently complete and general requirements on methods. Acceptance criteria for evaluation of changes in the TS conditions are presented. As the probabilistic safety assessment (PSA) has developed over the years, it has demonstrated to constitute a useful tool for evaluating many aspects of the TS from a risk point of view. and in that way making the PSAs as well as the decision tools better. This also means that it will be possible to take credit for safety system overcapacity as well as inherent safety features and strength of non-safety classed systems. However, PSA is only one of the tools that shall be used in an evaluation process of TS changes (strengthening/relaxation). PSA is an excellent tool to be used to verify the importance, and thereby possibly relaxation, of TS requirements. But, since PSA is only one tool in the evaluation, it is not sufficient in itself for defining which equipment that shall or shall not have TS requirements. The purpose of this guidance document is to provide general requirements, requirements on methods and acceptance criteria on risk-informed evaluation of TS changes based on PSA. The purpose is not to provide a single solution. As part of the review of the TS conditions this guidance specify requirements on: - Quality verification of the PSA model; - Verification that the PSA model is sufficiently robust with regard to SSCs for which requirements both are and are not defined by the TS; - Verification that the SSCs, for which TS demands are to be evaluated, are modelled in a sufficient manner; - Methods for performing the evaluation; - Which evaluation criteria that shall be used (and how that is verified to be correct); - Acceptance criteria: This guidance also briefly discusses the documentation of the analysis of the TS changes. This guidance

  4. THE MODEL OF TEACHING A FOREIGN LANGUAGE FOR SPECIFIC PURPOSES IN A TECHNICAL UNIVERSITY

    Directory of Open Access Journals (Sweden)

    Cherkashina, E.I.

    2017-06-01

    Full Text Available The article presents a new model of a linguistic educational process that can be implemented in the practice of teaching a foreign language in a technical university. The proposed model takes into account the characteristic features of mindset of students of technical universities and faculties, and it constitutes a matrix with a binary opposition. Filled-in matrix cells represent a structure of the language knowledge content in a visual form. Knowledge of the system organization of a language helps the students to understand "language in action" in the way that corresponds to their left hemisphere mindset. The knowledge of the dominant hemisphere cerebration peculiarities of the students of technical specializations (engineering physicists lets us model a lingvo-educational process in a non-linguistic university. A complex linking of lingvo-didactic components makes the teachers of foreign language take into consideration the results of the research in the field of functional interhemispheric asymmetry of the brain. The emphasis on the abilities of the left hemisphere dominating among the students has to change the approach of the teachers of foreign languages to the organization of the linguistic educational process in a technical university. It is also important to consider that the skills which led the life in the information age remain necessary, but they alone are no longer sufficient for personal self-realization in the new conceptual age.

  5. Comparison of implementation of selected TMI action plan requirements on operating plants designed by Babcock and Wilcox

    International Nuclear Information System (INIS)

    Thoma, J.O.

    1984-05-01

    This report provides the results of a study conducted by the US Nuclear Regulatory Commission staff to compare the degree to which eight Babcock and Wilcox (B and W) designed licensed nuclear power plants have complied with the requirements in NUREG-0737, Clarification of TMI Action Plan Requirements. The eight licensed operating plants examined are as follows: Arkansas Nuclear One Unit 1 (ANO-1), Crystal River Unit 3, Davis Besse, Oconee Units 1, 2, and 3, Rancho Seco, and Three Mile Island Unit 1 (TMI-1). The purpose of this audit was to establish the progress of the TMI-1 licensee, General Public Utilities (GPU) Nuclear Corporation, in completing the long-term requirements in NUREG-0737 relative to the other B and W licensees examined

  6. Calculation of particulate dispersion in a design-basis tornadic storm from the Babcock and Wilcox Plant, Leechburg, Pennsylvania

    International Nuclear Information System (INIS)

    Pepper, D.W.

    1978-03-01

    A three-dimensional numerical model is used to calculate ground-level air concentration and deposition (due to precipitation scavenging) after a hypothetical tornado strike at the Babcock and Wilcox Plutonium Fabrication Facility at Leechburg, Pennsylvania. Plutonium particles lss than 20 μm in diameter are assumed to be lifted into the tornadic storm cell by the vortex. The rotational characteristics of the tornadic storm are embedded within the larger mesoscale flow of the storm system. The design-basis translational wind values are based on probabilities associated with existing records of tornado strikes in the vicinity of the plant site. Turbulence exchange coefficients are based on empirical values deduced from experimental data in severe storms and from theoretical assumptions obtained from the literature. The quasi-Lagrangian method of moments is used to model the transport of concentration within a grid cell volume

  7. Technical specification for design, fabrication, use and maintenance of tie-down system

    International Nuclear Information System (INIS)

    Curcuruto, S.; Palmieri, G.; Trivelloni, S.; Orsini, A.

    1993-01-01

    IAEA Safety Series ndeg6 states that to ensure compliance with the Regulation the programs of quality assurance must be put in practice either for design, manufacture, testing, documentation, use and maintenance and inspection of all packages or for transport and intransit storage operations. Therefore in view of a standardization coming from Q.A. criteria, the Italian Competent Authority for transport of radioactive material (ENEA-DISP) is preparing a technical guide for the design, construction, use and maintenance of tie-down system for road transport of packages containing radioactive materials. The paper shows some phases of the program started by ENEA-DISP for the redaction of the technical guide. (J.P.N.)

  8. Evaluation of the Technical Adequacy of Three Methods for Identifying Specific Learning Disabilities Based on Cognitive Discrepancies.

    Science.gov (United States)

    Stuebing, Karla K; Fletcher, Jack M; Branum-Martin, Lee; Francis, David J

    2012-01-01

    This study used simulation techniques to evaluate the technical adequacy of three methods for the identification of specific learning disabilities via patterns of strengths and weaknesses in cognitive processing. Latent and observed data were generated and the decision-making process of each method was applied to assess concordance in classification for specific learning disabilities between latent and observed levels. The results showed that all three methods had excellent specificity and negative predictive values, but low to moderate sensitivity and very low positive predictive values. Only a very small percentage of the population (1%-2%) met criteria for specific learning disabilities. In addition to substantial psychometric issues underlying these methods, general application did not improve the efficiency of the decision model, may not be cost effective because of low base rates, and may result in many children receiving instruction that is not optimally matched to their specific needs.

  9. Technical Specifications of Structural Health Monitoring for Highway Bridges: New Chinese Structural Health Monitoring Code

    Directory of Open Access Journals (Sweden)

    Fernando Moreu

    2018-03-01

    Full Text Available Governments and professional groups related to civil engineering write and publish standards and codes to protect the safety of critical infrastructure. In recent decades, countries have developed codes and standards for structural health monitoring (SHM. During this same period, rapid growth in the Chinese economy has led to massive development of civil engineering infrastructure design and construction projects. In 2016, the Ministry of Transportation of the People’s Republic of China published a new design code for SHM systems for large highway bridges. This document is the first technical SHM code by a national government that enforces sensor installation on highway bridges. This paper summarizes the existing international technical SHM codes for various countries and compares them with the new SHM code required by the Chinese Ministry of Transportation. This paper outlines the contents of the new Chinese SHM code and explains its relevance for the safety and management of large bridges in China, introducing key definitions of the Chinese–United States SHM vocabulary and their technical significance. Finally, this paper discusses the implications for the design and implementation of a future SHM codes, with suggestions for similar efforts in United States and other countries.

  10. Technical specifications of air handling system of the inspection of a field

    International Nuclear Information System (INIS)

    Kim, Seon Duk; Bang, Hong Sik; Oh, Yon Woo

    2002-07-01

    A T.A.B(Testing, Adjusting and Balancing) technique, the basic technique of air handling facility, is one of the essential technical items which workers in charge of operation of facilities have to acquire. Especially, through scientific and reasonable inspective procedures, the reduction of energy and guarantee of designed skill have become influential important problems in our time rather than in the past days. Entrepreneurs have required more thorough verify of performances and procedure of test in order to raise the investment efficiency and reduce expenditure. For that reason, I hope that co-operator acquire objective and substantial knowledges about air handling facility so that they are helped from them

  11. Objectives, specification and elaboration of technical scenarios for emergency drills involving a French PWR

    International Nuclear Information System (INIS)

    Duco, J.

    1989-08-01

    All safety measures taken during the design, the construction and the operation of a nuclear power plant decrease to an extremely low level the probability of an accident with unacceptable consequences for the public. Nevertheless, for the case such an accident should be initiated, emergency plans have been elaborated: the on-site emergency plan to protect the plant personnel, terminate the accident and mitigate the consequences; the short-term and longer-term off-side emergency plans to protect the public and organise the return to acceptable living conditions. The appropriateness and preparedness of such plans have to be checked regularly by means of drills, which may be restricted to technical aspects concerning the nuclear units, or involve all actors, i.e. the utility, all the branches of the administration concerned and a media simulation. Some aspects of the choice of goals and preparation of drills are presented and illustrated by the national EPAULE exercice in 1987. Technically speaking, the drills have proved the validity of the current organization and evidenced its operability: uncertainties remain as regards the actual vs expected behavior of the population, due to emotional aspects linked to the lack of direct perception of the degree of danger and to the information received in an actual nuclear emergency

  12. Validity of multiple stress creep recovery (MSCR) test for DOTD asphalt binder specification : technical summary.

    Science.gov (United States)

    2017-09-01

    Higher traffic coupled with heavier loads led the asphalt industry to introduce polymer-modified binders to enhance the durability and strength of hot mix asphalt (HMA) pavements. When the Superpave Performance Graded (PG) binder specification (AASHT...

  13. A reexamination of the North American Crepis agamic complex and comparison with the findings of Babcock and Stebbins' classic biosystematic monograph.

    Science.gov (United States)

    Sears, Christopher J; Whitton, Jeannette

    2016-07-01

    Babcock and Stebbins coined the term agamic complex in their 1938 monograph of the North American Crepis agamic complex. Despite the historical role that this complex holds in the evolutionary literature, it has not been reexamined in over 75 years. We present a thorough reevaluation of the complex to test hypotheses proposed by Babcock and Stebbins about its origins and spread, the relationships of diploids, and the nature and origins of polyploids. We used flow cytometry to infer ploidy of roughly 600 samples spanning the morphological and taxonomic diversity of the complex and a phylogenetic analysis of plastid DNA variation to infer maternal relationships among diploids and to infer maternal origins of polyploids. We identified populations of all seven recognized diploids plus one new lineage. Phylogenetic analysis of plastid DNA variation in diploids revealed a well-resolved, but moderately supported phylogeny, with evidence for monophyly of the North America Crepis agamic complex and no evidence of widespread homoploid hybridization. Polyploids showed evidence of multiple origins and a pattern of frequent local co-occurrence consistent with repeated colonization of suitable sites. Our findings agree broadly with the distribution and variation of ploidy within and among species described by Babcock and Stebbins. One key difference is finding support for monophyly of North American species, and refuting their hypothesis of polyphyly. Our results provide an explicit phylogenetic framework for further study of this classic agamic complex. © 2016 Botanical Society of America.

  14. Knowledge Sharing for Common Understanding of Technical Specifications Through Artifactual Culture

    DEFF Research Database (Denmark)

    Zahedi, Mansooreh; Babar, Muhammad Ali

    2014-01-01

    specification knowledge. We also present the practices that make up the artifact-based knowledge sharing system in the studied case. Finally, we shed some light on the caveats of knowledge sharing practices adopted by the studied company. The findings can provide useful insights into the artifact...

  15. Technical Specification action statements requiring shutdown. A risk perspective with application to the RHR/SSW systems of a BWR

    Energy Technology Data Exchange (ETDEWEB)

    Mankamo, T. [Avaplan Oy, Espoo (Finland); Kim, I.S.; Samanta, P.K. [Brookhaven National Lab., Upton, NY (United States)

    1993-11-01

    When safety systems fail during power operation, the limiting conditions for operation (LCOs) and associated action statements of technical specifications typically require that the plant be shut down within the limits of allowed outage time (AOT). However, when a system needed to remove decay heat, such as the residual heat removal (RHR) system, is inoperable or degraded, shutting down the plant may not necessarily be preferable, from a risk perspective, to continuing power operation over a usual repair time, giving priority to the repairs. The risk impact of the basic operational alternatives, i.e., continued operation or shutdown, was evaluated for failures in the RHR and standby service water (SSW) systems of a boiling-water reactor (BWR) nuclear power plant. A complete or partial failure of the SSW system fails or degrades not only the RHR system but other front-line safety systems supported by the SSW system. This report presents the methodology to evaluate the risk impact of LCOs and associated AOT; the results of risk evaluation from its application to the RHR and SSW systems of a BWR; the findings from the risk-sensitivity analyses to identify alternative operational policies; and the major insights and recommendations to improve the technical specifications action statements.

  16. A Preliminary Investigation of General and Technique-specific Assessments for the Evaluation of Laparoscopic Technical Skills.

    Science.gov (United States)

    Vergis, Ashley; Steigerwald, Sarah

    2017-10-07

    Background  Both general and technique-specific assessments of technical skill have been validated in surgical education. The purpose of this study was to assess the correlation between the objective structured assessment of technical skills (OSATS) and the global operative assessment of laparoscopic skills (GOALS) rating scales using a high-fidelity porcine laparoscopic cholecystectomy model. Methods Post-graduate year-one general surgery and urology residents (n=14) performed a live laparoscopic porcine cholecystectomy. Trained surgeons rated their performance using OSATS and GOALS assessment scales. Results Pearson's correlation coefficient between OSATS and GOALS was 0.96 for overall scores. It ranged from 0.78 - 0.89 for domains that overlapped between the two scales. Conclusion There is a very high correlation between OSATS and GOALS. This implies that they likely measure similar constructs and that either may be used for summative-type assessments of trainee skill. However, further investigation is needed to determine if technique-specific assessments may provide more useful feedback in formative evaluation.

  17. Experiences with applications of PSA results for optimization/revision of technical specifications for operation of nuclear power plants

    International Nuclear Information System (INIS)

    Vijaya, A.K.; Guptan, Rajee; Mohan, Nalini; Ghadge, S.G.; Bajaj, S.S.

    2006-01-01

    Over the past few years, NPCIL has performed comprehensive Level-1 Probabilistic Safety Assessment (PSA) for a 220 MWe Pressurised Heavy Water Reactor (PHWR) at Kakrapar Atomic Power Station (KAPS) and for the first 540 MWe PHWR at Tarapur Atomic Power Project (TAPP- 3 and 4). The major objective of these PSAs was to present an integrated picture of the safety of the plant to identify and understand key plant vulnerabilities. As a result of the availability of these PSAs, there is a desire to use them to operate the plants in the most efficient manner practicable. In recent years, the operation of Indian Nuclear Power Plants has been characterized by improved availability/capacity factors and reduced forced outages. Frequency of planned outages is also being reduced. In order to achieve this, the PSAs are now being used as an engineering tool for optimization of Technical Specifications with regard to Allowed Outage Time (AOT) and Surveillance Test Intervals (STIs). USNRC Regulatory Guides have published Probabilistic Safety Criteria (PSC) which can be used as guidelines for optimization of technical specification, taking into consideration Instantaneous (conditional) Risk, Cumulative Risk over the AOT period, and Average Risk over a long period. This paper discusses the approaches followed for such optimization. Case studies are also presented. (author)

  18. Technical specifications: Perry Nuclear Power Plant, unit no. 1 (Docket no. 50-440): Appendix ''A'' to license no. NPF-58

    International Nuclear Information System (INIS)

    1986-11-01

    This report presents technical specifications for the Perry-1 Reactor in the areas of: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  19. Generic evaluation of small break loss-of-coolant accident behavior in Babcock and Wilcox designed 177-FA operating plants

    International Nuclear Information System (INIS)

    1980-01-01

    Slow system depressurization resulting from small break loss-of-coolant accidents (LOCAs) in the reactor coolant system have not, until recently, received detailed analytical study comparable to that devoted to large breaks. Following the TMI-2 accident, the staff had a series of meetings with Babcock and Wilcox (B and W) and the B and W licensees. The staff requested that B and W and the licensees: (1) systematically evaluate plant response for small break loss-of-coolant accidents; (2) address each of the concerns documented in the Michelson report; (3) validate the computer codes used against the TMI-2 accident; (4) extend the break spectrum analysis to very small breaks, giving special consideration to failure of pressurizer valves to close; (5) analyze degraded conditions where AFW is not available; (6) prepare design changes aimed at reducing the probability of loss-of-coolant accidents produced by the failure of a PORV to close; and (7) develop revised emergency procedures for small breaks. This report describes the review of the generic analyses performed by B and W based on the requests stated above

  20. Technical Note: Evaluation of individual ultraviolet radiation dosimeter sensitivity and specificity for assessing shade use.

    Science.gov (United States)

    Holcomb, K E; Stull, C L

    2017-09-01

    The effects of solar or UV radiation on livestock are often evaluated in research focused on heat stress, dermatological conditions, and other topics, with radiation measurements recorded by instrumentation at a field or local weather station for a general geographical location. Individual sensors would be valuable for quantifying an individual animal's exposure, especially as they move about in a heterogeneous environment. Individual commercially available UV dosimeters were evaluated for specificity and sensitivity and found to be potentially valuable research tools for assessing and comparing the UV radiation exposure of individual animals.

  1. Technical-evaluation report on the proposed technical-specification changes on degraded grid-voltage protection for the Rancho Seco Nuclear Generating Plant (Docket No. 50-312)

    International Nuclear Information System (INIS)

    Selan, J.C.

    1983-01-01

    This Technical Evaluation Report is a revision and contains supplemental information to the Technical Evaluations documented in previous LLNL reports dated October 1980 (UCID-18690), November 10, 1981 (UCID-19113), and July 15, 1983 (UCID-19708). These reports encompass the NRC requirements on Degraded Grid Voltage Protection and Adequacy of Station Electric Distribution System Voltages. The evaluation finds that the proposed Technical Specification changes on the undervoltage/overvoltage trip setpoints and Limiting Conditions for Operation provide the required protection to the Class 1E Equipment from sustained abnormal voltages

  2. CT-guided Bipolar and Multipolar Radiofrequency Ablation (RF Ablation) of Renal Cell Carcinoma: Specific Technical Aspects and Clinical Results

    Energy Technology Data Exchange (ETDEWEB)

    Sommer, C. M., E-mail: christof.sommer@med.uni-heidelberg.de [University Hospital Heidelberg, INF 110, Department of Diagnostic and Interventional Radiology (Germany); Lemm, G.; Hohenstein, E. [Minimally Invasive Therapies and Nuclear Medicine, SLK Kliniken Heilbronn GmbH, Clinic for Radiology (Germany); Bellemann, N.; Stampfl, U. [University Hospital Heidelberg, INF 110, Department of Diagnostic and Interventional Radiology (Germany); Goezen, A. S.; Rassweiler, J. [Clinic for Urology, SLK Kliniken Heilbronn GmbH (Germany); Kauczor, H. U.; Radeleff, B. A. [University Hospital Heidelberg, INF 110, Department of Diagnostic and Interventional Radiology (Germany); Pereira, P. L. [Minimally Invasive Therapies and Nuclear Medicine, SLK Kliniken Heilbronn GmbH, Clinic for Radiology (Germany)

    2013-06-15

    Purpose. This study was designed to evaluate the clinical efficacy of CT-guided bipolar and multipolar radiofrequency ablation (RF ablation) of renal cell carcinoma (RCC) and to analyze specific technical aspects between both technologies. Methods. We included 22 consecutive patients (3 women; age 74.2 {+-} 8.6 years) after 28 CT-guided bipolar or multipolar RF ablations of 28 RCCs (diameter 2.5 {+-} 0.8 cm). Procedures were performed with a commercially available RF system (Celon AG Olympus, Berlin, Germany). Technical aspects of RF ablation procedures (ablation mode [bipolar or multipolar], number of applicators and ablation cycles, overall ablation time and deployed energy, and technical success rate) were analyzed. Clinical results (local recurrence-free survival and local tumor control rate, renal function [glomerular filtration rate (GFR)]) and complication rates were evaluated. Results. Bipolar RF ablation was performed in 12 procedures and multipolar RF ablation in 16 procedures (2 applicators in 14 procedures and 3 applicators in 2 procedures). One ablation cycle was performed in 15 procedures and two ablation cycles in 13 procedures. Overall ablation time and deployed energy were 35.0 {+-} 13.6 min and 43.7 {+-} 17.9 kJ. Technical success rate was 100 %. Major and minor complication rates were 4 and 14 %. At an imaging follow-up of 15.2 {+-} 8.8 months, local recurrence-free survival was 14.4 {+-} 8.8 months and local tumor control rate was 93 %. GFR did not deteriorate after RF ablation (50.8 {+-} 16.6 ml/min/1.73 m{sup 2} before RF ablation vs. 47.2 {+-} 11.9 ml/min/1.73 m{sup 2} after RF ablation; not significant). Conclusions. CT-guided bipolar and multipolar RF ablation of RCC has a high rate of clinical success and low complication rates. At short-term follow-up, clinical efficacy is high without deterioration of the renal function.

  3. A technical basis to relax the dew point specification for the environment in the vapor space in DWPF canisters

    International Nuclear Information System (INIS)

    Louthan, M.R. Jr.

    1995-05-01

    This memorandum establishes the technical basis to conclude that relaxing, from 0 C to 20 C, the dew point specification for the atmosphere in the vapor space (free volume) of a DWPF canister will not provide an environment that will cause significant amounts of corrosion induced degradation of the canister wall. The conclusion is based on engineering analysis, experience and review of the corrosion literature. The basic assumptions underlying the conclusion are: (1) the canister was fabricated from Type 304L stainless steel; (2) the corrosion behavior of the canister material, including base metal, fusion zones and heat effected zones, is typified by literature data for, and industrial experience with, 300 series austenitic stainless steels; and (3) the glass-metal crevices created during the pouring operation will not alter the basic corrosion resistance of the steel although such crevices might serve as sites for the initiation of minor amounts of corrosion on the canister wall

  4. Improving the action requirements of technical specifications: A risk-comparison of continued operation and plant shutdown

    International Nuclear Information System (INIS)

    Kim, I.S.; Samanta, P.K.

    1994-01-01

    When the systems needed to remove decay heat are inoperable or degraded, the risk of shutting down the plant may be comparable to, or even higher than, that of continuing power operation with the equipment inoperable while giving priority to repairs. This concern arises because the plant may not have sufficient capability for removing decay heat during the shutdown. However, Technical Specifications (TSs) often require ''immediate'' shutdown of the plant. In this paper, the authors present risk-based analyses of the various operational policy alternatives available in such situations, with an example application to the standby service water (SSW) system of a BWR. These analyses can be used to define risk-effective requirements for those standby safety systems under discussion

  5. Critical evaluation of the nonradiological environmental technical specifications. Volume 3. Peach Bottom Atomic Power Station Units 2 and 3

    Energy Technology Data Exchange (ETDEWEB)

    Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.; Witten, A.J.

    1976-08-10

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for Units 2 and 3 of the Peach Bottom Nuclear Power Plant was conducted for the Office of Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of both the hydrothermal and ecological monitoring data collected from 1967 through 1976. Specific recommendations are made for improving both the present hydrothermal and ecological monitoring programs. Hydrothermal monitoring would be improved by more complete reporting of in-plant operating parameters. In addition, the present boat surveys could be discontinued, and monitoring efforts could be directed toward expanding the present thermograph network. Ecological monitoring programs were judged to be of high quality because standardized collection techniques, consistent reporting formats, and statistical analyses were performed on all of the data and were presented in an annual report. Sampling for all trophic groups was adequate for the purposes of assessing power plant induced perturbations. Considering the extensive period of preoperational data (six years) and operational data (three years) available for analysis, consideration could be given to reducing monitoring effort after data have been collected for a period when both units are operating at full capacity. In this way, an assessment of the potential ecological impact of the Peach Bottom facility can be made under conditions of maximum plant induced perturbations.

  6. Critical evaluation of the nonradiological environmental technical specifications. Volume 3. Peach Bottom Atomic Power Station Units 2 and 3

    International Nuclear Information System (INIS)

    Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.; Witten, A.J.

    1976-01-01

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for Units 2 and 3 of the Peach Bottom Nuclear Power Plant was conducted for the Office of Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of both the hydrothermal and ecological monitoring data collected from 1967 through 1976. Specific recommendations are made for improving both the present hydrothermal and ecological monitoring programs. Hydrothermal monitoring would be improved by more complete reporting of in-plant operating parameters. In addition, the present boat surveys could be discontinued, and monitoring efforts could be directed toward expanding the present thermograph network. Ecological monitoring programs were judged to be of high quality because standardized collection techniques, consistent reporting formats, and statistical analyses were performed on all of the data and were presented in an annual report. Sampling for all trophic groups was adequate for the purposes of assessing power plant induced perturbations. Considering the extensive period of preoperational data (six years) and operational data (three years) available for analysis, consideration could be given to reducing monitoring effort after data have been collected for a period when both units are operating at full capacity. In this way, an assessment of the potential ecological impact of the Peach Bottom facility can be made under conditions of maximum plant induced perturbations

  7. Implicit Treatment of Technical Specification and Thermal Hydraulic Parameter Uncertainties in Gaussian Process Model to Estimate Safety Margin

    Directory of Open Access Journals (Sweden)

    Douglas A. Fynan

    2016-06-01

    Full Text Available The Gaussian process model (GPM is a flexible surrogate model that can be used for nonparametric regression for multivariate problems. A unique feature of the GPM is that a prediction variance is automatically provided with the regression function. In this paper, we estimate the safety margin of a nuclear power plant by performing regression on the output of best-estimate simulations of a large-break loss-of-coolant accident with sampling of safety system configuration, sequence timing, technical specifications, and thermal hydraulic parameter uncertainties. The key aspect of our approach is that the GPM regression is only performed on the dominant input variables, the safety injection flow rate and the delay time for AC powered pumps to start representing sequence timing uncertainty, providing a predictive model for the peak clad temperature during a reflood phase. Other uncertainties are interpreted as contributors to the measurement noise of the code output and are implicitly treated in the GPM in the noise variance term, providing local uncertainty bounds for the peak clad temperature. We discuss the applicability of the foregoing method to reduce the use of conservative assumptions in best estimate plus uncertainty (BEPU and Level 1 probabilistic safety assessment (PSA success criteria definitions while dealing with a large number of uncertainties.

  8. Optimization and improvement of the technical specifications for Santa Maria de Garona and Cofrentes nuclear power plants

    International Nuclear Information System (INIS)

    Norte Gomez, M.D.; Alcantud, F.; Hoyo, C. del

    1993-01-01

    Technical Specifications (TS) form one of the basic documents necessary for licensing nuclear power plants and are required by the Government in accordance with Article 26 of the Regulation for Nuclear and Radioactive Facilities. They contain specific plant characteristics and operating limits to provide adequate protection for the safety and health of operators and the general public. For operator actuation, TS include all the surveillance requirements and limiting operating conditions (operation at full power, startup, hot and cold shutdown, and refueling outage) of safety-related systems. They also include the conventional support systems which are necessary to keep the plant in a safe operating conditioner to bring it to safe shutdown in the event of incidents or hypothetical accidents. Because of the large volume of information contained in the TS, the NRC and American utility owners began to simplify and improve the initial standard TS, which has given way to the development of a TS Optimization Program in the USA under the auspices of the NRC. Empresarios Agrupados has been contracted by the BWR Spanish Owners' Group (GPE-BWR) to develop optimized TS for the Santa Maria de Garona and Cofrentes Nuclear Power Plants. The optimized and improved TS are simplified versions of the current ones and facilitate the work of plant operators. They help to prevent risks, and reduce the number of potential transients caused by the large number of tests required by current TS. Plant operational safety is enhanced and higher effective operation is achieved. The GPE-BWR has submitted the first part of the optimized TS with their corresponding Bases to the Spanish Nuclear Council (CSN), for comment and subsequent approval. Once the TS are approved by the Spanish Nuclear Council, the operators of the Santa Maria de Garona and Cofrentes Nuclear Power Plants will be given a training and adaptation course prior to their implementation. (author)

  9. Technical specifications: Susquehanna Steam Electric Station, Unit No. 2 (Docket No. 50-388). Appendix A to License No. NPF-22

    International Nuclear Information System (INIS)

    1984-03-01

    Susquehanna Steam Electric Station, Unit 2 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  10. Technical specifications, Braidwood Station, Unit Nos. 1 and 2 (Docket Nos. STN 50-456 and STN 50-457): Appendix ''A'' to License No. NPF-70

    International Nuclear Information System (INIS)

    1987-05-01

    The Braidwood Station, Unit Nos. 1 and 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public. 18 figs., 55 tabs

  11. Technical specifications, Palo Verde Nuclear Generating Station, Unit No. 1 (Docket No. 50-528). Appendix A to License No. NPF-34

    International Nuclear Information System (INIS)

    1984-12-01

    Technical specifications are presented concerning operating safety limits for reactivity control systems, power distribution, instrumentation, coolant system, emergency core cooling system, containment systems, plant systems, electrical power systems, refueling operations, radioactive effluents, and radiological environmental monitoring; design features of the reactor site, containment, reactor core, coolant system, and fuel storage; and administrative controls

  12. Resolution 127/012. It approve the fuel quality 50-S Oil Gas characteristics within the framework of Technical Quality Specifications Rules for liquid fuel

    International Nuclear Information System (INIS)

    2012-01-01

    This resolution approves the initiative of Ancap fuel quality 50-S Oil Gas characteristics within the framework of Technical Quality Specifications Rules for liquid fuel. This resolution is according to the opinion of the National Energy Regulatory Unit and the Energy and Water Services in relation with the requirements of the current rule.

  13. Technical specifications, Waterford Steam Electric Station, Unit No. 3 (Docket No. 50-382). Appendix A to License No. NPF-38

    International Nuclear Information System (INIS)

    1985-03-01

    The Waterford, Unit 3 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  14. Heat transfer calculations for the High Flux Isotope Reactor (HFIR). Technical specifications: bases for safety limits and limiting safety system settings

    International Nuclear Information System (INIS)

    Sims, T.M.; Swanks, J.H.

    1977-09-01

    Heat transfer analyses, in support of the preparation of the HFIR technical specifications, were made to establish the bases for the safety limits and limiting safety system settings applicable to the HFIR. The results of these analyses, along with the detailed bases, are presented

  15. Technical specifications, Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322): Appendix ''A'' to License No. NPF-82

    International Nuclear Information System (INIS)

    1989-04-01

    The Shoreham, Unit 1, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public. 20 figs., 75 tabs

  16. Moving Towards a Technical Specification for Fluorescence Excitation-Emission Mapping and Absorbance Analysis of Colored Dissolved Organic Matter

    Science.gov (United States)

    Gilmore, A. M.

    2010-12-01

    Colored dissolved organic matter (CDOM) measurements with fluorescence and absorbance are important for evaluating a wide variety natural and industrial water sources. However, uncertainties and ambiguities continue to be propagated regarding interpretation of CDOM spectral data due to the variety of instruments, sampling chemistry conditions and types of analysis algorithms. Recent efforts have focused on standardization and interlaboratory comparisons of CDOM samples with respect to preparation, spectroscopic evaluation and mathematical analysis. This study deals with correlating absorbance and fluorescence data measured with the same sample to minimize interlaboratory variation. The theoretical significance of true simultaneous acquisition of the corrected (NIST Traceable) absorbance spectrum and fluorescence excitation spectral profile and excitation emission map is discussed as a means to provide the least ambiguous spectral data. Key issues considered are the variations introduced by ‘serial’ acquisitions of absorbance and fluorescence data. Variation can be caused by the different light-exposure history (especially UV) in the instruments, dissolved oxygen content associated with temperature changes and oxidation kinetics of the CDOM and in many cases concentration- and pH-related changes associated with diluting and pH buffering of the CDOM sample, respectively. Concentration changes in CDOM can be associated with optical anomalies including self-quenching and -absorption which systematically alter the fluorescence spectrum. Clearly, monitoring the absorbance and fluorescence simultaneously would deal with the above sampling variations and facilitate correcting the absorbance based fluorescence anomalies. The proposed method(s) described will be discussed in view of their potential to serve as the basis for an international technical specification in terms of the optical instrument and sampling conditions for CDOM analysis and reporting.

  17. Critical evaluation of the nonradiological environmental technical specifications. Volume 2. Surry Power Plants, Units 1 and 2

    International Nuclear Information System (INIS)

    Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.

    1976-01-01

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for Units 1 and 2 of the Surry Nuclear Power Plant was carried out for the Office of Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected from 1973 through 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The two primary methods used for temperature monitoring employ a fixed thermographs network and boat measurements. Review of data indicates that both the application and formulation of the hydrothermal monitoring program are inadequate to fully characterize the operation of the plant and the behavior of the thermal plume. Furthermore, there are no existing data that can be used to adequately verify or disprove the validity of the various Surry plume predictions. The ecological analysis includes validation of impacts predicted in the Final Environmental Statement using the operational monitoring data. Phytoplankton cell concentrations, chlorophyll a, and carbon-14 measurements were used to monitor changes in the primary producers. Densities of consumers (i.e., zooplankton, benthos, and fish) were sed to monitor changes in the primary producers. Models based on operating data were constructed to determine whether changes were occurring at each trophic level. Analysis of the monitoring data suggests that the thermal discharges at Surry are having a negative effect on the phytoplankton and zooplankton but are enhancing the benthic and nekton populations in the discharge area

  18. Critical evaluation of the nonradiological environmental technical specifications. Volume 2. Surry Power Plants, Units 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.

    1976-08-10

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for Units 1 and 2 of the Surry Nuclear Power Plant was carried out for the Office of Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected from 1973 through 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The two primary methods used for temperature monitoring employ a fixed thermographs network and boat measurements. Review of data indicates that both the application and formulation of the hydrothermal monitoring program are inadequate to fully characterize the operation of the plant and the behavior of the thermal plume. Furthermore, there are no existing data that can be used to adequately verify or disprove the validity of the various Surry plume predictions. The ecological analysis includes validation of impacts predicted in the Final Environmental Statement using the operational monitoring data. Phytoplankton cell concentrations, chlorophyll a, and carbon-14 measurements were used to monitor changes in the primary producers. Densities of consumers (i.e., zooplankton, benthos, and fish) were sed to monitor changes in the primary producers. Models based on operating data were constructed to determine whether changes were occurring at each trophic level. Analysis of the monitoring data suggests that the thermal discharges at Surry are having a negative effect on the phytoplankton and zooplankton but are enhancing the benthic and nekton populations in the discharge area.

  19. Airborne Laser Remote Sensor for Oil Detection and Classification : Engineering Requirements and Technical Considerations Relevant to a Performance Specification

    Science.gov (United States)

    1975-08-01

    This report outlines the engineering requirements for an Airborne Laser Remote Sensor for Oil Detection and Classification System. Detailed engineering requirements are given for the major units of the system. Technical considerations pertinent to a ...

  20. Technical aspects of typing for HLA-DP alleles using allele-specific DNA in vitro amplification and sequence-specific oligonucleotide probes. Detection of single base mismatches

    DEFF Research Database (Denmark)

    Fugger, L; Morling, N; Ryder, L P

    1990-01-01

    The polymerase chain reaction (PCR) is an effective method for in vitro DNA amplification which combined with probing with synthetic oligonucleotides can be used for, e.g., HLA-typing. We have studied the technical aspects of HLA-DP typing with the technique. DNA from mononuclear nucleated cells...... was extracted with either a simple salting out method or phenol/chloroform. Both DNAs could be readily used for PCR. The MgC2 concentration of the PCR buffer and the annealing temperature of the thermal cycle of the PCR were the two most important variables. The MgCl2 concentration and the temperature must...... be carefully titrated for each primer pair in the PCR. The influence of mismatches between the primer and the DNA template were studied and we found that, by using primers differing only from each other at the 3' end, cross-amplification of closely homologous alleles could be avoided. Thus, single base...

  1. UK: Technical data for waste incineration background for modelling of product-specific emissions in a life cycle assessment context

    DEFF Research Database (Denmark)

    Hauschild, Michael Zwicky

    with the disposal of a product through waste incineration. Based on knowledge of the material composition of the product and the technology applied in the waste incineration plant, the model estimates input of energy and auxiliary materials required for the incineration of the product and generation of energy...... and output of emissions to the environment caused by the incineration. The work has been performed as part of the EUREKA project EUROENVIRON 1296: LCAGAPS, sponsored by the Danish Agency for Industry and Trade. This report presents a compilation of technical data on waste incineration that serve...... as background for a model of incineration processes to be used in the inventory analysis of LCA....

  2. WHO Working Group on Technical Specifications for Manufacture and Evaluation of Yellow Fever Vaccines, Geneva, Switzerland, 13-14 May 2009.

    Science.gov (United States)

    Ferguson, Morag; Shin, Jinho; Knezevic, Ivana; Minor, Philip; Barrett, Alan

    2010-12-06

    In May 2009, WHO convened a meeting of Working Group on Technical Specifications for Manufacturing and Evaluating Yellow Fever (YF) Vaccines, Geneva, Switzerland to initiate revision of the WHO Recommendations (formerly, Requirements) for YF vaccine published in WHO Technical Report Series number 872 (1998). The Working Group, consisting of experts from academia, industry, national regulatory authorities and national control laboratories, reviewed the latest issues of safety, efficacy and quality of YF vaccines and agreed that (i) the revision should focus on live attenuated YF vaccine virus 17D lineage; and that (ii) nonclinical and clinical guidelines for new vaccines prepared from 17D lineage be developed. Copyright © 2010. Published by Elsevier Ltd.. All rights reserved.

  3. Technical specifications Limerick Generating Station, Unit No.1 (Docket No. 50-352). Appendix ''A'' to License No. NPF-39

    International Nuclear Information System (INIS)

    1985-06-01

    The specifications include: definitions, safety limits and limiting safety system settings, bases, limiting conditions for operation and surveillance requirements, design features, and administrative controls

  4. WHO Working Group on technical specifications for manufacture and evaluation of dengue vaccines, Geneva, Switzerland, 11-12 May 2009.

    Science.gov (United States)

    Trent, Dennis; Shin, Jinho; Hombach, Joachim; Knezevic, Ivana; Minor, Philip

    2010-12-06

    In May 2009, a group of international experts on dengue, vaccine quality and clinical evaluation met together (i) to review disease, vaccine pipeline, quality issues in manufacturing, issues of environmental risk assessment, nonclinical and clinical evaluation of live recombinant dengue vaccines and (ii) to initiate revising WHO guidelines for the production and quality control of candidate tetravalent dengue vaccines (live). This report summarizes an exchange of views on scientific and technical issues related to the quality, safety and efficacy of candidate dengue vaccines. Recognizing live dengue vaccines are the major vaccines in the clinical pipeline, the Working Group agreed (i) to focus on live dengue vaccines in the revision of the WHO guidelines and (ii) to add new guidelines on nonclinical and clinical evaluation, and environmental risk assessment for live dengue vaccines in the revision. Copyright © 2010. Published by Elsevier Ltd.. All rights reserved.

  5. Technical Specifications, Seabrook Station, Unit 1 (Docket No. 50-443). Appendix ''A'' to License No. NPF-56

    International Nuclear Information System (INIS)

    1986-10-01

    This report provides specifications for the Seabrook Station Unit 1 reactor concerning: safety limits and limiting safety settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  6. Technical specifications, South Texas Project, Unit No. 1 (Docket No. 50-498): Appendix ''A'' to License No. NPF-71

    International Nuclear Information System (INIS)

    1987-08-01

    This report presents specifications for the South Texas Project, Unit No. 1 concerning: safety limits, and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  7. TECHNICAL ECONOMIC FEASIBILITY OF PADDY RICE FIELDS VARIETY OF APPROACH PTT SPECIFIC LOCATIONS IN PAPUA (Case Jayapura

    Directory of Open Access Journals (Sweden)

    Afrizal Malik

    2013-01-01

    Full Text Available Study aims to determine technical economically feasibility of irrigration rice in village of Sumbe, Namblong District, Jayapura on-farm research involving farmers with an area of 2.50 ha cooperators, July to November 2011. Technology introduced: PTT, 4:1 legowo systems, seed varieties Inpari labeled 1, 2, 4, 6, 7, 9, 10, and Sintanur. Fertilizer: urea 150 kg +100 kg +100 kg SP-36 Phonska KCl +50 kg per ha. Variables: height and number of tillers 35 and 65 dap, weight of 1000 seeds, productivity, input, and output. Data were analyzed descriptively. Highest productivity in varieties Inpari 7 (7.925 tonnes per ha Milled Rice (MR and lowest Sintanur varieties (4.625 tonnes per ha MR. Pest stand: rice leaffolder and stinky rice pest. Lowest expenditure on non-cooperators Ciherang farmers IDR 12.15 million per ha per Growing Season (GS and highest in varieties Inpari 7 (IDR 15,005,000 per ha per GS. Lowest Acceptance Ciherang farmers on non-cooperators, IDR 16.4 million per ha per GS and highest in varieties Inpari 7, IDR 27.7 million per ha per GS. If farmers apply recommendation technologies using Inpari 7 varieties, farmers receiving IDR 3,173,750 per month (greater than Regional Minimum Wage of Jayapura. Need government support in order to minimize dependence on outside

  8. Congener-specific carbon isotope analysis of technical PCN and PCB preparations using 2DGC-IRMS

    Energy Technology Data Exchange (ETDEWEB)

    Horii, Y.; Yamashita, N. [National Institute of Advanced Industrial Science and Technology (AIST). Tsukuba (Japan); Petrick, G. [Kiel Univ. (Germany). Inst. fuer Marineforschung; Katase, T. [Nihon Univ., Fujisawa (Japan). College of Bioresource Sciences; Gamo, T. [Tokyo Univ. (Japan). Ocean Research Institute

    2004-09-15

    Carbon isotope analysis is one of the most traditional approaches used in biogeochemical research for the last few decades. The isotopic composition of 13C/12C in bulk carbon has been measured in many kinds of environmental matrixes and supposed to be a useful indicator to understand biogeochemical circulation of carbon in ecosystems. With the recent advancements in instrumental analysis, compound-specific carbon isotope analysis (CSIA) is emerging as a hot issue in the research area of source determination of natural products. However, only limited investigations have been reported to date, regarding the CSIA of manmade chemicals such as polychlorinated biphenyls (PCBs). Although a traditional approaches such as fingerprinting, to determine sources of specific anthropogenic chemicals in environment has been in use for decades, those techniques are relatively more qualitative than quantitative; therefore, development of novel and reliable method is required to enable comprehensive understanding of sources and environmental destiny of man-made chemicals, especially those that are hazardous ones. In this study, we developed a new approach of CSIA using two-dimensional gas chromatograph (2DGC) with combustion chamber (C)/ isotope ratio mass spectrometer (IRMS) and applied for ''congener-specific'' carbon isotopic analysis of PCBs and polychlorinated naphthalenes (PCNs). We clarified the need to solve the co-elution of individual chlorobiphenyl and chloronaphthalene congeners and to decrease the blank for ''congener-specific'' CSIA.

  9. Environmental consequences of postulated plutonium releases from the Babcock and Wilcox Plant, Leechburg, Pennsylvania, as a result of severe natural phenomena

    International Nuclear Information System (INIS)

    McPherson, R.B.; Watson, E.C.

    1979-03-01

    Potential environmental consequences in terms of radiation dose to people are presented for postulated plutonium releases accidently caused by severe natural phenomena at the Babcock and Wilcox plant, Leechburg, Pennsylvania. The severe natural phenomena considered are earthquakes, tornadoes, high straight-line winds, and floods. Maximum plutonium deposition values are given for significant locations around the site. All important potential exposure pathways are examined. The most likely 50-year committed dose equivalents are given for the maximum-exposed individual and the population within a 50-mile radius of the plant. The maximum plutonium deposition values most likely to occur at the site boundary are also given. The most likely calculated 50-year collective committed dose equivalents are all much lower than the collective dose equivalent expected from 50 years of exposure to natural background radiation and medical x-rays. The most likely maximum residual plutonium contamination estimated to be deposited at the site boundary following Earthquake No. 3, the 110-mph and 130-mph winds, and the 130 mph tornado are above the Environmental Protection Agency's (EPA) proposed guideline for plutonium in the general environment of 0.2 μCi/m 2

  10. High-intensity efforts in elite soccer matches and associated movement patterns, technical skills and tactical actions. Information for position-specific training drills.

    Science.gov (United States)

    Ade, Jack; Fitzpatrick, John; Bradley, Paul S

    2016-12-01

    This study aimed to translate movement patterns, technical skills and tactical actions associated with high-intensity efforts into metrics that could potentially be used to construct position-specific conditioning drills. A total of 20 individual English Premier League players' high-intensity running profiles were observed multiple times (n = 100) using a computerised tracking system. Data were analysed using a novel high-intensity movement programme across five positions (centre back [CB], full-back [FB], central midfielder [CM], wide midfielder [WM] and centre forward [CF]). High-intensity efforts in contact with the ball and the average speed of efforts were greater in WMs than CBs, CMs and CFs (effect sizes [ES]: 0.9-2.1, P high-intensity trends in and out of possession that could assist practitioners when devising position-specific drills.

  11. Identifying priority technical and context-specific issues in improving the conduct, reporting and use of health economic evaluation in low- and middle-income countries.

    Science.gov (United States)

    Luz, Alia; Santatiwongchai, Benjarin; Pattanaphesaj, Juntana; Teerawattananon, Yot

    2018-02-05

    The use of economic evaluation in healthcare policies and decision-making, which is limited in low- and middle-income countries (LMICs), might be promoted through the improvement of the conduct and reporting of studies. Although the literature indicates that there are many issues affecting the conduct, reporting and use of this evidence, it is unclear which factors should be prioritised in finding solutions. This study aims to identify the top priority issues that impede the conduct, reporting and use of economic evaluation as well as potential solutions as an input for future research topics by the international Decision Support Initiative and other movements. A survey on issues regarding the conduct, reporting and use of economic evaluation as well as on potential solutions was conducted using an online questionnaire among researchers who have experience in conducting economic evaluations in LMICs. The respondents were requested to consider the list of issues provided, rank the most important ones and propose solutions. A scoring system was applied to derive the ranking of difficulties according to researchers' responses. Issues were grouped into technical and context-specific difficulties and analysed separately as a whole and by region. Researchers considered the lack of quality local clinical data, poor reporting and insufficient data to conduct the analysis from the chosen perspective as the most important technical difficulties. On the other hand, the non-integration of economic evaluations into decision-making was considered the most important context-specific issue. Finally, context-specific issues were considered the larger barrier to the use of economic evaluation. The technical issues that were considered most important were closely linked with the lack of an appropriately functioning information system as well as the capacity to generate essential contextual information (e.g. data and locally relevant utility values), especially when the methodology is

  12. Patient-specific reconstruction plates are the missing link in computer-assisted mandibular reconstruction: A showcase for technical description.

    Science.gov (United States)

    Cornelius, Carl-Peter; Smolka, Wenko; Giessler, Goetz A; Wilde, Frank; Probst, Florian A

    2015-06-01

    Preoperative planning of mandibular reconstruction has moved from mechanical simulation by dental model casts or stereolithographic models into an almost completely virtual environment. CAD/CAM applications allow a high level of accuracy by providing a custom template-assisted contouring approach for bone flaps. However, the clinical accuracy of CAD reconstruction is limited by the use of prebent reconstruction plates, an analogue step in an otherwise digital workstream. In this paper the integration of computerized, numerically-controlled (CNC) milled, patient-specific mandibular plates (PSMP) within the virtual workflow of computer-assisted mandibular free fibula flap reconstruction is illustrated in a clinical case. Intraoperatively, the bone segments as well as the plate arms showed a very good fit. Postoperative CT imaging demonstrated close approximation of the PSMP and fibular segments, and good alignment of native mandible and fibular segments and intersegmentally. Over a follow-up period of 12 months, there was an uneventful course of healing with good bony consolidation. The virtual design and automated fabrication of patient-specific mandibular reconstruction plates provide the missing link in the virtual workflow of computer-assisted mandibular free fibula flap reconstruction. Copyright © 2015 European Association for Cranio-Maxillo-Facial Surgery. Published by Elsevier Ltd. All rights reserved.

  13. Technical note: Protozoa-specific antibodies raised in sheep plasma bind to their target protozoa in the rumen.

    Science.gov (United States)

    Williams, Y J; Rea, S M; Popovski, S; Skillman, L C; Wright, A-D G

    2014-12-01

    Binding of IgG antibodies to Entodinium spp. in the rumen of sheep (Ovis aries) was investigated by adding IgG, purified from plasma, directly into the rumen. Plasma IgG was sourced from sheep that had or had not been immunized with a vaccine containing whole fixed Entodinium spp. cells. Ruminal fluid was sampled approximately 2 h after each antibody dosing. Binding of protozoa by a specific antibody was detected using an indirect fluorescent antibody test. An antibody titer in the ruminal fluid was determined by ELISA, and the concentration of ruminal fluid ammonia-N and ruminal pH were also determined. Entodinium spp. and total protozoa from IgG-infused sheep were enumerated by microscopic counts. Two-hourly additions of IgG maintained a low antibody titer in the rumen for 12 h and the binding of the antibody to the rumen protozoa was demonstrated. Increased ammonia-N concentrations and altered ruminal fluid pH patterns indicated that additional fermentation of protein was occurring in the rumen after addition of IgG. No reduction in numbers of Entodinium spp. was observed (P>0.05). Although binding of antibodies to protozoa has been demonstrated in the rumen, it is unclear how much cell death occurred. On the balance of probability, it would appear that the antibody was degraded or partially degraded, and the impact of this on protozoal populations and the measurement of a specific titer is also unclear.

  14. Technical documentation in support of the project-specific analysis for construction and operation of the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lazaro, M.A.; Vinikour, W. [Argonne National Lab., IL (United States). Environmental Assessment Div.; Allison, T. [Argonne National Lab., IL (United States). Decision and Information Sciences Div.] [and others

    1996-09-01

    This document provides information that supports or supplements the data and impact analyses presented in the National Ignition Facility (NIF) Project-Specific Analysis (PSA). The purposes of NIF are to achieve fusion ignition in the laboratory for the first time with inertial confinement fusion (ICF) technology and to conduct high- energy-density experiments ins support of national security and civilian application. NIF is an important element in the DOE`s science-based SSM Program, a key mission of which is to ensure the reliability of the nation`s enduring stockpile of nuclear weapons. NIF would also advance the knowledge of basic and applied high-energy- density science and bring the nation a large step closer to developing fusion energy for civilian use. The NIF PSA includes evaluations of the potential environmental impacts of constructing and operating the facility at one of five candidate site and for two design options.

  15. Determination dimension and technical specification of the cylindrical pneumatics for the tote movement on multipurpose the gamma irradiator BATAN

    International Nuclear Information System (INIS)

    Muhammad Subhan; Ari Satmoko

    2016-01-01

    BATAN develops irradiator gamma category IV in cooperation with IZOTOP (Hungary). Transportation technology products that will be developed uses rail system to pool. Products that will be irradiated are put into tote then placed on the transportation rail, when tote has been in irradiated room tote enters into irradiated rack. The movement of the tote during on irradiated rack will be driven by the pneumatic system. Based on data from Isotop there are 14 cylindrical pneumatics that are in the irradiated room. Through the results analysis then used double acting cylinder type from the Festo pneumatics catalog. Through the results calculation that the force used on all types of cylinders for movement tote still much smaller than of force bent permitted. Beside that there are 4 group a pneumatic have common specifications they are group one cylindrical C1, C3, C12 and C14 they are group two cylindrical C2, C4, C11, and C13 they are group three cylindrical C7, C9, C15 and C17 they are group four cylindrical C10 and C17. (author)

  16. Sphere-Enhanced Microwave Ablation (sMWA) Versus Bland Microwave Ablation (bMWA): Technical Parameters, Specific CT 3D Rendering and Histopathology

    Energy Technology Data Exchange (ETDEWEB)

    Gockner, T. L., E-mail: theresa.gockner@med.uni-heidelberg.de [University Hospital Heidelberg, Department of Diagnostic and Interventional Radiology (Germany); Zelzer, S., E-mail: s.zelzer@dkfz-heidelberg.de [German Cancer Research Center (dkfz), Medical and Biological Informatics (Germany); Mokry, T., E-mail: theresa.mokry@med.uni-heidelberg.de; Gnutzmann, D., E-mail: daniel.gnutzmann@med.uni-heidelberg.de; Bellemann, N., E-mail: nadine.bellemann@med.uni-heidelberg.de [University Hospital Heidelberg, Department of Diagnostic and Interventional Radiology (Germany); Mogler, C., E-mail: carolin.mogler@med.uni-heidelberg.de [University Hospital Heidelberg, Department of General Pathology (Germany); Beierfuß, A., E-mail: anja.beierfuss@ethianum.de; Köllensperger, E., E-mail: eva.koellensperger@ethianum.de; Germann, G., E-mail: guenter.germann@ethianum.de [Ethianum Heidelberg, Clinic for Plastic Reconstructive Surgery and Aesthetic Surgery (Germany); Radeleff, B. A., E-mail: boris.radeleff@med.uni-heidelberg.de; Stampfl, U., E-mail: ulrike.stampfl@med.uni-heidelberg.de; Kauczor, H. U., E-mail: hu.kauczor@med.uni-heidelberg.de [University Hospital Heidelberg, Department of Diagnostic and Interventional Radiology (Germany); Pereira, P. L., E-mail: philippe.pereira@slk-kliniken.de [SLK Kliniken Heilbronn GmbH, Clinic for Radiology, Minimally-invasive Therapies and Nuclear Medicine (Germany); Sommer, C. M., E-mail: christof.sommer@med.uni-heidelberg.de [University Hospital Heidelberg, Department of Diagnostic and Interventional Radiology (Germany)

    2015-04-15

    PurposeThis study was designed to compare technical parameters during ablation as well as CT 3D rendering and histopathology of the ablation zone between sphere-enhanced microwave ablation (sMWA) and bland microwave ablation (bMWA).MethodsIn six sheep-livers, 18 microwave ablations were performed with identical system presets (power output: 80 W, ablation time: 120 s). In three sheep, transarterial embolisation (TAE) was performed immediately before microwave ablation using spheres (diameter: 40 ± 10 μm) (sMWA). In the other three sheep, microwave ablation was performed without spheres embolisation (bMWA). Contrast-enhanced CT, sacrifice, and liver harvest followed immediately after microwave ablation. Study goals included technical parameters during ablation (resulting power output, ablation time), geometry of the ablation zone applying specific CT 3D rendering with a software prototype (short axis of the ablation zone, volume of the largest aligned ablation sphere within the ablation zone), and histopathology (hematoxylin-eosin, Masson Goldner and TUNEL).ResultsResulting power output/ablation times were 78.7 ± 1.0 W/120 ± 0.0 s for bMWA and 78.4 ± 1.0 W/120 ± 0.0 s for sMWA (n.s., respectively). Short axis/volume were 23.7 ± 3.7 mm/7.0 ± 2.4 cm{sup 3} for bMWA and 29.1 ± 3.4 mm/11.5 ± 3.9 cm{sup 3} for sMWA (P < 0.01, respectively). Histopathology confirmed the signs of coagulation necrosis as well as early and irreversible cell death for bMWA and sMWA. For sMWA, spheres were detected within, at the rim, and outside of the ablation zone without conspicuous features.ConclusionsSpecific CT 3D rendering identifies a larger ablation zone for sMWA compared with bMWA. The histopathological signs and the detectable amount of cell death are comparable for both groups. When comparing sMWA with bMWA, TAE has no effect on the technical parameters during ablation.

  17. Towards the development of technical specifications for the production of lithium-lead alloys for the ITER HCLL TMB

    Energy Technology Data Exchange (ETDEWEB)

    Barrado, Ana Isabel, E-mail: anaisabel.barrado@ciemat.es [CIEMAT. Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas (Spain); Conde, Estefania; Fernandez, Marta [CIEMAT. Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas (Spain); Gomez-Salazar, Jose Maria [UCM. Dpto. De Ciencia de Materiales e Ingenieria Metalurgica (Spain); Quejido, Alberto; Quinones, Javier [CIEMAT. Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas (Spain)

    2012-08-15

    Highlights: Black-Right-Pointing-Pointer Pb-Li alloy plays a key role in the new commercial fusion reactors functionality. Black-Right-Pointing-Pointer It is important to have a complete characterization to define their physicochemical properties. Black-Right-Pointing-Pointer Methodology developed is a key tool that allows performing quality control procedures. Black-Right-Pointing-Pointer Determine concentrations of major and trace elements, which can be found in Pb-Li alloy. - Abstract: The ITER and DEMO projects are developing new Test Blanket Modules (TBM), where the Pb-Li alloy plays a key role in the new commercial fusion reactors functionality. The Breeding Blanket (BB) has to perform several functions which are essential for the reactor operation. The HCLL TBM is one of the Breeding Blanket concepts to be tested in ITER. It is cooled by He and uses the eutectic liquid metal LLE (Lithium-Lead Eutectic) as breeder material (enriched at 90% in {sup 6}Li). Pb-Li eutectic alloy has no known uses outside of fusion technology, so the available databases of this material are currently incomplete. It is very important, within the material specifications, to have a complete characterization in order to define their chemical and physical properties, because any variation in the alloy composition has significant consequences in their behaviour, and therefore in their regenerative function inside the blanket. The chemical characterization methodology developed and presented in this paper (useful for both Pb-Li alloys as any Pb alloy) is a key tool that allows performing standard quality control procedures for base material and/or monitoring the alloy during the reactor operation. This report provides a procedure to perform a wide material chemical characterization, assessing the concentrations of major elements, as well as a review of trace level elements that can be found both in the eutectic alloy and in starting materials. In this determination plays an important

  18. RAMS+C informed decision-making with application to multi-objective optimization of technical specifications and maintenance using genetic algorithms

    International Nuclear Information System (INIS)

    Martorell, S.; Villanueva, J.F.; Carlos, S.; Nebot, Y.; Sanchez, A.; Pitarch, J.L.; Serradell, V.

    2005-01-01

    The role of technical specifications and maintenance (TSM) activities at nuclear power plants (NPP) aims to increase reliability, availability and maintainability (RAM) of Safety-Related Equipment, which, in turn, must yield to an improved level of plant safety. However, more resources (e.g. costs, task force, etc.) have to be assigned in above areas to achieve better scores in reliability, availability, maintainability and safety (RAMS). Current situation at NPP shows different programs implemented at the plant that aim to the improvement of particular TSM-related parameters where the decision-making process is based on the assessment of the impact of the change proposed on a subgroup of RAMS+C attributes. This paper briefly reviews the role of TSM and two main groups of improvement programs at NPP, which suggest the convenience of considering the approach proposed in this paper for the Integrated Multi-Criteria Decision-Making on changes to TSM-related parameters based on RAMS+C criteria as a whole, as it can be seem as a decision-making process more consistent with the role and synergic effects of TSM and the objectives and goals of current improvement programs at NPP. The case of application to the Emergency Diesel Generator system demonstrates the viability and significance of the proposed approach for the Multi-objective Optimization of TSM-related parameters using a Genetic Algorithm

  19. Technical presentation

    CERN Multimedia

    GS Department

    2010-01-01

    10 March 2010 DYNEOS 10:00 – 12:00 - Main Building, Room B, 61-1-009 Dyneos AG is active in the fields of photonics, laser and high-precision positioning. Our highly qualified engineer team has more than 30 years of experience in electro-optical solutions sales. The engineers are supported by a technical and administrative team. We are focused on the Swiss market and represent six suppliers (Coherent, PI Physik Instrumente, SIOS, Nanonics Imaging, APE, Ekspla) in order to give a qualified sales and service support to our customers. Our products are dedicated to the research field as well as to industry. In addition to standard catalog products, we offer custom designs to fulfill the specific needs of OEM customers or specific applications.

  20. Technical specifications, Braidwood Station Unit Nos. 1 and 2 (Docket Nos. STN 50-456 and STN 50-457): Appendix ''A'' to License No. NPF-72, [October 1986-July 1987

    International Nuclear Information System (INIS)

    1987-07-01

    The Braidwood Station, Units 1 and 2, technical specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  1. Technical specifications, South Texas Project, Unit Nos. 1 and 2 (Docket Nos. 50-498 and 50-499): Appendix ''A'' to License Nos. NPF-76 and NPF-78

    International Nuclear Information System (INIS)

    1989-01-01

    The South Texas Project, Unit Nos. 1 and 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  2. Technical Specifications, South Texas Project, Unit Nos. 1 and 2 (Docket Nos. 50-498 and 50-499): Appendix ''A'' to License Nos. NPF-76 and NPF-80

    International Nuclear Information System (INIS)

    1989-03-01

    The South Texas Project, Unit Nos. 1 and 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  3. Congener-specific analysis of polychlorinated naphthalenes (PCNs) in the major Chinese technical PCB formulation from a stored Chinese electrical capacitor.

    Science.gov (United States)

    Huang, Jun; Yu, Gang; Yamauchi, Makoto; Matsumura, Toru; Yamazaki, Norimasa; Weber, Roland

    2015-10-01

    Impurity of polychlorinated naphthalenes (PCNs) in commercial polychlorinated biphenyl (PCB) formulations has been recognized as a relevant source of PCNs in the environment. Congener-specific analysis of most main PCB formulations has been accomplished previously, excluding the Chinese product. The insulating oil in a stored Chinese electric capacitor containing the major Chinese technical formulation "PCB3" was sampled and tested by isotope dilution technology using high-resolution gas chromatography coupled to high-resolution mass spectrometry (HRGC/HRMS). The detected concentration of PCNs in the Chinese PCB oil sample was 1,307.5 μg/g and therefore significantly higher than that reported in PCB formulations from other countries, as well as that in the transformer oil (ASKAREL Nr 1740) additionally tested in the present study for comparison. Based on the measurement, the total amount of PCNs in Chinese PCB3 oil is estimated to be 7.8 t, which would mean only 0.005 % of global production of PCNs of 150,000 t. The homolog profile is similar to those of PCN in Aroclor 1262 and Clophen A40, where the contributions from hexa-CNs and hepta-CNs are predominant and accounted for similar proportions. The Toxic Equivalent Quantity (TEQ) concentration of dioxin-like PCN congeners is 0.47 μg TEQ/g, with the dominant contributors of CN-73 and CN-66/67. This TEQ content from PCN is higher than that in most other PCB formulations with the exemption of the Russian Sovol formulation. The total TEQ in the historic 6,000 t of the Chinese PCB3 formulation is estimated to be 2.8 kg TEQ.

  4. Recycled aggregate in road construction following the Spanish General Technical Specifications for Roads and Bridge Works (PG-3: a case study

    Directory of Open Access Journals (Sweden)

    Martín-Morales, M.

    2013-03-01

    Full Text Available This research characterizes four samples of recycled aggregate for their potential use in road construction projects in consonance with the Spanish General Technical Specifications for Roads and Bridge Works (PG-3. Although some fractions were of sufficient quality for the construction of embankments, backfills, and quarry-run fills, they were ultimately found to be unsuitable for the construction of underground drainage, granular structural layers, soil stabilization and concrete pavements. They were negatively evaluated because of their particle size distribution and sulfate content. Nevertheless, the quality of this recycled aggregate could be substantially improved by manually removing the gypsum before the crushing process at the plant or by selecting the material with greater care at the beginning of the process. Finally, we suggest that Construction and Demolition (C&D waste plant managers should modify the manufacturing process to obtain a suitable particle size distribution in accordance with PG-3 requirements and the projected use of the aggregate.

    En esta investigación se han caracterizado cuatro muestras de árido reciclado para su potencial uso en obras de carreteras en España siguiendo el Pliego de Prescripciones Técnicas Generales para Obras de Carreteras y Puentes (PG-3. Aunque algunas fracciones presentaron suficiente calidad para la construcción de terraplenes, rellenos localizados y rellenos todo en uno, resultaron inadecuadas para la construcción de drenes subterráneos, zahorras, suelos estabilizados y pavimentos de hormigón. Obtuvieron una evaluación negativa en cuanto a distribución granulométrica y contenido en sulfatos. No obstante, la calidad de este árido reciclado podría mejorar sustancialmente eliminando manualmente el yeso antes de la trituración en planta o seleccionando el material con un mayor cuidado al inicio del proceso. Finalmente, recomendamos que los empresarios de las plantas de residuos

  5. Imagining Technicities

    DEFF Research Database (Denmark)

    Liboriussen, Bjarke; Plesner, Ursula

    2011-01-01

    to the elements of taste and skill. In the final analysis those references were synthesized as five imagined technicities: the architect, the engineer, the client, the Chinese, and the Virtual World native. Because technicities are often assumed and rarely discussed as actants who influence practice, their role......, this article focuses on innovative uses of virtual worlds in architecture. We interviewed architects, industrial designers and other practitioners. Conceptually supported by an understanding of technicity found in Cultural Studies, the interviews were then coded with a focus on interviewees’ references...... in cooperation and development of ICTs seems to pass unnoticed. However, since they are aligned into ICTs, technicities impact innovation....

  6. OSH technical reference manual

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    In an evaluation of the Department of Energy (DOE) Occupational Safety and Health programs for government-owned contractor-operated (GOCO) activities, the Department of Labor`s Occupational Safety and Health Administration (OSHA) recommended a technical information exchange program. The intent was to share written safety and health programs, plans, training manuals, and materials within the entire DOE community. The OSH Technical Reference (OTR) helps support the secretary`s response to the OSHA finding by providing a one-stop resource and referral for technical information that relates to safe operations and practice. It also serves as a technical information exchange tool to reference DOE-wide materials pertinent to specific safety topics and, with some modification, as a training aid. The OTR bridges the gap between general safety documents and very specific requirements documents. It is tailored to the DOE community and incorporates DOE field experience.

  7. Unit-specific calibration of Actigraph accelerometers in a mechanical setup - is it worth the effort? The effect on random output variation caused by technical inter-instrument variability in the laboratory and in the field

    DEFF Research Database (Denmark)

    Moeller, Niels C; Korsholm, Lars; Kristensen, Peter L

    2008-01-01

    *min-1 vs. calibrated SDbetween units = 67 counts*min-1). However, the effect of applying the derived calibration to children's and adolescents' free living physical activity data did not alter the coefficient of variation (CV) (children: CVraw = 30.2% vs. CVcalibrated = 30.4%, adolescents: CVraw = 36...... accelerometers in a mechanical setup using four different settings varying in frequencies and/or amplitudes. Calibration effect was analysed by comparing raw and calibrated data after applying unit-specific calibration factors to data obtained during quality checks in a mechanical setup and to data collected...... conditions had no apparent effect on inter-instrument variability. In all probability, the effect of technical calibration was primarily attenuated in the field by other more dominant sources of variation. However, routine technical assessments are still very important for determining the acceleration...

  8. Technical Network

    CERN Multimedia

    2007-01-01

    In order to optimize the management of the Technical Network (TN), to ease the understanding and purpose of devices connected to the TN, and to improve security incident handling, the Technical Network Administrators and the CNIC WG have asked IT/CS to verify the "description" and "tag" fields of devices connected to the TN. Therefore, persons responsible for systems connected to the TN will receive email notifications from IT/CS asking them to add the corresponding information in the network database. Thank you very much for your cooperation. The Technical Network Administrators & the CNIC WG

  9. Technical Network

    CERN Multimedia

    2007-01-01

    In order to optimise the management of the Technical Network (TN), to facilitate understanding of the purpose of devices connected to the TN and to improve security incident handling, the Technical Network Administrators and the CNIC WG have asked IT/CS to verify the "description" and "tag" fields of devices connected to the TN. Therefore, persons responsible for systems connected to the TN will receive e-mails from IT/CS asking them to add the corresponding information in the network database at "network-cern-ch". Thank you very much for your cooperation. The Technical Network Administrators & the CNIC WG

  10. Methodology for technical risk assessment

    International Nuclear Information System (INIS)

    Waganer, L.M.; Zuckerman, D.S.

    1983-01-01

    A methodology has been developed for and applied to the assessment of the technical risks associated with an evolving technology. This methodology, originally developed for fusion by K. W. Billman and F. R. Scott at EPRI, has been applied to assess the technical risk of a fuel system for a fusion reactor. Technical risk is defined as the risk that a particular technology or component which is currently under development will not achieve a set of required technical specifications (i.e. probability of failure). The individual steps in the technical risk assessment are summarized. The first step in this methodology is to clearly and completely quantify the technical requirements for the particular system being examined. The next step is to identify and define subsystems and various options which appear capable of achieving the required technical performance. The subsystem options are then characterized regarding subsystem functions, interface requirements with the subsystems and systems, important components, developmental obstacles and technical limitations. Key technical subsystem performance parameters are identified which directly or indirectly relate to the system technical specifications. Past, existing and future technical performance data from subsystem experts are obtained by using a Bayesian Interrogation technique. The input data is solicited in the form of probability functions. Thus the output performance of the system is expressed as probability functions

  11. Mechanical Engineering Department Technical Review

    Energy Technology Data Exchange (ETDEWEB)

    Carr, R.B.; Denney, R.M. (eds.)

    1981-07-01

    The Mechanical Engineering Department Technical Review is published to inform readers of various technical activities within the Department, promote exchange of ideas, and give credit to personnel who are achieving the results. The report is presented in two parts: technical achievements and publication abstracts. The first is divided into seven sections, each of which reports on an engineering division and its specific activities related to nuclear tests, nuclear explosives, weapons, energy systems, engineering sciences, magnetic fusion, and materials fabrication.

  12. Mechanical Engineering Department Technical Review

    International Nuclear Information System (INIS)

    Carr, R.B.; Denney, R.M.

    1981-01-01

    The Mechanical Engineering Department Technical Review is published to inform readers of various technical activities within the Department, promote exchange of ideas, and give credit to personnel who are achieving the results. The report is presented in two parts: technical achievements and publication abstracts. The first is divided into seven sections, each of which reports on an engineering division and its specific activities related to nuclear tests, nuclear explosives, weapons, energy systems, engineering sciences, magnetic fusion, and materials fabrication

  13. Specific PVMaT R and D in CdTe Product Manufacturing; Phase II Annual Subcontract Technical Report; May 1999--September 2000

    Energy Technology Data Exchange (ETDEWEB)

    McMaster, A. (First Solar, LLC)

    2001-01-22

    Just prior to the beginning of Phase II of the PVMaT project Solar Cells, Inc, (SCI) and True North Partners of Scottsdale, AZ, formed a joint venture partnership name First Solar, LLC. By the end of 1999, this event resulted in the construction of a new major manufacturing plant for photovoltaic modules, based on cadmium telluride, located in Perrysburg, a suburb of Toledo, Ohio. This plant was designed to be capable of producing PV modules at a rate of 100 MW per year within about three years. Significantly, a new semiconductor coating system, the heat of the production line, has already shown the capability of the 100 MW per year rate. These events have led to the expansion of the effort on the PVMaT project that included the former SCI team in Toledo, Ohio, a new team of engineering subcontractor, Product Search, Inc., and, later, a new laser team from First Solar, both from Scottsdale, Arizona. These three teams joined in a collaborative effort on Tasks 4: Manufacturing Line Improvements, on Task 5: Product Readiness, and on Task Environmental, Health, and Safety Issues. One Task 4 goal was to address the technical issues of the failed UL 1703 qualification testing in Phase I. Completing this goal, along with module lamination improvement done in Task 5, was instrumental in the design, fabrication, and installation of a high-throughput solar finishing line. The main components of this line, also a Task 4 project, were successfully tested in module finalization on the production line. Developing a novel, single-laser scribing system was another major accomplishment. In Task 5, the major activity was improved module lamination. Progress in Tasks 4 and 5 resulted in improved modules that were submitted for UL 1703 qualification testing. In March 2000, a new encapsulation process came under development, in which the back glass cover plate is substituted by a combination of a polymer layer as a dielectric and aluminum foil as a moisture barrier. The go al of the

  14. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball

    2010-01-01

    Operational Experience At the end of the first full-year running period of LHC, CMS is established as a reliable, robust and mature experiment. In particular common systems and infrastructure faults accounted for <0.6 % CMS downtime during LHC pp physics. Technical operation throughout the entire year was rather smooth, the main faults requiring UXC access being sub-detector power systems and rack-cooling turbines. All such problems were corrected during scheduled technical stops, in the shadow of tunnel access needed by the LHC, or in negotiated accesses or access extensions. Nevertheless, the number of necessary accesses to the UXC averaged more than one per week and the technical stops were inevitably packed with work packages, typically 30 being executed within a few days, placing a high load on the coordination and area management teams. It is an appropriate moment for CMS Technical Coordination to thank all those in many CERN departments and in the Collaboration, who were involved in CMS techni...

  15. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball

    2010-01-01

    Operational Experience Since the closure of the detector in February, the technical operation of CMS has been quite smooth and reliable. Some minor interventions in UXC were required to cure failures of power supplies, fans, readout boards and rack cooling connections, but all these failures were repaired in scheduled technical stops or parasitically during access dedicated to fixing LHC technical problems. The only occasion when CMS had to request an access between fills was to search for the source of an alarm from the leak-detection cables mounted in the DT racks. After a few minutes of diagnostic search, a leaking air-purge was found. Replacement was complete within 2 hours. This incident demonstrated once more the value of these leak detection cables; the system will be further extended (during the end of year technical stop) to cover more racks in UXC and the floor beneath the detector. The magnet has also been operating reliably and reacted correctly to the 14s power cut on 29 May (see below). In or...

  16. Technical endoscopy

    International Nuclear Information System (INIS)

    Cavalar, K.O.

    1988-01-01

    A survey is provided on different versions of endoscopes, taking into account the new developments of video endoscopy. With a variety of practical examples it is shown that technical tests using endoscopy are a demanding task for nondestructive testing, whose requirements can only be met on a customized basis. (orig./HP) [de

  17. Technical Training: Technical Training Seminar

    CERN Multimedia

    2004-01-01

    TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch Monday 9 February 2004 From 10:00 to 12:00 - IT Auditorium - bldg. 31, 3rd floor ANSOFT High-Frequency Seminar David Prestaux, Application Engineer, ANSOFT F-78535 BUC, France This Technical Training seminar will present two Ansoft application products: Ansoft HFSS and Ansoft Designer. Ansoft HFSS makes use of the Finite Element Method (FEM) to calculate field solutions from first principles. It can accurately predict all high-frequency behaviours such as dispersion, mode conversion, and losses due to materials and radiation. Ansoft Designer is a suite of design tools to fully integrate high-frequency, physics-based electromagnetic simulations into a seamless system-level simulation environment. Ansoft Designer uses a simple interface to give complete control over every design task, by a method allowing multiple solvers, Solver on Demand. • Introduction • Overview of the Ansoft Total solution • Ansoft HFSS 9...

  18. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball

    Overview From a technical perspective, CMS has been in “beam operation” state since 6th November. The detector is fully closed with all components operational and the magnetic field is normally at the nominal 3.8T. The UXC cavern is normally closed with the radiation veto set. Access to UXC is now only possible during downtimes of LHC. Such accesses must be carefully planned, documented and carried out in agreement with CMS Technical Coordination, Experimental Area Management, LHC programme coordination and the CCC. Material flow in and out of UXC is now strictly controlled. Access to USC remains possible at any time, although, for safety reasons, it is necessary to register with the shift crew in the control room before going down.It is obligatory for all material leaving UXC to pass through the underground buffer zone for RP scanning, database entry and appropriate labeling for traceability. Technical coordination (notably Stephane Bally and Christoph Schaefer), the shift crew and run ...

  19. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball and W. Zeuner

    2011-01-01

    In this report we will review the main achievements of the Technical Stop and the progress of several centrally-managed projects to support CMS operation and maintenance and prepare the way for upgrades. Overview of the extended Technical Stop  The principal objectives of the extended Technical Stop affecting the detector itself were the installation of the TOTEM T1 telescopes on both ends, the readjustment of the alignment link-disk in YE-2, the replacement of the light-guide sleeves for all PMs of both HFs, and some repairs on TOTEM T2 and CASTOR. The most significant tasks were, however, concentrated on the supporting infrastructure. A detailed line-by-line leak search was performed in the C6F14 cooling system of the Tracker, followed by the installation of variable-frequency drives on the pump motors of the SS1 and SS2 tracker cooling plants to reduce pressure transients during start-up. In the electrical system, larger harmonic filters were installed in ...

  20. Technical Training: Technical Training Seminar

    CERN Multimedia

    2004-01-01

    Tuesday 30 March TECHNICAL TRAINING SEMINAR From 9:00 to 12:00 and from 13:00 to 16:00 hrs - Council Chamber, Salle B, Salle des Pas Perdus National Instruments (NI) on Tour 2004 Claudia Jüngel, Evrem Yarkin, Joel Clerc, Hervé Baour / NATIONAL INSTRUMENTS The special event NI on Tour 2004, run in Germany, Austria and Switzerland, will be at CERN on March 30. Technical seminars and free introductory courses will be offered all day long in the Council Chamber, Salle B, and Salle des Pas Perdus (buildings 61 and 503). Technical conferences: 09:00 - 12:00 Data acquisition systems on PCs. Industrial measurement and control techniques. 13:00 - 16:00 Advanced LabVIEW software and PXI instrumentation. Measuring instruments and system components for teststand automation. Introductory courses: 09:00 - 12:00 DIAdem: Data analysis and presentation 13:00 - 16:00 Data acquisition with LabVIEW Language: English and French Free special seminar. Registration is recommended with National Instruments Switzerland (please sp...

  1. Technical Training: Technical Training Seminar

    CERN Multimedia

    2004-01-01

    Tuesday 30 March TECHNICAL TRAINING SEMINAR From 9:00 to 12:00 and from 13:00 to 16:00 hrs - Council Chamber, Salle B, Salle des Pas Perdus National Instruments (NI) on Tour 2004 Claudia Jüngel, Evrem Yarkin, Joel Clerc, Hervé Baour / NATIONAL INSTRUMENTS The special event NI on Tour 2004, run in Germany, Austria and Switzerland, will be at CERN on March 30. Technical seminars and free introductory courses will be offered all day long in the Council Chamber, Salle B, and Salle des Pas Perdus (buildings 61 and 503). Technical conferences: 09:00 - 12:00 Data acquisition systems on PCs. Industrial measurement and control techniques. 13:00 - 16:00 Advanced LabVIEW software and PXI instrumentation. Measuring instruments and system components for teststand automation. Introductory courses: 09:00 - 12:00 DIAdem: Data analysis and presentation 13:00 - 16:00 Data acquisition with LabVIEW Language: English and French Free special seminar. Registration is recommended with National Instruments Swi...

  2. INDOT Technical Training Plan : [Technical Summary

    Science.gov (United States)

    2012-01-01

    A wide range of job classifications, increasing technical : performance expectations, licensing and certification requirements, : budget restrictions and frequent department : reorganization has made technical training of employees : more difficult, ...

  3. TECHNICAL-VOCATIONAL EDUCATION IN VIETNAM.

    Science.gov (United States)

    Department of National Education, Saigon (South Vietnam).

    THE DIRECTORATE OF TECHNICAL EDUCATION, SET UP IN 1955, WAS GIVEN THE SPECIFIC DUTY OF TRAINING TECHNICIANS NEEDED FOR DEVELOPING INDUSTRY AND HANDICRAFTS. THE PROBLEMS OF TECHNICAL EDUCATION IN 1955 WERE--(1) THERE WERE ONLY TWO TECHNICAL SCHOOLS AND TWO APPRENTICE SCHOOLS, THREE APPLIED ARTS SCHOOLS, AND SEVEN ATELIER ECOLES (ARTISTS' OR…

  4. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball and W. Zeuner

    2013-01-01

    For the reporting period, the CMS common systems and infrastructure worked well, without failures that caused significant data losses. One more disconnection of the magnet cold box occurred in the shadow of interruptions in data taking, caused by a series of technical faults. The recognition during 2012 that re-connection can only safely be done at around 2 T implies a minimum magnet recovery time of 12 hours and raises serious concerns about the number of ramping cycles of the magnet these incidents cause. This has triggered studies of how to make the cryo-system of the magnet more robust against failures. The proton-proton run ended just before the end-of-year CERN closure, during which CASTOR was installed on the negative end of CMS and both ZDC calorimeters were installed in TAN absorbers the LHC tunnel, in preparation for the heavy-ion run. The installation of CASTOR was an excellent “engineering test” of procedures for working in an activated environment. Despite some technical pr...

  5. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball and W. Zeuner

    2011-01-01

      Operational experience 2011 CMS is approaching the end of a very successful year of operation. Proton- proton running ended in the late afternoon of 30th October with a stunning 5.73 fb–1 delivered by LHC, of which CMS recorded 5.22 fb–1. During heavy-ion operation, which continues until 7th December, both the accelerator and the CMS detector have also performed very well. Despite the encouraging overall reliability of technical operation, several infrastructure failures which occurred since the last Bulletin are worthy of mention, with one leading for the first time to significant data-loss. On 10th July, a CERN-wide power failure brought down essentially all services including the magnet, due to an MCS setting being left in “manual” after the recent technical stop, but there was no significant damage and the detector was operational before the LHC, despite a slow and tortuous recovery (one of several indications this year that there is room for improve...

  6. TECHNICAL COORDINATION

    CERN Multimedia

    Austin Ball

    Summary of progress since last CMS week. Ten years of construction work have been completed. CMS is closed, in very close to the ideal low luminosity configuration, and performed well in the first tests with LHC beam. Behind this encouraging news is the story of a summer of intense commitment by many teams (from the collaboration and 3 CERN departments) working together, against the clock and despite many minor setbacks, to ensure that the experiment was ready to play a leading role in the excitement of September 10. Following beampipe bakeout and refill with pure neon, a magnificent effort by the ECAL group and the pt 5 technical crew made it possible to install and commission all 4 ECAL endcap Dees before the end of August. In the shadow of this activity, the barrel and forward pixel trackers and part of the beam monitoring were installed within the vac tank. The pt 5 technical teams then succeeded in safely removing the 20t installation tables and their support blocks from beneath the already installed ...

  7. Quality assurance of technical specification approval process

    Science.gov (United States)

    Antsev, V. Yu; Antseva, N. V.; Chernecova, E. A.

    2018-03-01

    The paper reviews the issue of increasing the efficiency of contract analysis on machine-building plants in accordance with process approach principles and on the basis of better interaction between marketing, finance and accounting, and R&D departments.

  8. Training of technical staff and technical staff managers

    International Nuclear Information System (INIS)

    Moody, G.F.

    1991-01-01

    The purpose of Technical Staff and Technical Staff Managers training is to provide job skills enhancement to individuals selected to fill key technical positions within a nuclear utility. This training is unique in that unlike other training programs accredited by the National Academy for Nuclear Training, it does not lead to specific task qualification. The problems encountered when determining the student population and curriculum are a direct result of this major difference. Major problems encountered are determining who should attend the training, what amount of training is necessary and sufficient, and how to obtain the best feedback in order to effect substantive program improvements. These topics will be explored and possible solutions discussed

  9. Technical presentation

    CERN Multimedia

    FP Department

    2009-01-01

    07 April 2009 Technical presentation by Leuze Electronics: 14.00 – 15.00, Main Building, Room 61-1-017 (Room A) Photoelectric sensors, data identification and transmission systems, image processing systems. We at Leuze Electronics are "the sensor people": we have been specialising in optoelectronic sensors and safety technology for accident prevention for over 40 years. Our dedicated staff are all highly customer oriented. Customers of Leuze Electronics can always rely on one thing – on us! •\tFounded in 1963 •\t740 employees •\t115 MEUR turnover •\t20 subsidiaries •\t3 production facilities in southern Germany Product groups: •\tPhotoelectric sensors •\tIdentification and measurements •\tSafety devices

  10. Technical presentation

    CERN Multimedia

    FI Department

    2008-01-01

    RADIOSPARES, the leading catalogue distributor of components (electronic, electrical, automation, etc.) and industrial supplies will be at CERN on Friday 3 October 2008 (Main Building, Room B, from 9.00 a.m. to 3.00 p.m.) to introduce its new 2008/2009 catalogue. This will be the opportunity for us to present our complete range of products in more detail: 400 000 part numbers available on our web site (Radiospares France, RS International, extended range of components from other manufacturers); our new services: quotations, search for products not included in the catalogue, SBP products (Small Batch Production: packaging in quantities adapted to customers’ requirements); partnership with our focus manufacturers; demonstration of the on-line purchasing tool implemented on our web site in conjunction with CERN. RADIOSPARES will be accompanied by representatives of FLUKE and TYCO ELECTRONICS, who will make presentations, demonstrate materials and answer any technical questio...

  11. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball and W. Zeuner

    2010-01-01

    Overview Once again, the bulk of this article reviews the intense activity of a recently completed shutdown, which, although quite unforeseeable until a few weeks before it started, proved by its success that our often advertised capability to conduct major maintenance within a two month period is real. Although safely completed, on-time to remarkable precision, the activity was not without incident, and highlighted our dependence on many experienced, specialist teams and their precise choreography. Even after the yoke was safely closed, magnet re-commissioning and beampipe pumpdown showed new and thought-provoking behaviour. The struggle to maintain adequate technical resources will be a pre-occupation over the coming months, in parallel with the start of truly sustained operation, for which various procedures are still being put in place. Planning for future shutdowns must now become a high priority, with many working groups and task forces already in existence to prepare infrastructure improvements and to...

  12. Technical Training: Technical Training Seminar

    CERN Multimedia

    2004-01-01

    TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch Tuesday 3 February 2004 From 09:00 to 13:30 - Training Centre Auditorium - bldg. 593, room 11 USB (Universal Serial Bus) CYPRESS Seminar Claudia Colombini, Field Application Engineer CYPRESS ActiveComp Electronic GmbH D-85077 MANCHING, Germany As a pioneer in USB, CYPRESS sets the standard for cost-effective solutions without sacrificing functionality, performance or reliability. Having shipped over 200 million USB devices, Cypress is the undisputed market leader and demonstrates unmatched USB expertise. With the industry's broadest selection of USB solutions, Cypress has the right silicon, software and support for every USB application, from Low-speed to High-Speed and USB On-The-Go (OTG). 9:00 - 10:30 Overview of USB systems. USB CYPRESS product overview. Peripherals: Low Speed, Full Speed, High Speed (1.1 and 2.0). Hub Solutions, Embedded Host Solutions, On-The-Go (OTG) and wireless USB. USB Development Tools (first part) 10:30 -...

  13. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball and W. Zeuner

    2012-01-01

      UXC + detectors As explained in detail in the November 2011 bulletin, the bellows unit at −18.5 m from the CMS interaction point was identified as a prime candidate for the regularly occurring pressure spikes which occasionally led to sustained severe background conditions in 2011, affecting dead time and data quality. Similar regions in LHC with vacuum instabilities were observed to be close to bellows, which radiography showed to have distorted RF-fingers — on removal, they proved to have been severely overheated. The plans for the Year-End Technical Stop were adapted to prioritise radiography of the bellows at 16 m to 18 m either end of CMS. Excellent work by the beam pipe, survey and heavy mechanical teams allowed the X-rays to be taken as planned on 20th December, showing that the bellow at −18.5m had an obvious non-conformity. The RF-fingers were found inside the end of the opposing flared pipe instead of outside. In addition, the overlap between fingers and...

  14. TECHNICAL COORDINATION

    CERN Multimedia

    Austin Ball

    2013-01-01

      Since the last report, much visible progress has been made, as the LS1 programme approaches the halfway point. From early October, technical and safety shift-crew have been present around the clock, allowing detectors to stay switched on overnight, ensuring that safety systems are operational and instructions for non-expert shift-crew are clear. LS1 progress Throughout the summer, whilst the solenoid vacuum tank and YB0 surfaces were accessible, an extensive installation programme took place to prepare for Tracker colder operation and the PLT installation, in 2014, the Phase 1 Pixel Tracker installation, in 2016–’17, and the HCAL Phase 1 upgrade completion, ending in LS2. This included pipework for N2 or dry air to flush the Tracker bulkhead region, many sensors to monitor temperature and dew point in the Tracker and its service channels, heating wires outside the Tracker cooling bundles, supports for the new vacuum-jacketed, concentric, CO2 Pixel cooling lines, the PLT cool...

  15. ESGE-ESGENA technical specification for process validation and routine testing of endoscope reprocessing in washer-disinfectors according to EN ISO 15883, parts 1, 4, and ISO/TS 15883-5.

    Science.gov (United States)

    Beilenhoff, Ulrike; Biering, Holger; Blum, Reinhard; Brljak, Jadranka; Cimbro, Monica; Dumonceau, Jean-Marc; Hassan, Cesare; Jung, Michael; Neumann, Christiane; Pietsch, Michael; Pineau, Lionel; Ponchon, Thierry; Rejchrt, Stanislav; Rey, Jean-François; Schmidt, Verona; Tillett, Jayne; van Hooft, Jeanin

    2017-12-01

    1 Prerequisites. The clinical service provider should obtain confirmation from the endoscope washer-disinfector (EWD) manufacturer that all endoscopes intended to be used can be reprocessed in the EWD. 2 Installation qualification. This can be performed by different parties but national guidelines should define who has the responsibilities, taking into account legal requirements. 3 Operational qualification. This should include parametric tests to verify that the EWD is working according to its specifications. 4 Performance qualification. Testing of cleaning performance, microbiological testing of routinely used endoscopes, and the quality of the final rinse water should be considered in all local guidelines. The extent of these tests depends on local requirements. According to the results of type testing performed during EWD development, other parameters can be tested if local regulatory authorities accept this. Chemical residues on endoscope surfaces should be searched for, if acceptable test methods are available. 5 Routine inspections. National guidelines should consider both technical and performance criteria. Individual risk analyses performed in the validation and requalification processes are helpful for defining appropriate test frequencies for routine inspections. © Georg Thieme Verlag KG Stuttgart · New York.

  16. Technical innovation and management

    International Nuclear Information System (INIS)

    Yoon, Yang Cheol

    1982-08-01

    This book gives explanations of the conception of technical innovation, development plan in Korea, connection between technology and a growth factor in national income, problem of technical innovation in developing country, analysis on cooperation between a developed country and a developing country, evaluation and strategy of technical development in Korea, technical innovation of industry, management of technical industry, analysis of special condition in Korea.

  17. Compact Process Development at Babcock & Wilcox

    Energy Technology Data Exchange (ETDEWEB)

    Eric Shaber; Jeffrey Phillips

    2012-03-01

    Multiple process approaches have been used historically to manufacture cylindrical nuclear fuel compacts. Scale-up of fuel compacting was required for the Next Generation Nuclear Plant (NGNP) project to achieve an economically viable automated production process capable of providing a minimum of 10 compacts/minute with high production yields. In addition, the scale-up effort was required to achieve matrix density equivalent to baseline historical production processes, and allow compacting at fuel packing fractions up to 46% by volume. The scale-up approach of jet milling, fluid-bed overcoating, and hot-press compacting adopted in the U.S. Advanced Gas Reactor (AGR) Fuel Development Program involves significant paradigm shifts to capitalize on distinct advantages in simplicity, yield, and elimination of mixed waste. A series of compaction trials have been completed to optimize compaction conditions of time, temperature, and forming pressure using natural uranium oxycarbide (NUCO) fuel at packing fractions exceeding 46% by volume. Results from these trials are included. The scale-up effort is nearing completion with the process installed and operable using nuclear fuel materials. Final process testing is in progress to certify the process for manufacture of qualification test fuel compacts in 2012.

  18. Technical communication. Perspectives for the Eighties, part 2

    Science.gov (United States)

    Mathes, J. C. (Compiler); Pinelli, T. E. (Compiler)

    1981-01-01

    The importance of technical writing as a separate discipline is suggested. Some specific areas addressed were: technical writing skills industry needs, definitions of technical writing, the hows and whys of inhouse writing, and the nature of the composing process in technical comunication.

  19. TWRSview system requirements specification

    International Nuclear Information System (INIS)

    Caldwell, J.A.; Lee, A.K.

    1995-12-01

    This document provides the system requirements specification for the TWRSview software system. The TWRSview software system is being developed to integrate electronic data supporting the development of the TWRS technical baseline

  20. [Analogies and analogy research in technical biology and bionics].

    Science.gov (United States)

    Nachtigall, Werner

    2010-01-01

    The procedural approaches of Technical Biology and Bionics are characterized, and analogy research is identified as their common basis. The actual creative aspect in bionical research lies in recognizing and exploiting technically oriented analogies underlying a specific biological prototype to indicate a specific technical application.

  1. Strategy of technical innovation

    International Nuclear Information System (INIS)

    Lee, Ga Jong

    1990-12-01

    This book deals with policy of scientific technique and technical innovation such as research for development and types of technical innovation, historical development and process of technical innovation, economic growth, technology change and investment for research and development, structure and form of technical transfer with the meaning process, from, structure and theory, economic growth and investment of research and development with experiential analysis and case study on strategy of technical innovation in electron and fine chemical industry.

  2. Teaching Students the Verticality of Technical Documentation.

    Science.gov (United States)

    Hager, Peter J.

    1992-01-01

    Advocates making technical writing courses more vertical in structure by including an extensive study of at least one specific form of technical documentation. Examines how students can gain experience in the vertical process by designing, writing, testing, and producing user manuals for on-campus cooperative education clients. Lists the benefits…

  3. ITA technical activities status report

    International Nuclear Information System (INIS)

    Shimomura, Y.

    2004-01-01

    This note summarizes the progress made in the technical work of the ITER Transitional Arrangements in the period between September 2003 and June 2004. It comprises design work, update of baseline documents, risk management plan, ITER baseline web site, preparation of technical specifications, task agreements, international team status, CAD and document management, codes and standards, common expenses, future network connectivity needs, travel support of members of the International Team, testing blanket working group, physics status, diagnostics, task agreements for large physics R and D

  4. TECHNICAL TRAINING SEMINAR

    CERN Multimedia

    Davide Vitè

    2002-01-01

    Wednesday 6 March TECHNICAL TRAINING SEMINAR from 9:30 to 16:45 - IT Amphitheatre - bldg. 31.3.004 Analog Devices DSP Day Thorsten Kistler (Application Engineer), Steffen Boerner (Product Specialist) / ANALOG DEVICES Munich Trying to meet your design challenges, Analog Devices compiles application information and offers chipsets, software, reference designs and mixed-signal, application specific DSPs, for a range of real-time signal processing applications. This seminar will present the latest 16bit fixed-point and 32bit floating-point DSPs (roadmaps; internal architectures, blocks, features benchmarks), with their software, development kits and emulators: Fixed-Point DSP-Family, ADSP-218x and ADSP-219x Blackfin DSP SHARC-Family, 2106x and 2116x TigerSHARC Industrial Contact: François Caloz, Sasco-Spoerle GmbH Language: English Free seminar, no registration Organiser: Davide Vitè / HR-TD / 75141 Davide.Vite@cern.ch Please read the full information on the Technical Training Seminars...

  5. Technical efficiency, efficiency change, technical progress and ...

    African Journals Online (AJOL)

    Technical efficiency, efficiency change, technical progress and productivity growth in the national health systems of continental African countries. ... a view to analysing changes in efficiency and changes in technology. The analysis was based on a five-year panel data (1999-2003) from all the 53 countries of continental ...

  6. The Effectiveness of Problem-based Learning Approach on Students’ Skills in Technical Vocational Education and Training (TVET) Specifically on Programming Course Using a Computerized Numerical Control (CNC) Simulator

    DEFF Research Database (Denmark)

    Mohamad, Hasim Bin; de Graaff, Erik

    2013-01-01

    using a Computerized Numerical Control (CNC) simulator. The study will use data from the German-Malaysian Institute in Malaysia. The findings of this study will provide a general guideline for educators in Technical and Vocational Education and Training (TVET) institutions in implementing Problem...

  7. Reader-Centered Technical Writing

    Science.gov (United States)

    Narayanan, M.

    2012-12-01

    Technical writing is an essential part of professional communication and in recent years it has shifted from a genre-based approach. Formerly, technical writing primarily focused on generating templates of documents and sometimes it was creating or reproducing traditional forms with minor modifications and updates. Now, technical writing looks at the situations surrounding the need to write. This involves deep thinking about the goals and objectives of the project on hand. Furthermore, one observes that it is very important for any participatory process to have the full support of management. This support needs to be well understood and believed by employees. Professional writing may be very persuasive in some cases. When presented in the appropriate context, technical writing can persuade a company to improve work conditions ensuring employee safety and timely production. However, one must recognize that lot of professional writing still continues to make use of reports and instruction manuals. Normally, technical and professional writing addresses four aspects. Objective: The need for generating a given professionally written technical document and the goals the document is expected to achieve and accomplish. Clientele: The clientele who will utilize the technical document. This may include the people in the organization. This may also include "unintended readers." Customers: The population that may be affected by the content of the technical document generated. This includes the stakeholders who will be influenced. Environment: The background in which the document is created. Also, the nature of the situation that warranted the generation of the document. Swiss Psychologist Jean Piaget's view of Learning focuses on three aspects. The author likes to extend Jean Piaget's ideas to students, who are asked to prepare and submit Reader-Centered Technical Writing reports and exercises. Assimilation: Writers may benefit specifically, by assimilating a new object into

  8. ITER technical basis

    International Nuclear Information System (INIS)

    2002-01-01

    Following on from the Final Report of the EDA(DS/21), and the summary of the ITER Final Design report(DS/22), the technical basis gives further details of the design of ITER. It is in two parts. The first, the Plant Design specification, summarises the main constraints on the plant design and operation from the viewpoint of engineering and physics assumptions, compliance with safety regulations, and siting requirements and assumptions. The second, the Plant Description Document, describes the physics performance and engineering characteristics of the plant design, illustrates the potential operational consequences foe the locality of a generic site, gives the construction, commissioning, exploitation and decommissioning schedule, and reports the estimated lifetime costing based on data from the industry of the EDA parties

  9. SPACE-R Thermionic Space Nuclear Power System: Design and Technology Demonstration Program. Semiannual technical progress report for period ending March 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    This Semiannual Technical Progress Report summarizes the technical progress and accomplishments for the Thermionic Space Nuclear Power System (TI-SNPS) Design and Technology Demonstration Program of the Prime Contractor, Space Power Incorporated (SPI), its subcontractors and supporting National Laboratories during the first half of the Government Fiscal Year (GFY) 1993. SPI`s subcontractors and supporting National Laboratories include: Babcock & Wilcox for the reactor core and externals; Space Systems/Loral for the spacecraft integration; Thermocore for the radiator heat pipes and the heat exchanger; INERTEK of CIS for the TFE, core elements and nuclear tests; Argonne National Laboratories for nuclear safety, physics and control verification; and Oak Ridge National laboratories for materials testing. Parametric trade studies are near completion. However, technical input from INERTEK has yet to be provided to determine some of the baseline design configurations. The INERTEK subcontract is expected to be initiated soon. The Point Design task has been initiated. The thermionic fuel element (TFE) is undergoing several design iterations. The reactor core vessel analysis and design has also been started.

  10. How to be an Effective Technical Writer?

    Directory of Open Access Journals (Sweden)

    M Solaiman Ali

    2012-07-01

    Full Text Available Abstract--This paper has focused on technical writing as a skill for engineers. It has sought to define technical writing and throw light on the content and technique of writing the various components of successful technical reports (for example, articles, papers, or research reports, such as theses and dissertations. Then, it has highlighted other special features and principles of effective technical writing. The material in this paper is divided into seven major parts. Part 1 (Technical writing for engineers stresses that a successful engineering career requires strong writing skills. Part 2 (How to write the major sections or elements of a report describes the techniques of writing the abstract, introduction, literature review, procedure/methods & materials, results, discussion, conclusion, and recommendations. Part 3 (Special features of technical writing brings into focus some of the special features of technical writing such as tables & graphs in the text, graphics in instructions, team writing, ethics (plagiarism, document sources, three citation styles and IEEE reference style. Part 4 (Technical usage deals with writing abbreviations, initialisms and acronyms, numbers, units of measurement, and equations.Part 5 (Technical style highlights the imperative writing style and other features of technical writing such as the use of active and passive voices, plain vs. complex syntax, avoiding redundant or superfluous expressions, and vague generalities, using words or expressions with visual impact, the past tense to describe experimental work, the present tense to describe hypotheses, principles, theories and truths, and breaking up the text of the report into short sections. Part 6 (Document specifications emphasizes the technical writer’s need to conform to such document specifications as word count, format, font, number of words per line of text imposed. Part 7 (Reader-friendly technical writing suggests choosing the varied writing modes

  11. Technical training: places available

    CERN Multimedia

    2013-01-01

    If you would like more information on a course, or for any other inquiry/suggestions, please contact Technical.Training@cern.ch. Eva Stern and Elise Romero, Technical Training Administration (Tel: 74924)

  12. Technical training - places available

    CERN Multimedia

    2013-01-01

    If you would like more information on a course, or have any other inquiry/suggestions, please contact Technical.Training@cern.ch. Eva Stern and Elise Romero, Technical Training Administration (Tel: 74924)

  13. Technical training: places available

    CERN Multimedia

    2014-01-01

    If you would like more information on a course, or have any other inquiry/suggestions, please contact Technical.Training@cern.ch. Eva Stern and Marie Lahchimi, Technical Training Administration (Tel: 74924)

  14. Technical training: places available

    CERN Multimedia

    2014-01-01

    If you would like more information on a course, or have any other inquiry/suggestions, please contact Technical.Training@cern.ch. Eva Stern and Elise Romero, Technical Training Administration (Tel: 74924)

  15. Technical training: places available

    CERN Multimedia

    2013-01-01

    If you would like more information on a course, or for any other inquiry/suggestions, please contact Technical.Training@cern.ch. Eva Stern and Elise Romero, Technical Training Administration (Tél : 74924)  

  16. Technical Assistance Plan (TAP)

    Science.gov (United States)

    A Technical Assistance Plan (TAP) enables community groups to retain the services of an independent technical advisor and to provide resources for a community group to help inform other community members about site decisions.

  17. Teaching Technical Writing - Towards Technical Writing

    DEFF Research Database (Denmark)

    Kastberg, Peter

    2000-01-01

    In this paper I will present key aspects of the curriculum for the university degree in technical translation that I have designed for and subsequently implemented at the German Department of the Aarhus School of Business, Denmark. My starting point will be a critical discussion of the norm...... that used to govern what the quality of an LSP text should be as opposed to the standpoint, which I advocate. By way of summing up, I will show how a university curriculum is designed so that - upon graduation - the technical translator could also be methodological quite well suited to take on the challenge...... of technical writing....

  18. System for Users Technical Support

    OpenAIRE

    Andriušaitienė, Ramunė

    2007-01-01

    This Master thesis presents a study of computer equipment support services providing company’s business processes, specifics of the ongoing communication between end-users and supporting engineers-consultants and presents review of some information systems designed to automate certain technical support activities. Core aim of this study is to alleviate the daily work of above mentioned consultants when supporting end-users to locate and resolve issues in owned computer equipment. This paper o...

  19. Nucleoelectric plants technical memory

    International Nuclear Information System (INIS)

    Araujo Pereira, Alvaro de

    1991-01-01

    The work explains the basic norms that establish the guidelines to the Technical Memory elaboration of this electrical energy sector - the nucleoelectric plants. It guides the technicians who execute the Technical Memory of the plants, exposing the items that may compose the work: contents: introduction, planning, proposition, equipment and materials supply, construction, commissioning, commercial actions, budget, financing and costs; generalities: drawings and photographies, monetary references, terminology, system units, management, graphic guide project, responsible staff, a summarized technical card and illustrations

  20. Has Technical Communication Arrived as a Profession

    OpenAIRE

    Pringle, Kathy; Williams, Sean

    2005-01-01

    This article examines the design and technology components of technical communication by investigating how practitioners imagine their work and the profession, specifically with respect to technology. In short, we wanted to interrogate the duality of “core design skills” and “technology skills” by asking practitioners to reflect both on the definition of technical communication and on the role technology plays in their work. We wanted to weigh claims that communication and rhetorical skills a...

  1. Canister Storage Building (CSB) Technical Safety Requirements

    International Nuclear Information System (INIS)

    KRAHN, D.E.

    2000-01-01

    The purpose of this section is to explain the meaning of logical connectors with specific examples. Logical connectors are used in Technical Safety Requirements (TSRs) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TSRs are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings

  2. Guidelines for Preparing Interim Technical Reports

    International Development Research Centre (IDRC) Digital Library (Canada)

    IDRC CRDI

    The interim technical report explains what was achieved with the money and time spent on a project during a specific reporting period. The interim report specifically .... o knowledge creation (new knowledge embodied in forms other than publications or reports: new technologies, new methodologies, new curricula, new ...

  3. Bulletin Survey: Technical clarifications

    CERN Multimedia

    2002-01-01

    In the latest of our articles on the results of the Bulletin survey, we respond to some of your technical comments on the Electronic Bulletin. Many thanks to the more than 500 of you who completed the questionnaire. The full statistics will be published next week. 'It takes too long to download the pages' Yes, it's true that the Electronic Bulletin's download time isn't perfect but it will improve when the Bulletin migrates to another, faster database. 'I find it very difficult to locate all the articles' Some people experience difficulty negotiating their way through the Bulletin once they have entered a specific section. The blue column on the left contains an 'In this issue' link taking you to the other sections. What's more, the whole of the paper Bulletin is available in the electronic version. As the latter is relatively new, however, it will take a bit of time to get used to browsing through it. Many of you say that it's still too early to form an opinion. 'Pull-down menus would be good, so that yo...

  4. TECHNICAL TRAINING SEMINAR

    CERN Multimedia

    Davide VITÈ

    2002-01-01

    Wednesday 6 March   from 9:30 to 16:45 - IT Auditorium - bldg. 31 3-004 Analog Devices DSP Day Thorsten Kistler (Application Engineer), Steffen Boerner (Product Specialist) / ANALOG DEVICES Munich Trying to meet your design challenges, Analog Devices compiles application information and offers chipsets, software, reference designs and mixed-signal, application specific DSPs, for a range of real-time signal processing applications. This seminar will present the latest 16bit fixed-point and 32bit floating-point DSPs (roadmaps; internal architectures, blocks, features benchmarks), with their software, development kits and emulators: Fixed-Point DSP-Family, ADSP-218x and ADSP-219x Blackfin DSP SHARC-Family, 2106x and 2116x TigerSHARC Industrial Contact: François Caloz, Sasco-Spoerle GmbH Language: English Free seminar, no registration Organiser: Davide Vitè / HR-TD / 75141 Davide.Vite@cern.ch Please read the full information on the Technical Training Seminars pages here or con...

  5. TECHNICAL TRAINING SEMINAR

    CERN Multimedia

    Davide Vitè

    2002-01-01

    Wednesday 6 March from 9:30 to 16:45 - IT Auditorium - bldg. 31 3-004 Analog Devices DSP Day Thorsten Kistler (Application Engineer), Steffen Boerner (Product Specialist) / ANALOG DEVICES Munich Trying to meet your design challenges, Analog Devices compiles application information and offers chipsets, software, reference designs and mixed-signal, application specific DSPs, for a range of real-time signal processing applications. This seminar will present the latest 16bit fixed-point and 32bit floating-point DSPs (roadmaps; internal architectures, blocks, features benchmarks), with their software, development kits and emulators: Fixed-Point DSP-Family, ADSP-218x and ADSP-219x Blackfin DSP SHARC-Family, 2106x and 2116x TigerSHARC Industrial Contact: François Caloz, Sasco-Spoerle GmbH Language: English Free seminar, no registration Organiser: Davide Vitè / HR-TD / 75141 Davide.Vite@cern.ch Please read the full information on the Technical Training Seminars pages here or contact the organiser.

  6. Map Specifications and Exchange of Geographical Information

    DEFF Research Database (Denmark)

    Frederiksen, Poul

    1999-01-01

    Specifications for Technical Maps 1993 – 99 are described giving an overview of the specification structure including the object description of the latest version: TK99.The technical map specifications are related to the standards for topographical maps - especially the TOP10DK standard. Common...... object definitions are essential for the standards. Technical as well as topographical map information is exchangeable through the Danish developed “Standard for Exchange of Digital Map Information”, known as the DSFL-format....

  7. Tank waste technical options report

    International Nuclear Information System (INIS)

    Boomer, K.D.; Baker, S.K.; Boldt, A.L.; Galbraith, J.D.; Garfield, J.S.; Golberg, C.E.; Higley, B.A.; Johnson, L.J.; Kupfer, M.J.; Marusich, R.M.; Parazin, R.J.; Praga, A.N.; Reddick, G.W.; Reddick, J.A.; Slaathaug, E.J.; Swanson, L.M.; Waldo, T.L.; Worcester, C.E.

    1993-01-01

    This document, Tank Waste Technical Options Report, assesses technologies that can be applied to treat and dispose of all Hanford Site tank waste including the cesium and strontium capsules. This effort continues the single-shell tank systems engineering work that began at the urging of a National Academy of Science subpanel. The study develops data on specific technologies that are combined to form alternativesfor waste treatment and disposal. These alternatives are defined and evaluated in the Tank Waste Decision Analysis Report. Both studies are an integral part of the Tank Waste Remediation System goal of defininga new technical strategy in 1993. The engineering work represented in this document will also serve as data for the environmental impact statement support document

  8. Technical Manual. The ACT®

    Science.gov (United States)

    ACT, Inc., 2014

    2014-01-01

    This manual contains technical information about the ACT® college readiness assessment. The principal purpose of this manual is to document the technical characteristics of the ACT in light of its intended purposes. ACT regularly conducts research as part of the ongoing formative evaluation of its programs. The research is intended to ensure that…

  9. TRANSLATING SERVICE TECHNICAL PROSE

    African Journals Online (AJOL)

    of technical literature: advertising agencies dealing with clients in the technical fields, workshops ..... editing, a subject specialist. (preferably a physician au fait with aerospace matters), and two good translators. Having all the resources at hand, the teams seclude themselves with all their allocated documents and the senior.

  10. Developing Technical Skill Assessments

    Science.gov (United States)

    Hyslop, Alisha

    2009-01-01

    One of the biggest challenges facing the career and technical education (CTE) community as it works to implement the 2006 Perkins Act is responding to more rigorous requirements for reporting on CTE students' technical skill attainment. The U.S. Department of Education suggested in non-regulatory guidance that states and locals use the number of…

  11. Summer Technical Students 2004

    CERN Multimedia

    Maximilien Brice

    2004-01-01

    About 100 technical and doctoral students arrive each year, undergraduates and post-graduates who are preparing diploma or doctoral theses in applied science and technology. They spend up to two years at the Laboratory, as technical students as part of their formal training for a recognised degree or its equivalent.

  12. Transformation of technical infrastructure

    DEFF Research Database (Denmark)

    Nielsen, Susanne Balslev

    1998-01-01

    article about the need of new planning forums in order to initiate transformations with in management of large technical systems for energy, waste and water supply.......article about the need of new planning forums in order to initiate transformations with in management of large technical systems for energy, waste and water supply....

  13. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Glasser, Alan H. [Fusion Theory and Computation Inc., Kingston, WA (United States)

    2018-02-02

    Final technical report on DE-SC0016106. This is the final technical report for a portion of the multi-institutional CEMM project. This report is centered around 3 publications and a seminar presentation, which have been submitted to E-Link.

  14. Technical Training for Managers.

    Science.gov (United States)

    Haverland, Edgar M.

    The question has arisen as to what kind of information a manager without extensive technical training needs to learn to supervise effectively. For example, the Nike Hercules fire control platoon leader, usually an officer in his first active duty assignment, seldom has had extensive technical training. Yet he is responsibile for the…

  15. Investment specific technological progress and structural change

    Directory of Open Access Journals (Sweden)

    Ricardo Silva Azevedo Araujo

    2010-12-01

    Full Text Available In this paper we introduce investment specific technical progress into Pasinetti's model of structural change. Our aim is to assess the effects of embodied technical progress on economic growth and macroeconomic variables. Our findings suggest that despite the fact that this type of technical progress increases the productivity of capital, it has negative effects on conditions that promote full employment.

  16. Technical Agency in Practice

    DEFF Research Database (Denmark)

    Krummheuer, Antonia Lina

    2015-01-01

    ) description of hybrid networks in which human and non-human actants are granted agency without differentiating different kinds of agency, EMCA focuses on the member's perspectives and the situated construction of technical agency that is made relevant within an ongoing interaction. Based on an EMCA analysis......The paper combines the discussion of technical agency and hybrid networks of Actor-Network Theory (ANT) with an ethnomethodological/conversation analytical (EMCA) perspective on situated practices in which participants ascribe agency to technical artefacts. While ANT works with (ethnographic...... of three video recordings of situations in which technical agency is made relevant by the human participants, the paper demonstrates different ways in which agency is granted to technical artefacts. Human participants can treat a technology as communication partner, as an active part (and actant...

  17. Base compaction specification feasibility analysis.

    Science.gov (United States)

    2012-12-01

    The objective of this research is to establish the technical engineering and cost : analysis concepts that will enable WisDOT management to objectively evaluate the : feasibility of switching construction specification philosophies for aggregate base...

  18. Systematization of the technical and economic sizing of isolated photovoltaic systems through specific software; Sistematizacao do dimensionamento tecnico e economico de sistemas fotovoltaicos isolados por meio de programa computacional

    Energy Technology Data Exchange (ETDEWEB)

    Marini, Jose A.; Rossi, Luiz A. [Universidade Estadual de Campinas, SP (Brazil). Faculdade de Engenharia Agricola

    2005-01-15

    One of the main referring subjects to the solar energy is how to compare it economically with other sources of energy, as alternative as conventional energy (like electric grid). The purpose of this work was to develop a software which congregates the technical and economic main data to identify, through methods of micro economic analysis, the commercial viability in the sizing of photovoltaic systems, besides considering the benefits proceeding from the proper energy generation. Considering the period of useful life of the components of the generation system of photovoltaic electricity, the costs of the energy proceeding from the conventional grid had been identified. For the comparison of the conventional sources, electric grid and diesel generation, three scenes of costs of photovoltaic panels and two for the factor of availability of diesel generation had been used. The results have shown that if the cost of the panels is low and the place of installation is more distant of the electric grid, the photovoltaic system becomes the best option. (author)

  19. Urology technical and non-technical skills development: the emerging role of simulation.

    Science.gov (United States)

    Rashid, Prem; Gianduzzo, Troy R J

    2016-04-01

    To review the emerging role of technical and non-technical simulation in urological education and training. A review was conducted to examine the current role of simulation in urology training. A PUBMED search of the terms 'urology training', 'urology simulation' and 'urology education' revealed 11,504 titles. Three hundred and fifty-seven abstracts were identified as English language, peer reviewed papers pertaining to the role of simulation in urology and related topics. Key papers were used to explore themes. Some cross-referenced papers were also included. There is an ongoing need to ensure that training time is efficiently utilised while ensuring that optimal technical and non-technical skills are achieved. Changing working conditions and the need to minimise patient harm by inadvertent errors must be taken into account. Simulation models for specific technical aspects have been the mainstay of graduated step-wise low and high fidelity training. Whole scenario environments as well as non-technical aspects can be slowly incorporated into the curriculum. Doing so should also help define what have been challenging competencies to teach and evaluate. Dedicated time, resources and trainer up-skilling are important. Concurrent studies are needed to help evaluate the effectiveness of introducing step-wise simulation for technical and non-technical competencies. Simulation based learning remains the best avenue of progressing surgical education. Technical and non-technical simulation could be used in the selection process. There are good economic, logistic and safety reasons to pursue the process of ongoing development of simulation co-curricula. While the role of simulation is assured, its progress will depend on a structured program that takes advantage of what can be delivered via this medium. Overall, simulation can be developed further for urological training programs to encompass technical and non-technical skill development at all stages, including

  20. Technical standards in nuclear area

    International Nuclear Information System (INIS)

    Grimberg, M.

    1978-01-01

    The technical standardization in nuclear area is discussed. Also, the competence of CNEN in standardization pursuit is analysed. Moreover, the process of working up of technical standards is explained; in addition, some kinds of technical standards are discussed. (author) [pt

  1. Technical approach to aging management

    International Nuclear Information System (INIS)

    Vora, J.P.; Johnson, A.B. Jr.; Allen, R.P.

    1992-10-01

    Systematic and effective control of age-related degradation of safety-related components, systems, and structures in nuclear power plants (NPPs) is an important challenge to plant operators. Several data bases, available to provide guidance on aging management, are summarized. However, the ultimate consideration is: How effectively is aging management being implemented at individual plants? Illustrated here is a specific strategy that served to develop the technical data base for the Nuclear Plant Aging Research Program. The strategy is comprehensive, systematic, and adaptable. Effective aging management at NPPs could be facilitated by a parallel strategy. The elements of a strategy are suggested

  2. The general technical regulation and the standardization

    International Nuclear Information System (INIS)

    Laverie, Michel; Houze, Christian; Lebouleux, Philippe

    1980-01-01

    Through a certain number of procedures, the thorough appreciation of the safety of a nuclear installation relies more on a specific appreciation taking into account the references as a whole, than on a technical regulation which claims to cover all the problems. Nevertheless, a French technical regulation structure regarding the safety domain must be built up progressively. The authors consider the principles of such a structure, and together they make the inventory of the works, finished, in progress or contemplated. The description of this specifically French approach emphazises the multiple and complementary forms given to statutory implements [fr

  3. Technical and economic guidelines

    International Nuclear Information System (INIS)

    1978-01-01

    This paper proposes technical and economic data and analysis for use in comparing the nuclear systems considered in INFCE. It suggests that a relatively detailed set of characteristics be developed for each system. An alternative to this approach is to concentrate on comparing the characteristic of most interest to INFCE, using a differential comparison to established systems (such as the LWR and HWR) where possible. This would avoid the repetitive analysis of design characteristics that are common to many systems. In making the INFCE comparisons it would still be appropriate that a selected set of information, pertinent to the primary assessment factors under consideration, be developed for each nuclear system. This selected set, much more limited than that set forth in the body of this paper, would include overall descriptions of the reactor and fuel cycle facilities, as well as specific information on resource utilization, flow of nuclear materials, and other areas to be determined by the Working Group. On the other hand, in areas such as costs, nuclear safety, and environmental impacts, it would not be intended that information be developed at a level of detail comparable to that resulting from a detailed design of each system being compared. Instead, the detailed set of data identified in this paper can serve as a check list to assure that all pertinent characteristics are considered, at least on a differential basis; more detailed assessments would be needed only where the differences have substantial impact. Thus this paper asks for more detail than will probably be appropriate for many contributed papers

  4. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Juan Camilo Serrano

    2011-12-16

    New and novel material and process technologies applied in wind blade designs and production are critical to increasing the competitiveness of wind power generation against traditional sources of energy. In this project, through collaboration between PPG Industries and MAG Industrial Automation Systems, the potential of using automated manufacturing for the production of fiber glass composite wind blades was evaluated from both technical and economic points of view. Further, it was demonstrated that by modifying the standard blade raw material forms through the use of cost effective pre-impregnated rovings coupled with using an automated fiber placement machine to lay up the parts, it is possible to produce state of the art composite laminates with significantly improved mechanical performance and with higher processing rates than standard blade production technology allows for today, thereby lowering the cost of energy over turbine blades made using traditional processes and materials. In conformity with the scope of work of the submitted proposal, the project team completed each task and documented and reported its findings on the appropriate quarterly report submitted to the DOE project team. The activities and this report are divided into 5 subtasks: (1) Material Investigation - Reviews traditional materials and key specifications and testing methods; (2) Manufacturing and Automation - Identifies new candidate material forms and automated layup processes; (3) Process Development - Performs trials of candidate materials and processes; (4) Predictive Analysis - Assesses impact of new material forms and automated processes on a model blade design; and (5) Feasibility Assessment - Compares traditional manufacturing processes and materials to new candidate material forms and automated processes.

  5. Technical Report Writing Today

    DEFF Research Database (Denmark)

    Riordan, Daniel G.

    2014-01-01

    Section 1: Technical Communication Basics (8 chapters on tech com, audiences, tech com process, tech com style, researching, designing pages, using visual aids, describing). Section 2: Technical Communication Applications (7 chapters on sets of instructions, informal reports and email, developing...... websites/using social media, formal reports, recommendation and feasibility reports, proposals, user manuals). Section 3: Professional Communication (2 chapters and 2 appendices on presentations, job application materials, brief handbook for tech writers, documenting sources).......Section 1: Technical Communication Basics (8 chapters on tech com, audiences, tech com process, tech com style, researching, designing pages, using visual aids, describing). Section 2: Technical Communication Applications (7 chapters on sets of instructions, informal reports and email, developing...

  6. Superfund Technical Assistance Grants

    Data.gov (United States)

    U.S. Environmental Protection Agency — This asset includes data related to the Superfund Technical Assistance Grant program, including grant number, award amounts, award dates, period of performance,...

  7. Applying technical versatility

    Energy Technology Data Exchange (ETDEWEB)

    None

    1970-01-01

    The breadth and depth of the diversified technical programs at Mound Laboratory since its inception are characterized by a record of competence and versatility during the past generation. A spectrum of mission assignments has been completed successfully in such diverse technical areas as process development and manufacturing of explosive components, research on fuels for the Civilian Power Reactor Program, separation of radioactive materials, fabrication of radioisotopic heat sources, stable gaseous isotope separation and purification, and many other areas. Mound Laboratory is one of the key U.S. Atomic Energy Commission sites that has demonstrated its technical competence in both weapons and non-weapons activities. This report has been prepared to complement the AEC’s vigorous program of scientific information dissemination. Three broad areas of technical competence are highlighted here: explosive technology, radionuclide technology, and stable gaseous isotope separation, which encompass a broad variety of techniques and supporting disciplines.

  8. Technical report writing today

    CERN Document Server

    Riordan, Daniel G

    2014-01-01

    "Technical Report Writing Today" provides thorough coverage of technical writing basics, techniques, and applications. Through a practical focus with varied examples and exercises, students internalize the skills necessary to produce clear and effective documents and reports. Project worksheets help students organize their thoughts and prepare for assignments, and focus boxes highlight key information and recent developments in technical communication. Extensive individual and collaborative exercises expose students to different kinds of technical writing problems and solutions. Annotated student examples - more than 100 in all - illustrate different writing styles and approaches to problems. Numerous short and long examples throughout the text demonstrate solutions for handling writing assignments in current career situations. The four-color artwork in the chapter on creating visuals keeps pace with contemporary workplace capabilities. The Tenth Edition offers the latest information on using electronic resum...

  9. Socio-technical Betwixtness

    DEFF Research Database (Denmark)

    Bossen, Claus

    2017-01-01

    the intrinsically social and technical interwovenness of design, and the necessity of including affected people and stakeholders in the design process. This betwixtness of socio-technical design is demonstrated by the analysis of two IT systems for healthcare: a foundational model for electronic healthcare records......This chapter focusses on two challenges for socio-technical design: Having to choose between different rationales for design, and the adequate understanding and depiction of the work to be redesigned. These two challenges betwixt the otherwise strong tenets of socio-technical design of pointing out......, and an IT system organizing hospital porters’ work. The conceptual background for the analysis of the cases is provided by a short introduction to different rationales for organizational design, and by pointing to the differences between a linear, rationalistic versus an interactional depiction of work....

  10. Science and Technical Indicators

    Czech Academy of Sciences Publication Activity Database

    Laiblová Kadlecová, Ivana; Lhoták, Martin; Mika, Pavel

    -, č. 3 (2014) E-ISSN 1805-2800 Keywords : bibliometrics Subject RIV: AF - Documentation, Lib rarianship, Information Studies http://www. lib .cas.cz/casopis-informace/science-and-technical-indicators/

  11. NCDC Technical Reports

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — NCDC Technical Reports is a set of retrospective analyses produced by the Research Customer Service Group and the National Climatic Data Center from 1995 to 2008....

  12. Retention of technical professionals

    OpenAIRE

    2012-01-01

    M.Ing. The loss of skills and knowledge of technical professionals experienced by many organizations in South Africa has serious implications on the competitiveness of these organizations in the local and international markets. Organizations should come to realize that they should find creative ways to retain critical skills and knowledge and ensure continuity in terms of succession management. Technical professionals play a crucial role in society. They are responsible for maintaining the...

  13. Understanding Socio Technical Modularity

    DEFF Research Database (Denmark)

    Thuesen, Christian Langhoff; Kudsk, Anders; Hvam, Lars

    2011-01-01

    dimension of modularity like irrational behaviors, cultural differences, learning processes, social organization and institutional influences on modularity. The paper addresses this gab offering a reinterpretation of the modularity concept from a socio-technical perspective in general and Actor Network...... Theory in particular. By formulating modularity from an ANT perspective covering social, material and process aspects, the modularity of a socio-technical system can be understood as an entanglement of product, process, organizational and institutional modularity. The theoretical framework is illustrated...

  14. THE DIMENSIONS OF CREATIVITY IN TECHNICAL EDUCATION

    Directory of Open Access Journals (Sweden)

    Małgorzata Franc

    2016-06-01

    Full Text Available Introduction: this paper engages with the change in the approach to technical education and to its research nature, quantity and quality ratio. The technical education is ordinary education and technical education at the same time. The technical education is a set of activities aimed at the skillful use of technology in deliberately organized process of interacting with an individual, causing permanent changes in their personality. Formation of a learner’s technological culture is made by providing knowledge about the products of technology, experiencing technical situations, raising respect for human technical creativity and products of creativity, developing an ability to use the products of technology. Technical education is aimed at the student’s cognitive realm, providing information and building a system of knowledge about the technical reality, developing cognitive skills needed to receive, understand, interpret and verify technical phenomena. Materials and Methods: the research was based on the analysis of students’ theses enrolled at Organization and Management Faculty of Lodz University of Technology. Results: objective quality indicators were defined for the purposes of analysis. The analysis results are not final, but they form the basis for an in-depth understanding of the academic reality. Generic requirements have been developed to polytechnic education. Discussion and Conclusions: polytechnic education is a specific link in the development of culture and civilization that provides value to the formation of personality. Different areas of the human civilization and the objective socio-cultural world are the basis for development. Polytechnic education forms the elite, providing the stable development of the society in accordance with the rules and principles.

  15. Sistematização do dimensionamento técnico e econômico de sistemas fotovoltaicos isolados por meio de programa computacional Systematization of the technical and economic sizing of isolated photovoltaic systems through specific software

    Directory of Open Access Journals (Sweden)

    José A. Marini

    2005-04-01

    Full Text Available Uma das principais questões referentes à energia solar é como compará-la, técnica e economicamente, com outras fontes de energia, tanto alternativas quanto com as convencionais (como a rede elétrica. O propósito deste trabalho foi desenvolver um programa computacional que reúne os principais dados técnicos e econômicos, para identificar, por meio de métodos de análise microeconômica, a viabilidade comercial no dimensionamento de sistemas fotovoltaicos, além de considerar os benefícios provenientes da própria geração energética. Na análise microeconômica da energia solar, foram identificados os custos da energia proveniente da rede convencional durante o período de vida útil dos componentes do sistema gerador de eletricidade fotovoltaica, pelo estudo dos custos de investimentos iniciais e manutenção do sistema. Para comparação com as fontes convencionais - rede elétrica e grupo diesel - foram usados três cenários de custos de painéis fotovoltaicos e dois para o fator de disponibilidade do grupo diesel. Pelos resultados, verifica-se que, quanto mais baixo o custo dos painéis e mais distante o local situar-se da rede elétrica, o sistema fotovoltaico torna-se a opção mais vantajosa.One of the main referring subjects to the solar energy is how to compare it economically with other sources of energy, as much alternatives as with conventionals (like the electric grid. The purpose of this work was to develop a software which congregates the technical and economic main data to identify, through methods of microeconomic analysis, the commercial viability in the sizing of photovoltaic systems, besides considering the benefits proceeding from the proper energy generation. Considering the period of useful life of the components of the generation system of photovoltaic electricity, the costs of the energy proceeding from the conventional grid had been identified. For the comparison of the conventional sources, electric grid

  16. Simulation-based ureteroscopy skills training curriculum with integration of technical and non-technical skills: a randomised controlled trial.

    Science.gov (United States)

    Brunckhorst, Oliver; Shahid, Shahab; Aydin, Abdullatif; McIlhenny, Craig; Khan, Shahid; Raza, Syed Johar; Sahai, Arun; Brewin, James; Bello, Fernando; Kneebone, Roger; Khan, Muhammad Shamim; Dasgupta, Prokar; Ahmed, Kamran

    2015-09-01

    Current training modalities within ureteroscopy have been extensively validated and must now be integrated within a comprehensive curriculum. Additionally, non-technical skills often cause surgical error and little research has been conducted to combine this with technical skills teaching. This study therefore aimed to develop and validate a curriculum for semi-rigid ureteroscopy, integrating both technical and non-technical skills teaching within the programme. Delphi methodology was utilised for curriculum development and content validation, with a randomised trial then conducted (n = 32) for curriculum evaluation. The developed curriculum consisted of four modules; initially developing basic technical skills and subsequently integrating non-technical skills teaching. Sixteen participants underwent the simulation-based curriculum and were subsequently assessed, together with the control cohort (n = 16) within a full immersion environment. Both technical (Time to completion, OSATS and a task specific checklist) and non-technical (NOTSS) outcome measures were recorded with parametric and non-parametric analyses used depending on the distribution of our data as evaluated by a Shapiro-Wilk test. Improvements within the intervention cohort demonstrated educational value across all technical and non-technical parameters recorded, including time to completion (p technical and non-technical skills teaching is both educationally valuable and feasible. Additionally, the curriculum offers a validated simulation-based training modality within ureteroscopy and a framework for the development of other simulation-based programmes.

  17. Technical Teachers and Technical Teacher Education - Research Results

    Directory of Open Access Journals (Sweden)

    D. Dobrovská

    2002-01-01

    Full Text Available Chartered engineers who are new teachers of technical subjects at various educational institutions receive technical teacher education in the accredited bachelor programme at the Czech Technical University in Prague. This paper presents the results of a recent survey in which engineers expressed their opinions on technical teacher education.

  18. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Aristos Aristidou Natureworks); Robert Kean (NatureWorks); Tom Schechinger (IronHorse Farms, Mat); Stuart Birrell (Iowa State); Jill Euken (Wallace Foundation & Iowa State)

    2007-10-01

    /storage/transportation equipment and the processor would build and operate the plant. Pilot fermentation studies demonstrated dramatic improvements in yields and rates with optimization of batch fermentor parameters. Demonstrated yields and rates are approaching those necessary for profitable commercial operation for production of ethanol or lactic acid. The ability of the biocatalyst to adapt to biomass hydrolysate (both biomass sugars and toxins in the hydrolysate) was demonstrated and points towards ultimate successful commercialization of the technology. However, some of this work will need to be repeated and possibly extended to adapt the final selected biocatalyst for the specific commercial hydrolysate composition. The path from corn stover in the farm field to final products, involves a number of steps. Each of these steps has options, problems, and uncertainties; thus creating a very complex multidimensional obstacle to successful commercial development. Through the tasks of this project, the technical and commercial uncertainties of many of these steps have been addressed; thus providing for a clearer understanding of paths forward and commercial viability of a corn stover-based biorefinery.

  19. Branch technical position for performance assessment of low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Campbell, A.C.; Abramson, L.; Byrne, R.M.

    1994-01-01

    The U.S. Nuclear Regulatory Commission has developed a Draft Branch Technical Position on Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. The draft technical position addresses important issues in performance assessment modeling and provides a framework and technical basis for conducting and evaluating performance assessments in a disposal facility license application. The technical position also addresses specific technical policy issues and augments existing NRC guidance pertaining to LLW performance assessment

  20. Career and Technical Education. 2016 Annual Report

    Science.gov (United States)

    Utah System of Higher Education, 2016

    2016-01-01

    Career and Technical Education (CTE) is a key ingredient to meet the needs of Utah's economy. Utah System of Higher Education (USHE) institutions offer CTE programs in all regions of the state, working closely with local business and industry leaders to develop and deliver programs specifically tailored to local workforce development needs. This…

  1. Career and Technical Education. 2015 Annual Report

    Science.gov (United States)

    Utah System of Higher Education, 2015

    2015-01-01

    Career and Technical Education (CTE) is a key ingredient to meet the needs of Utah's economy. Utah System of Higher Education (USHE) institutions offer CTE programs in all regions of the state, working closely with local business and industry leaders to develop and deliver programs specifically tailored to local workforce development needs. This…

  2. Technical training: places available

    CERN Multimedia

    2013-01-01

    If you would like more information on a course, or for any other inquiry/suggestions, please contact Technical.Training@cern.ch Valeria Perez Reale, Learning Specialist, Technical Programme Coordinator (Tel.: 62424) Eva Stern and Elise Romero, Technical Training Administration (Tel.: 74924)   Electronics design Next Session Duration Language Introduction to VHDL 21-Feb-13 to 22-Feb-13 2 days English Mechanical design Next Session Duration Language ANSYS - Introduction à ANSYS Mechanical APDL 04-Feb-13 to 07-Feb-13 4 days English Applications de la cotation fonctionnelle et du langage ISO 06-Feb-13 to 08-Feb-13 2 days 4 hours French CATIA V5 – Surfacique 14-Jan-13 to 15-Jan-13 2 days French Office software Next Session Duration Language ACCESS 2010 - niveau 2 : ECDL 06-Feb-13 to 07-Feb-13 2 days French Dreamweaver CS3 - Niveau 1 14-Jan-13 to 15-Jan-13 2 d...

  3. Technical training - Places available

    CERN Multimedia

    2012-01-01

    If you would like more information on a course, or for any other inquiry/suggestions, please contact Technical.Training@cern.ch Valeria Perez Reale, Learning Specialist, Technical Programme Coordinator (Tel.: 62424) Eva Stern and Elise Romero, Technical Training Administration (Tel.: 74924)   Electronics design Next Session Duration Language Availability Certified LabVIEW Associate Developer (CLAD) 06-Dec-12 to 06-Dec-12 1 hour English One more place available Compatibilité électromagnetique (CEM): Applications 23-Nov-12 to 23-Nov-12 3.5 hours English 3 places available Compatibilité électromagnétique (CEM): Introduction 23-Nov-12 to 23-Nov-12 3 hours English 43 places available Effets des Radiations sur les composants et systèmes électroniques 11-Dec-12 to 12-Dec-12 1 day 4 hours French 9 places available LabVIEW for beginners ...

  4. Windows 10 Technical Preview

    OpenAIRE

    Jyväsjärvi, Teppo

    2015-01-01

    Tässä opinnäytetyössä tutustaan uuden kesällä 2015 virallisesti julkaistavan Windows 10 -käyttöjärjestelmän Technical Preview -kehitysversioon. Ensimmäinen Technical Preview -versio julkaistiin syksyllä 2014. Opinnäytetyössä tutustaan Windows 10:n uusin ominaisuuksiin ja tehdään vertailua aiemman Windows 8.1 -version kanssa. Työssä Windows 10 Technical Preview asennetaan virtuaalikoneelle, käydään läpi asennuksen eri vaiheet sekä suurimmat muutokset käyttöliittymässä ja sovelluksissa. Op...

  5. Technical training - places available

    CERN Multimedia

    2012-01-01

    If you would like more information on a course, or for any other inquiry/suggestions, please contact Technical.Training@cern.ch Valeria Perez Reale, Learning Specialist, Technical Programme Coordinator (Tel.: 62424) Eva Stern and Elise Romero, Technical Training Administration (Tel.: 74924) HR Department »Electronics design Next Session Duration Language Availability Comprehensive VHDL for FPGA Design 08-Oct-12 to 12-Oct-12 5 days English 3 places available Foundations of Electromagnetism and Magnet Design (EMAG) 14-Nov-12 to 27-Nov-12 6 days English 20 places available Impacts de la suppression du plomb (RoHS) en électronique 26-Oct-12 to 26-Oct-12 8 hours French 15 places available Introduction to VHDL 10-Oct-12 to 11-Oct-12 2 days English 7 places available LabVIEW Real Time and FPGA 13-Nov-12 to 16-Nov-12 5 days French 5 places available »Mechanical design Next Se...

  6. Fuel Element Technical Manual

    Energy Technology Data Exchange (ETDEWEB)

    Burley, H.H. [ed.

    1956-08-01

    It is the purpose of the Fuel Element Technical Manual to Provide a single document describing the fabrication processes used in the manufacture of the fuel element as well as the technical bases for these processes. The manual will be instrumental in the indoctrination of personnel new to the field and will provide a single data reference for all personnel involved in the design or manufacture of the fuel element. The material contained in this manual was assembled by members of the Engineering Department and the Manufacturing Department at the Hanford Atomic Products Operation between the dates October, 1955 and June, 1956. Arrangement of the manual. The manual is divided into six parts: Part I--introduction; Part II--technical bases; Part III--process; Part IV--plant and equipment; Part V--process control and improvement; and VI--safety.

  7. Recommendations of technical specifications for ethanol and its blends (E6) and the infrastructure for their management in Mexico; Recomendaciones de especificaciones tecnicas para el etanol y sus mezclas (E6) y la infraestructura para su manejo en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-15

    This paper describes the importance and benefits of using ethanol-gasoline blend as a substitute for pure gasoline. It presents data of global ethanol market, as well as major producers, processes involved for different raw materials and productivity indicators. It discusses the main properties to be monitored in ethanol and the importance of each one. It also examines the impact of the addition of ethanol in automotive gasoline and the influence of each property in the operation of the cars and the environment. It presents an assessment of the international specifications anhydrous ethanol used in the United States, Brazil and the European Union as well as suggestions for limits harmonization of the main parameters and methodologies, from recently published studies (White Paper-Bioetahnol Guidelines Task Force and to Ethanol from Worldwide Fuel Charter Committee). It includes the specification of Brazilian gasoline, added with 25% of ethanol (E25). It suggests an anhydrous ethanol specification and a specification for gasoline mixtures / ethanol E6 for implementation in Mexico. It presents a prioritization of laboratory testing methods for ethanol and ethanol-blended gasoline in three categories, indicating the most appropriate test to be used at different points in the distribution chain of products. It discusses the impact of ethanol on the distribution facilities for fuels, actions to control potential problems, selection of materials and equipment, safety procedures and presents the mixing gasoline / ethanol. It also describes the Brazilian system of production / distribution of fuels and the experience of this country to control fuel quality from the legislation. It includes a table with the top teams, their costs, Brazilian suppliers and a list of Brazilian standards for fuel storage and transport. Finally, we present some suggestions that may be important to ensure the evolution of specifications of ethanol and ethanol-blended gasoline in the course of the

  8. Innovative technical plasma applications

    International Nuclear Information System (INIS)

    Wintner, E.

    2013-01-01

    Plasma is the predominant status of matter, in stars as well as in interstellar space. In science, it was only recognized rather late as a specific (fourth) state of matter: Sir William Crookes described it in 1879 as “radiant matter”, Irving Langmuir created the name “plasma” in 1928. Technically generated plasma is employed very broadly in modern technology. Some examples are Plasma Displays, Fluorescent Lamps (also the modern Energy Saving Lamps), Corona Discharges (for e.g. Ozone generation, or even engine ignition), arc welding and cutting, reactive ion etching, mass spectroscopy, ion rocket engines and many more. Very early since the development of the laser, it was also employed to generate a plasma (spark) in air or on surfaces. Generally, for this purpose at least ns (“Giant”) pulses have to be used. In more recent times, pico- and femtosecond pulses have allowed to create plasma very easily and effectively. Laser fusion may represent the ultimate application in this direction, based on highly amplified ns pulses for inertial confinement or ps pulses designed as fast igniter. The idea of employing laser pulses for the ignition of engines was attempted for the first time in 1978, although with inadequate tools like the CO2 laser. After a long time of inactivity in this field, about 10 years ago a few institutions like Vienna University of Technology first resumed this approach with the help of modern type solid-state lasers and started systematic investigations around the idea of laser ignition of internal combustion engines. Now, this technique has reached a high degree of maturity; remaining problems lie on the development level and are to be solved soon. Ambitious product development by leading engine producers or ignition equipment suppliers has been started world-wide since several years and, as a result, in one or two years laser ignition will probably be imple-mented into high power gas engines or, somewhat later, high-priced automotive

  9. Human research ethics committees in technical universities.

    Science.gov (United States)

    Koepsell, David; Brinkman, Willem-Paul; Pont, Sylvia

    2014-07-01

    Human research ethics has developed in both theory and practice mostly from experiences in medical research. Human participants, however, are used in a much broader range of research than ethics committees oversee, including both basic and applied research at technical universities. Although mandated in the United States, the United Kingdom, Canada, and Australia, non-medical research involving humans need not receive ethics review in much of Europe, Asia, Latin America, and Africa. Our survey of the top 50 technical universities in the world shows that, where not specifically mandated by law, most technical universities do not employ ethics committees to review human studies. As the domains of basic and applied sciences expand, ethics committees are increasingly needed to guide and oversee all such research regardless of legal requirements. We offer as examples, from our experience as an ethics committee in a major European technical university, ways in which such a committee provides needed services and can help ensure more ethical studies involving humans outside the standard medical context. We provide some arguments for creating such committees, and in our supplemental article, we provide specific examples of cases and concerns that may confront technical, engineering, and design research, as well as outline the general framework we have used in creating our committee. © The Author(s) 2014.

  10. Technical memory 2007

    International Nuclear Information System (INIS)

    2009-01-01

    The technical memory 2007 of the Nuclear Regulatory Authority (ARN) of the Argentine Republic, compiles the papers published in the subject on radiation protection and nuclear safety, and presented in journals, technical reports, congress or meetings of these specialities by personnel of the mentioned institution during 2007. In this edition the documents are presented on: environmental protection; transport of radioactive materials; regulations; research reactors and nuclear power plants; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; physical dosimetry; knowledge management; radioactive waste management [es

  11. Transformation of technical infrastructure

    DEFF Research Database (Denmark)

    Nielsen, Susanne Balslev

    , the evolution of large technological systems and theories about organisational and technological transformationprocesses. The empirical work consist of three analysis at three different levels: socio-technical descriptions of each sector, an envestigation of one municipality and envestigations of one workshop......The scope of the project is to investigate the possibillities of - and the barriers for a transformation of technical infrastructure conserning energy, water and waste. It focus on urban ecology as a transformation strategy. The theoretical background of the project is theories about infrastructure...

  12. CERN Technical Training : Vista !

    CERN Multimedia

    HR Department

    2008-01-01

    You are running Vista on your new PC – or are planning to install it? The Technical Training service is organizing a half-day training course on the new features of the VISTA operating system. This course introduces the new interfaces and presents the new functionalities for people who are experienced in the use of Windows XP. The next bilingual sessions of this course will take place on 12 December 2008 and 30 January 2009. Register using our catalogue: http://cta.cern.ch/cta2/f?p=110:9 or contact us with your questions/comments at mailto:Technical.Training@cern.ch

  13. CERN Technical Training : Vista !

    CERN Multimedia

    HR Department

    2009-01-01

    Are you running Vista on your new PC – or are you planning to install it? The Technical Training service is organizing a half-day training course on the new features of the VISTA operating system. This course introduces the new interfaces and presents the new functionalities for people who are experienced in the use of Windows XP. The next bilingual session of this course will take place on 30 January 2009. Register using our catalogue: http://cta.cern.ch/cta2/f?p=110:9 or contact us with your questions/comments at mailto:Technical.Training@cern.ch

  14. CERN Technical Training : Vista !

    CERN Multimedia

    HR Department

    2008-01-01

    You are running Vista on your new PC – or are planning to install it? The Technical Training service is organizing a half-day training on the new features of the VISTA operating system. This course introduces the new interfaces and presents the new functionalities for people who are experienced using Windows XP. The next bilingual sessions of this course will take place on December 12, 2008 and January 30, 2009. Register using our catalogue : http://cta.cern.ch/cta2/f?p=110:9 or contact us with your questions/comments at Technical.Training@cern.ch

  15. CERN Technical Training : Vista !

    CERN Multimedia

    HR Department

    2008-01-01

    Are you running Vista on your new PC – or are you planning to install it? The Technical Training service is organizing a half-day training course on the new features of the VISTA operating system. This course introduces the new interfaces and presents the new functionalities for people who are experienced in the use of Windows XP. The next bilingual sessions of this course will take place on 12 December 2008 and 30 January 2009. Register using our catalogue: http://cta.cern.ch/cta2/f?p=110:9 or contact us with your questions/comments at mailto:Technical.Training@cern.ch

  16. CERN Technical Training : Vista !

    CERN Multimedia

    HR Department

    2008-01-01

    Are you running Vista on your new PC – or are planning to install it? The Technical Training service is organizing a half-day training course on the new features of the VISTA operating system. This course introduces the new interfaces and presents the new functionalities for people who are experienced in the use of Windows XP. The next bilingual sessions of this course will take place on 12 December 2008 and 30 January 2009. Register using our catalogue: http://cta.cern.ch/cta2/f?p=110:9 or contact us with your questions/comments at Technical.Training@cern.ch

  17. New strategies for designing inexpensive but selective bioadsorbants for environmental pollutants: Selection of specific ligands and their cell surface expression. Technical progress report, September 15, 1996 -September 14, 1997

    International Nuclear Information System (INIS)

    Iverson, B.

    1997-01-01

    'Progress for the last twelve months has revolved around setting up an antibody engineering and surface display system for use with a metal-complex binding antibody. (1) The author has isolated genes for the V regions of the heavy and light chains for the Ru(bpy)3 specific monoclonal AC1106 (Shreder, K S., Hariman, A., and Iverson, B.L., J. Am. Chem. Soc. 1996, 118, 3192-3201). This antibody binds Ru(bpy), derivatives with better than nanomolar affinity, and will serve as the generic metal-complex binding pocket. Cloning antibody genes from hybridomas is complicated by the fact that primers must be found that amplify the particular heavy and light chain genes in the hybridoma of interest. Antibody gene amplification primers are generally designed to amplify antibody repertoires from lymphocyte mRNA isolated from animals. While cloning repertoires from animals is routinely successful due to the diverse population of target m RNA, hybridomas have a single target sequence. Therefore, multiple primers and conditions must be tried before the correct primer combination is identified.'

  18. Solar energy task force report technical training guidelines

    Energy Technology Data Exchange (ETDEWEB)

    O& #x27; Connor, K

    1979-10-01

    Guidelines are offered for programs oriented to commercial applications in solar energy, specifically water and space heating. These technologies are examined because they are, in some cases, economicaly feasible. Sample curricula and programs, technical jobs and skills, and equipment are suggested to assist those institutions contemplating the development of technical training. (MHR)

  19. technical efficiency and its determinants at different levels of ...

    African Journals Online (AJOL)

    Osondu

    2012-03-30

    Mar 30, 2012 ... Abstract. Examining the level of farm-specific technical efficiency of maize-based farming households in. Southern-Guinea Savanna (SGS) of Nigeria, this study fitted cross-sectional data into a Cobb-. Douglass production frontier. The study examined technical efficiency and its determinants.

  20. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Howe, Gary [RTI International, Research Triangle Park, NC (United States); Albritton, John [RTI International, Research Triangle Park, NC (United States); Denton, David [RTI International, Research Triangle Park, NC (United States); Turk, Brian [RTI International, Research Triangle Park, NC (United States); Gupta, Raghubir [RTI International, Research Triangle Park, NC (United States)

    2018-01-31

    technology has great potential to provide clean syngas from coal and petcoke-based gasification at increased efficiency and at significantly lower capital and operating costs than conventional syngas cleanup technologies. However, before the technology can be deemed ready for scale-up to a full commercial-scale demonstration, additional R&D testing is needed at the site to address the following critical technical risks: WDP sorbent stability and performance; Impact of WDP on downstream cleanup and conversion steps; Metallurgy and refractory; Syngas cleanup performance and controllability; Carbon capture performance and additional syngas cleanup The proposed plan to acquire this additional R&D data involves: Operation of the units to achieve an additional 3,000 hours of operation of the system within the performance period, with a target of achieving 1,000 hours of those hours via continuous operation of the entire integrated pre-commercial demonstration system; Rapid turnaround of repairs and/or modifications required as necessary to return any specific unit to operating status with documentation and lessons learned to support technology maturation, and; Proactive performance of maintenance activities during any unplanned outages and if possible while operating.

  1. Technical Writing in Hydrogeology.

    Science.gov (United States)

    Tinker, John R., Jr.

    1986-01-01

    A project for Writing Across the Curriculum at the University of Wisconsin-Eau Claire is described as a method to relate the process of writing to the process of learning hydrology. The project focuses on an actual groundwater contamination case and is designed to improve the technical writing skills of students. (JN)

  2. Technical Training: Places available

    CERN Multimedia

    Monique Duval

    2005-01-01

    The number of places available may vary. Please check our Web site to find out the current availability. Places are available on the following courses: LabVIEW Real-Time (F) : 7 - 9.6.2005 (3 jours) LabVIEW Migration 6 to 7: 14.6.2005 (1 day) IT3T/1 - Read your mail and more with Outlook 2003 : 14.6.2005 (IT Technical Training Tutorial, free of charge) IT3T/2 - Creating, managing and using distribution lists with Simba2 : 16.6.2005 (IT Technical Training Tutorial, free of charge) FrontPage 2003 - niveau 2 : 16 & 17.6.2005 (2 jours) Utilisation de fichiers PDF avec ACROBAT 6.0 : 20.6.2005 (1journée) Introduction to ANSYS: 21 - 24.6.2005 (4 days) IT3T/3 - Working remotely with Windows XP : 28.6.2005 (IT Technical Training Tutorial, free of charge) IT3T/4 - Editing Websites with Frontpage 2003 : 30.6.2005 (IT Technical Training Tutorial, free of charge) WORD 2003 (Short Course I) - HowTo... Work with repetitive tasks /AutoText, AutoFormat, AutoC...

  3. Technical objectives of inspection

    International Nuclear Information System (INIS)

    Sorenson, R.J.; Stewart, K.B.; Schneider, R.A.

    1976-01-01

    The various technical objectives of inspection are discussed in a very general manner. The discussion includes how the inspection function is related to the assumed threat, the various degrees of assurance and reliance on criteria, and the hierarchy of assurance which is obtained from the various types or levels of inspection

  4. Technical basis of safeguards

    International Nuclear Information System (INIS)

    Buechler, C.

    1975-01-01

    Definition of nuclear materials control. Materials accountancy and physical control as technical possibilities. Legal possibilities and levels of responsibility: material holders, national and international authority. Detection vs. prevention. Physical security and containment surveillance. Accountancy: materials balance concept. Materials measurement: inventory taking, flow determination. IAEA safeguards; verification of operator's statement. (HP) [de

  5. ITER EDA technical activities

    International Nuclear Information System (INIS)

    Aymar, R.

    1998-01-01

    Six years of technical work under the ITER EDA Agreement have resulted in a design which constitutes a complete description of the ITER device and of its auxiliary systems and facilities. The ITER Council commented that the Final Design Report provides the first comprehensive design of a fusion reactor based on well established physics and technology

  6. Technical Training: Places available

    CERN Multimedia

    Monique Duval

    2005-01-01

    The number of places available may vary. Please check our Web site to find out the current availability. Places are available on the following courses: LabVIEW Migration 6 to 7: 14.6.2005 (1 day) IT3T/1 - Read your mail and more with Outlook 2003 : 14.6.2005 (IT Technical Training Tutorial, free of charge) IT3T/2 - Creating, managing and using distribution lists with Simba2 : 16.6.2005 (IT Technical Training Tutorial, free of charge) FrontPage 2003 - niveau 2 : 16 & 17.6.2005 (2 jours) size="2">(1journée) Hands-on Introduction to Python Programming: 28 - 30.6.2005 (3 days) Introduction to ANSYS: 21 - 24.6.2005 (4 days) IT3T/3 - Working remotely with Windows XP: 28.6.2005 (IT Technical Training Tutorial, free of charge) IT3T/4 - Editing Websites with Frontpage 2003: 30.6.2005 (IT Technical Training Tutorial, free of charge) LabVIEW base 1 : 4 - 6.7.2005 (3 jours) LabVIEW Basics 2: AutoCorrect, Find/Replace) : 4.7.2005 (afternoon) WORD 2003 (Shor...

  7. Final technical report

    DEFF Research Database (Denmark)

    Juhl, Thomas Winther; Nielsen, Jakob Skov

    This project entails research with the goal to extend laser cutting of steel based metals to thickness above 20 mm and laser powers in the 10 kW range, with adequate accuracy and economically viable cutting speeds. The technical approach is to develop mirror based cutting heads with truly coaxial...

  8. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    John Ross

    2003-04-30

    The Final Technical Report summarizes research accomplishments and Publications in the period of 5/1/99 to 4/30/03 done on the grant. Extensive progress was made in the period covered by this report in the areas of chemical kinetics of non-linear systems; spatial structures, reaction - diffusion systems, and thermodynamic and stochastic theory of electrochemical and general systems.

  9. MCFire model technical description

    Science.gov (United States)

    David R. Conklin; James M. Lenihan; Dominique Bachelet; Ronald P. Neilson; John B. Kim

    2016-01-01

    MCFire is a computer program that simulates the occurrence and effects of wildfire on natural vegetation, as a submodel within the MC1 dynamic global vegetation model. This report is a technical description of the algorithms and parameter values used in MCFire, intended to encapsulate its design and features a higher level that is more conceptual than the level...

  10. Final Technical Report

    International Development Research Centre (IDRC) Digital Library (Canada)

    Tommy Ngai

    2014-03-31

    Mar 31, 2014 ... capacity building activities) to upgrade the technical and management capacities of governments ..... Elements of evaluation are required throughout the chain of activities in order to undertake a ...... Department of Water Supply and Sewerage Pokhara, Pokhara Engineering College, Choice Nepal, and.

  11. PISA 2009 Technical Report

    Science.gov (United States)

    OECD Publishing (NJ1), 2012

    2012-01-01

    The "PISA 2009 Technical Report" describes the methodology underlying the PISA 2009 survey. It examines additional features related to the implementation of the project at a level of detail that allows researchers to understand and replicate its analyses. The reader will find a wealth of information on the test and sample design,…

  12. PISA 2012 Technical Report

    Science.gov (United States)

    OECD Publishing, 2014

    2014-01-01

    The "PISA 2012 Technical Report" describes the methodology underlying the PISA 2012 survey, which tested 15-year-olds' competencies in mathematics, reading and science and, in some countries, problem solving and financial literacy. It examines the design and implementation of the project at a level of detail that allows researchers to…

  13. Materials Technical Team Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2013-08-01

    Roadmap identifying the efforts of the Materials Technical Team (MTT) to focus primarily on reducing the mass of structural systems such as the body and chassis in light-duty vehicles (including passenger cars and light trucks) which enables improved vehicle efficiency regardless of the vehicle size or propulsion system employed.

  14. Technical memory 1999

    International Nuclear Information System (INIS)

    2000-01-01

    The technical memory 1999 of the Nuclear Regulatory Authority (NRA) of the Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety, safeguards and physical protection, and presented in congress or meetings of these specialities by personnel of the mentioned institution during 1999

  15. Succession planning for technical experts

    Energy Technology Data Exchange (ETDEWEB)

    Kirk, Bernadette Lugue [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Cain, Ronald A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dewji, Shaheen A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Agreda, Carla L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-07-01

    This report describes a methodology for identifying, evaluating, and mitigating the loss of key technical skills at nuclear operations facilities. The methodology can be adapted for application within regulatory authorities and research and development organizations, and can be directly applied by international engagement partners of the Department of Energy’s National Nuclear Security Administration (NNSA). The resultant product will be of direct benefit to two types of NNSA missions: (1) domestic human capital development programs tasked to provide focused technical expertise to succeed an aging nuclear operations workforce, and (2) international safeguards programs charged with maintaining operational safeguards for developing/existing nuclear power program in nations where minimal available resources must be used effectively. This report considers succession planning and the critical skills necessary to meet an institution’s goals and mission. Closely tied to succession planning are knowledge management and mentorship. In considering succession planning, critical skill sets are identified and are greatly dependent on the subject matter expert in question. This report also provides examples of critical skills that are job specific.

  16. Technical approach to groundwater restoration

    International Nuclear Information System (INIS)

    1993-01-01

    The Technical Approach to Groundwater Restoration (TAGR) provides general technical guidance to implement the groundwater restoration phase of the Uranium Mill Tailings Remedial Action (UMTRA) Project. The TAGR includes a brief overview of the surface remediation and groundwater restoration phases of the UMTRA Project and describes the regulatory requirements, the National Environmental Policy Act (NEPA) process, and regulatory compliance. A section on program strategy discusses program optimization, the role of risk assessment, the observational approach, strategies for meeting groundwater cleanup standards, and remedial action decision-making. A section on data requirements for groundwater restoration evaluates the data quality objectives (DQO) and minimum data required to implement the options and comply with the standards. A section on sits implementation explores the development of a conceptual site model, approaches to site characterization, development of remedial action alternatives, selection of the groundwater restoration method, and remedial design and implementation in the context of site-specific documentation in the site observational work plan (SOWP) and the remedial action plan (RAP). Finally, the TAGR elaborates on groundwater monitoring necessary to evaluate compliance with the groundwater cleanup standards and protection of human health and the environment, and outlines licensing procedures

  17. Succession planning for technical experts

    International Nuclear Information System (INIS)

    Kirk, Bernadette Lugue; Cain, Ronald A.; Dewji, Shaheen A.; Agreda, Carla L.

    2017-01-01

    This report describes a methodology for identifying, evaluating, and mitigating the loss of key technical skills at nuclear operations facilities. The methodology can be adapted for application within regulatory authorities and research and development organizations, and can be directly applied by international engagement partners of the Department of Energy’s National Nuclear Security Administration (NNSA). The resultant product will be of direct benefit to two types of NNSA missions: (1) domestic human capital development programs tasked to provide focused technical expertise to succeed an aging nuclear operations workforce, and (2) international safeguards programs charged with maintaining operational safeguards for developing/existing nuclear power program in nations where minimal available resources must be used effectively. This report considers succession planning and the critical skills necessary to meet an institution’s goals and mission. Closely tied to succession planning are knowledge management and mentorship. In considering succession planning, critical skill sets are identified and are greatly dependent on the subject matter expert in question. This report also provides examples of critical skills that are job specific.

  18. Technical aspects of MR perfusion

    International Nuclear Information System (INIS)

    Sourbron, Steven

    2010-01-01

    The most common methods for measuring perfusion with MRI are arterial spin labelling (ASL), dynamic susceptibility contrast (DSC-MRI), and T 1 -weighted dynamic contrast enhancement (DCE-MRI). This review focuses on the latter approach, which is by far the most common in the body and produces measures of capillary permeability as well. The aim is to present a concise but complete overview of the technical issues involved in DCE-MRI data acquisition and analysis. For details the reader is referred to the references. The presentation of the topic is essentially generic and focuses on technical aspects that are common to all DCE-MRI measurements. For organ-specific problems and illustrations, we refer to the other papers in this issue. In Section 1 'Theory' the basic quantities are defined, and the physical mechanisms are presented that provide a relation between the hemodynamic parameters and the DCE-MRI signal. Section 2 'Data acquisition' discusses the issues involved in the design of an optimal measurement protocol. Section 3 'Data analysis' summarizes the steps that need to be taken to determine the hemodynamic parameters from the measured data.

  19. Place-Specific Computing

    DEFF Research Database (Denmark)

    Messeter, Jörn

    2009-01-01

    An increased interest in the notion of place has evolved in interaction design based on the proliferation of wireless infrastructures, developments in digital media, and a ‘spatial turn’ in computing. In this article, place-specific computing is suggested as a genre of interaction design...... that addresses the shaping of interactions among people, place-specific resources and global socio-technical networks, mediated by digital technology, and influenced by the structuring conditions of place. The theoretical grounding for place-specific computing is located in the meeting between conceptions...... examples of place-specific computing are presented from a series of pilot studies, conducted in close collaboration with design students in Malmö, Berlin, Cape Town and Rome, that generated 36 design concepts in the genre. Reflecting on these examples, issues in the design of place-specific computing...

  20. Explicating the Sustainable Design of Technical Artefacts

    DEFF Research Database (Denmark)

    Vissonova, Karina

    2016-01-01

    afforded by the properties of artefacts. The study is a conceptual analysis and as such belongs to the field of epistemology of design. It offers three contributions to the design discipline: (1) a proposition of the definition of the sustainable design kind; (2) a proposition of the concept of technical......Sustainable design of technical artefacts is referred to as if it were a kind of design with some specific characteristics. However, in design research and practice alike, there appears to be a lack of shared conceptions of what such a design might entail. Furthermore, we have no clear grounds...... for evaluating what makes the sustainable design solutions permissible. The lack of shared conceptions is largely due to ambiguities associated with the notion of sustainability. In response to these challenges, the aim of my study is to offer a definition of sustainable design of technical artefacts. I argue...

  1. INMM Physical Protection Technical Working Group Workshops

    International Nuclear Information System (INIS)

    Williams, J.D.

    1982-01-01

    The Institute of Nuclear Materials Management (INMM) established the Physical Protection Technical Working Group to be a focal point for INMM activities related to the physical protection of nuclear materials and facilities. The Technical Working Group has sponsored workshops with major emphasis on intrusion detection systems, entry control systems, and security personnel training. The format for these workshops has consisted of a series of small informal group discussions on specific subject matter which allows direct participation by the attendees and the exchange of ideas, experiences, and insights. This paper will introduce the reader to the activities of the Physical Protection Technical Working Group, to identify the workshops which have been held, and to serve as an introduction to the following three papers of this session

  2. The International Technical Safety Forum

    CERN Multimedia

    CERN Bulletin

    2010-01-01

    The International Technical Safety Forum is a meeting of safety experts from several physics labs in Europe and the US. Since 1998 participants have been meeting every couple of years to discuss common challenges in safety matters. The Forum helps them define best practices and learn from the important lessons learned by others.   The Forum's participants in front of building 40. This year, the meeting took place at CERN from 12 to 16 April. “This year's meeting covered subjects ranging from communication and training in matters of safety, to cryogenic safety, emergency preparedness and risk analysis”, explains Ralf Trant, head of the CERN Safety Commission and organiser of this year’s Forum. Radiation protection issues are not discussed at the meeting since they involve different expertise. The goal of the Forum is to allow participants to share experience, learn lessons and acquire specific knowledge in a very open way. Round-table discussions, dedicated time for ...

  3. TurboTech Technical Evaluation Automated System

    Science.gov (United States)

    Tiffany, Dorothy J.

    2009-01-01

    TurboTech software is a Web-based process that simplifies and semiautomates technical evaluation of NASA proposals for Contracting Officer's Technical Representatives (COTRs). At the time of this reporting, there have been no set standards or systems for training new COTRs in technical evaluations. This new process provides boilerplate text in response to interview style questions. This text is collected into a Microsoft Word document that can then be further edited to conform to specific cases. By providing technical language and a structured format, TurboTech allows the COTRs to concentrate more on the actual evaluation, and less on deciding what language would be most appropriate. Since the actual word choice is one of the more time-consuming parts of a COTRs job, this process should allow for an increase in quantity of proposals evaluated. TurboTech is applicable to composing technical evaluations of contractor proposals, task and delivery orders, change order modifications, requests for proposals, new work modifications, task assignments, as well as any changes to existing contracts.

  4. Engineering Technical Support Center Annual Report Fiscal ...

    Science.gov (United States)

    The United States Environmental Protection Agency (EPA or Agency) Office of Research and Development (ORD) created the Engineering Technical Support Center (ETSC) in 1987, one of several technical support centers created as part of the Technical Support Project (TSP). ETSC provides engineering expertise to Agency program and regional offices and remediation teams working at contaminated sites across the country. The ETSC is operated within ORD’s Land Remediation and Pollution Control Division (LRPCD) of the National Risk Management Research Laboratory (NRMRL) in Cincinnati, Ohio. The ETSC’s mission is to provide site-specific scientific and engineering technical support to Remedial Project Managers, On-Scene Coordinators, and other remediation personnel at contaminated sites. This allows local, regional, or national authorities to work more quickly, efficiently, and cost effectively, while also increasing the technical experience of the remediation team. Since its inception, the ETSC has supported countless projects across all EPA Regions in almost all states and territories. This report highlights significant projects the ETSC supported in fiscal year 2015 (FY15). These projects addressed an array of environmental scenarios, such as remote mining contamination, expansive landfill waste, cumulative impacts from multiple contamination sources, and persistent threats from abandoned industrial sites. Constructing and testing new and innovative treatment technol

  5. Bioethics for Technical Experts

    Science.gov (United States)

    Asano, Shigetaka

    Along with rapidly expanding applications of life science and technology, technical experts have been implicated more and more often with ethical, social, and legal problems than before. It should be noted that in this background there are scientific and social uncertainty elements which are inevitable during the progress of life science in addition to the historically-established social unreliability to scientists and engineers. In order to solve these problems, therefore, we should establish the social governance with ‘relief’ and ‘reliance’ which enables for both citizens and engineers to share the awareness of the issues, to design social orders and criterions based on hypothetical sense of values for bioethics, to carry out practical use management of each subject carefully, and to improve the sense of values from hypothetical to universal. Concerning these measures, the technical experts can learn many things from the present performance in the medical field.

  6. Sources of technical assistance

    International Nuclear Information System (INIS)

    Laue, H.J.

    1977-01-01

    This paper shows examples of technical assistance programmes within bilateral cooperation agreements between the Federal Republic of Germany and a number of developing countries of very different characteristics and summarizes the possibilities of technical assistance granted by international organizations, such as IAEA, UNDP, etc. A basic requirement for a successful transfer of technology is a high knowledge level of the indigenous scientists and engineers. Therefore, programmes for training and education and for information exchange are presented. Based on these, the means and methods of planning, performance and quality assurance are explained by practical examples and are related to the progress achieved in the use of nuclear energy and in establishing a national industry in the developing countries. (orig.) [de

  7. Technical Training: Places available

    CERN Multimedia

    Monique Duval

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an 'application for training' form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: The Joint PVSS JCOP Framework: 14 - 18.6.2004 (5 days) EXCEL 2003 - niveau 2 : 17 & 18.6.2004 (2 jours) MAGNE-04 : Magnétisme pour l'électrotechnique : 6 au 8.7.2004 (3 jours) Technical Training Monique Duval - Tel.74924 technical.training@cern.ch

  8. Independent technical review, handbook

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    Purpose Provide an independent engineering review of the major projects being funded by the Department of Energy, Office of Environmental Restoration and Waste Management. The independent engineering review will address questions of whether the engineering practice is sufficiently developed to a point where a major project can be executed without significant technical problems. The independent review will focus on questions related to: (1) Adequacy of development of the technical base of understanding; (2) Status of development and availability of technology among the various alternatives; (3) Status and availability of the industrial infrastructure to support project design, equipment fabrication, facility construction, and process and program/project operation; (4) Adequacy of the design effort to provide a sound foundation to support execution of project; (5) Ability of the organization to fully integrate the system, and direct, manage, and control the execution of a complex major project.

  9. Independent technical review, handbook

    International Nuclear Information System (INIS)

    1994-02-01

    Purpose Provide an independent engineering review of the major projects being funded by the Department of Energy, Office of Environmental Restoration and Waste Management. The independent engineering review will address questions of whether the engineering practice is sufficiently developed to a point where a major project can be executed without significant technical problems. The independent review will focus on questions related to: (1) Adequacy of development of the technical base of understanding; (2) Status of development and availability of technology among the various alternatives; (3) Status and availability of the industrial infrastructure to support project design, equipment fabrication, facility construction, and process and program/project operation; (4) Adequacy of the design effort to provide a sound foundation to support execution of project; (5) Ability of the organization to fully integrate the system, and direct, manage, and control the execution of a complex major project

  10. El Salvador - Formal Technical Education

    Data.gov (United States)

    Millennium Challenge Corporation — With a budget of nearly $20 million, the Formal Technical Education Sub-Activity was designed to strengthen technical and vocational educational institutions in the...

  11. Technical Leadership Development Program

    Science.gov (United States)

    2010-12-13

    the traditional tenets of leadership and management , systems thinking, understanding SOS issues, and thinking and acting holistically. Our research...international element 2.0 Enterprise Leadership and Management UNCLASSIFIED Contract Number: H98230-08-D-0171 DO 002. TO002, RT 004 Report No...mechanisms for leadership of the overall technical effort, for systems engineering, for requirements, management , and for systems integration. o Develop

  12. Technical approach document

    International Nuclear Information System (INIS)

    1989-12-01

    The Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law 95-604 (PL95-604), grants the Secretary of Energy the authority and responsibility to perform such actions as are necessary to minimize radiation health hazards and other environmental hazards caused by inactive uranium mill sites. This Technical Approach Document (TAD) describes the general technical approaches and design criteria adopted by the US Department of Energy (DOE) in order to implement remedial action plans (RAPS) and final designs that comply with EPA standards. It does not address the technical approaches necessary for aquifer restoration at processing sites; a guidance document, currently in preparation, will describe aquifer restoration concerns and technical protocols. This document is a second revision to the original document issued in May 1986; the revision has been made in response to changes to the groundwater standards of 40 CFR 192, Subparts A--C, proposed by EPA as draft standards. New sections were added to define the design approaches and designs necessary to comply with the groundwater standards. These new sections are in addition to changes made throughout the document to reflect current procedures, especially in cover design, water resources protection, and alternate site selection; only minor revisions were made to some of the sections. Sections 3.0 is a new section defining the approach taken in the design of disposal cells; Section 4.0 has been revised to include design of vegetated covers; Section 8.0 discusses design approaches necessary for compliance with the groundwater standards; and Section 9.0 is a new section dealing with nonradiological hazardous constituents. 203 refs., 18 figs., 26 tabs

  13. Technical training - Places available

    CERN Multimedia

    2012-01-01

    If you would like more information on a course, or for any other inquiry/suggestions, please contact Technical.Training@cern.ch Valeria Perez Reale, Learning Specialist, Technical Programme Coordinator (Tel.: 62424) Eva Stern and Elise Romero, Technical Training Administration (Tel.: 74924) HR Department Electronic Design Next Session Duration Language Availability Comprehensive VHDL for FPGA Design 08-Oct-12 to 12-Oct-12 5 days English 4 places Electrostatique / Protection ESD 28-Sep-12 to 28-Sep-12 3 hours French 25 places Impacts de la suppression du plomb (RoHS) en électronique 26-Oct-12 to 26-Oct-12 8 hours French 14 places Introduction to VHDL 10-Oct-12 to 11-Oct-12 2 days English 9 places LabVIEW Real Time and FPGA 13-Nov-12 to 16-Nov-12 5 days French 5 places LabVIEW for Experts 24-Sep-12 to 28-Sep-12 5 days English 6 places LabVIEW for beginners 15-Oct-12 to 17-...

  14. Manageability of Technical Innovation through Technical Property Rights

    Directory of Open Access Journals (Sweden)

    Michael Horeth

    2016-06-01

    Full Text Available The term innovation is used in many respects and has been evolving over the last decades. This paper mainly focusses on managing technical innovation and differentiates this kind of innovation from others. For managing technical innovation, this work applies technical property rights, patents and utility models. The opportunity to protect the companies’ technical knowledge legally is, apart from strategic measurements like trade secrecy, a very valuable tool to manage and commercialize innovation considering the shift from closed to rather open innovation. This paper discusses the applicability of legal protection measurements for the management of technical innovation containing a critical appraisal.

  15. Assessing Students' Technical Skill Attainment

    Science.gov (United States)

    Jorgensen, Haley

    2010-01-01

    The Wisconsin Technical College System (WTCS) is working to comply with the Carl D. Perkins Career and Technical Education Improvement Act of 2006 (Perkins) to ensure that its graduates have mastered the technical skills needed by business and industry. The legislation requires that each state identify and approve program assessment strategies…

  16. Technical specifications for the Oak Ridge Research Reactor

    International Nuclear Information System (INIS)

    1978-01-01

    The following sections are included: (1) glossary of terms, (2) safety limits and limiting safety system settings, (3) limiting conditions for operation, (4) surveillance requirements, (5) design features, and (6) administrative controls

  17. A decision making framework for risk-informed technical specifications

    International Nuclear Information System (INIS)

    Kim, B. S.; Kim, I. S.; Seo, M. S.; Sung, G. Y.

    2001-01-01

    The RITS literature survey on regulatory requirements and current TS research status in Korea as well as in foreign countries has been performed. Based on this survey, the RITS decision-making framework for the licensee and regulator point-of-view, respectively, is introduced in this paper. The required documents for the licensee to prepare are suggested in a systematic approach; the decision-making process of regulators for evaluating the documents is recommended

  18. Technical Specification for the CLIC Two-Beam Module

    CERN Document Server

    Riddone, G; Nousiainen, R; Samoshkin, A; Schulte, D; Syratchev, I; Wuensch, W; Zennaro, R

    2008-01-01

    A high-energy (0.5-3 TeV centre-of-mass), highluminosity Compact Linear Collider (CLIC) is being studied at CERN [1]. The CLIC main linacs, 21-km long each, are composed of 2-m long two beam modules. This paper presents their current layout, the main requirements for the different sub-systems (alignment, supporting, stabilization, cooling and vacuum) as well as the status of their integration.

  19. 10 CFR 61.12 - Specific technical information.

    Science.gov (United States)

    2010-01-01

    ... natural and demographic disposal site characteristics as determined by disposal site selection and... description of the design basis natural events or phenomena and their relationship to the principal design... intruder barriers; onsite traffic and drainage systems; survey control program; methods and areas of waste...

  20. Technical specifications for the Oak Ridge Research Reactor

    International Nuclear Information System (INIS)

    1986-05-01

    Information is presented concerning the Oak Ridge Research Reactor in the areas of: safety limits and limiting safety system settings; limiting conditions for operation; surveillance requirements; design features; administrative controls; and monitoring of effluents

  1. Instrument and Survey Analysis Technical Report: Program Implementation Survey. Technical Report #1112

    Science.gov (United States)

    Alonzo, Julie; Tindal, Gerald

    2011-01-01

    This technical document provides guidance to educators on the creation and interpretation of survey instruments, particularly as they relate to an analysis of program implementation. Illustrative examples are drawn from a survey of educators related to the use of the easyCBM learning system. This document includes specific sections on…

  2. Tracing the History of Technical Communication from 1850-2000: Plus a Series of Survey Studies.

    Science.gov (United States)

    McDowell, Earl E.

    This research focuses on the history of technical communication since 1850, with a specific focus on the technological changes that occurred between 1900 and 1950. This paper also discusses the development of professional technical communication organizations and the development of technical communication programs at the bachelor, masters, and…

  3. Career and Technical Education Administration: Requirements, Certification/Licensure, and Preparation

    Science.gov (United States)

    Zirkle, Christopher J.; Jeffery, Jeremy O.

    2017-01-01

    The current climate of career and technical administration requirements in all 50 states was detailed and explored. An increasing number of states are not requiring specific career-technical administration certification/licensure in order to oversee secondary career and technical education (CTE) programs, with more states moving towards a general…

  4. Technics and ethics

    International Nuclear Information System (INIS)

    Budnick, D.; Gemmel, F.

    1981-01-01

    Questions about the sense of life and the responsibility of technology are ethical questions. Young people in our neighbourhood who, compared to some time ago, see, hear and read much more of the world, deal with them increasingly. However, the permanent stream of information does not at all facilitate orientation but prevents many people from gaining some clearness about their own point of view. In asking the questions: where are we today. How can we get on. How can we start. The relation between ethics and technics is discussed under various aspects. (orig./HSCH) [de

  5. INOPS Technical Report

    DEFF Research Database (Denmark)

    Lindholst, Andrej Christian

    This research report contains background analyses and findings from the INOPS research project. The purpose of the INOPS project was, from an international perspective, to describe, analyse and recommend different forms of contracting out and public–private co-operations within the technical area...... in Denmark, Sweden, Norway and England. The research report addresses three key research questions in a comparative perspective: 1. Why are park and road maintenance services contracted out? 2. How are park and road maintenance services contracted out? 3. What are the outcomes from contracting out park...

  6. Argentina technical report

    International Nuclear Information System (INIS)

    2002-01-01

    At present, the Production Cyclotron Facility, installed at the Ezeiza Atomic Centre, is used for Tl-201 production; F-18 and I-123 production will be incorporated during this year. Concerning I-123 production, a system for irradiation of gaseous target has been developed in the frame of the IAEA Technical Assistance Project (ARG4085). The iodine production system delivers an ultra pure radioisotope via nuclear reactions: 124 Xe (p,2n) 123 Cs → 123 Xe → 123 I and 124 Xe (p,pn) 123 Xe → 123 I. This report describes the target and irradiation chamber design, the radiochemical purification process

  7. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Sobecky, Patricia A; Taillefert, Martial

    2013-03-29

    This final technical report describes results and findings from a research project to examine the role of microbial phosphohydrolase enzymes in naturally occurring subsurface microorganisms for the purpose of promoting the immobilization of the radionuclide uranium through the production of insoluble uranium phosphate minerals. The research project investigated the microbial mechanisms and the physical and chemical processes promoting uranium biomineralization and sequestration in oxygenated subsurface soils. Uranium biomineralization under aerobic conditions can provide a secondary biobarrier strategy to immobilize radionuclides should the metal precipitates formed by microbial dissimilatory mechanisms remobilize due to a change in redox state.

  8. RADTRAN 6 technical manual.

    Energy Technology Data Exchange (ETDEWEB)

    Weiner, Ruth F.; Neuhauser, Karen Sieglinde; Heames, Terence John; O' Donnell, Brandon M.; Dennis, Matthew L.

    2014-01-01

    This Technical Manual contains descriptions of the calculation models and mathematical and numerical methods used in the RADTRAN 6 computer code for transportation risk and consequence assessment. The RADTRAN 6 code combines user-supplied input data with values from an internal library of physical and radiological data to calculate the expected radiological consequences and risks associated with the transportation of radioactive material. Radiological consequences and risks are estimated with numerical models of exposure pathways, receptor populations, package behavior in accidents, and accident severity and probability.

  9. RADTRAN 6 Technical Manual

    Energy Technology Data Exchange (ETDEWEB)

    Weiner, Ruth F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Neuhauser, Karen Sieglinde [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Heames, Terence John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); O' Donnell, Brandon M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Dennis, Matthew L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-01-01

    This Technical Manual contains descriptions of the calculation models and mathematical and numerical methods used in the RADTRAN 6 computer code for transportation risk and consequence assessment. The RADTRAN 6 code combines user-supplied input data with values from an internal library of physical and radiological data to calculate the expected radiological consequences and risks associated with the transportation of radioactive material. Radiological consequences and risks are estimated with numerical models of exposure pathways, receptor populations, package behavior in accidents, and accident severity and probability.

  10. Compilation of Sandia Laboratories technical capabilities

    Energy Technology Data Exchange (ETDEWEB)

    Lundergan, C. D.; Mead, P. L. [eds.

    1975-11-01

    This report is a compilation of 17 individual documents that together summarize the technical capabilities of Sandia Laboratories. Each document in this compilation contains details about a specific area of capability. Examples of application of the capability to research and development problems are provided. An eighteenth document summarizes the content of the other seventeen. Each of these documents was issued with a separate report number (SAND 74-0073A through SAND 74-0091, except -0078). (RWR)

  11. Compilation of Sandia Laboratories technical capabilities

    International Nuclear Information System (INIS)

    Lundergan, C.D.; Mead, P.L.

    1975-11-01

    This report is a compilation of 17 individual documents that together summarize the technical capabilities of Sandia Laboratories. Each document in this compilation contains details about a specific area of capability. Examples of application of the capability to research and development problems are provided. An eighteenth document summarizes the content of the other seventeen. Each of these documents was issued with a separate report number (SAND 74-0073A through SAND 74-0091, except -0078)

  12. Modeling technical change in climate analysis: evidence from agricultural crop damages.

    Science.gov (United States)

    Ahmed, Adeel; Devadason, Evelyn S; Al-Amin, Abul Quasem

    2017-05-01

    This study accounts for the Hicks neutral technical change in a calibrated model of climate analysis, to identify the optimum level of technical change for addressing climate changes. It demonstrates the reduction to crop damages, the costs to technical change, and the net gains for the adoption of technical change for a climate-sensitive Pakistan economy. The calibrated model assesses the net gains of technical change for the overall economy and at the agriculture-specific level. The study finds that the gains of technical change are overwhelmingly higher than the costs across the agriculture subsectors. The gains and costs following technical change differ substantially for different crops. More importantly, the study finds a cost-effective optimal level of technical change that potentially reduces crop damages to a minimum possible level. The study therefore contends that the climate policy for Pakistan should consider the role of technical change in addressing climate impacts on the agriculture sector.

  13. Technical Training: Places available

    CERN Multimedia

    Monique Duval

    2005-01-01

    The number of places available may vary. Please check our Web site to find out the current availability. Places are available on the following courses: Hands-on Introduction to Python Programming: 28 - 30.6.2005 (3 days) Introduction to ANSYS: 28.6 - 1.7.2005 (4 days) IT3T/3 - Working remotely with Windows XP: 28.6.2005 (IT Technical Training Tutorial, free of charge) IT3T/4 - Editing Websites with Frontpage 2003: 30.6.2005 (IT Technical Training Tutorial, free of charge) LabVIEW base 1 : 4 - 6.7.2005 (3 jours) LabVIEW Basics 2: 7 - 8.7.2005 (2 days) Utilisation des fichiers PDF avec ACROBAT 7.0 : 5.7.2005 (1 jour) FrontPage 2003 - niveau 1 : 6-7.7.2005 (2 jours) WORD 2003 (Short Course I) - HowTo... Work with repetitive tasks /AutoText, AutoFormat, AutoCorrect, Find/Replace) : 4.7.2005 (afternoon) WORD 2003 (Short Course II) - HowTo... Mail merge: 5.7.2005 (afternoon) WORD 2003 (Short Course III) - HowTo... Work with long documents : 6.7.2005 (afternoon) ACCES...

  14. Technical Training: Places available

    CERN Multimedia

    Monique Duval

    2005-01-01

    The number of places available may vary. Please check our Web site to find out the current availability. Places are available on the following courses: Joint PVSS JCOP Framework: 8 - 12.8.2005 (5 days) FrontPage 2003 - niveau 1 : 1 - 2.9.2005 (2 jours) Utilisation des fichiers PDF avec ACROBAT 7.0 : 5.9.2005 (1 jour) LabVIEW Basics 1 : 5 - 7.9.2005 (3 days, dates to be confirmed) Introduction à Windows XP au CERN : 12.9.2005 (1 demi-journée) FrontPage 2003 - niveau 2 : 15 - 16.9.2005 (2 jours) AutoCAD 2005 - niveau 1 : 22, 23, 28, 29.9.2005 (4 jours) MAGNE-05 - Magnétisme pour l'électrotechnique : 27 - 29.9.2005 (3 jours) LabVIEW Application Development (Intermediate I): 5 - 7.12.2005 (3 days) LabVIEW Advanced Programming (Intermediate 2): 8 - 9.12.2005 (2 days) ENSEIGNEMENT TECHNIQUE TECHNICAL TRAINING Monique Duval 74924 technical.training@cern.ch

  15. Technical Training: Places available

    CERN Multimedia

    Monique Duval

    2005-01-01

    The number of places available may vary. Please check our Web site to find out the current availability. Places are available on the following courses: Hands-on Introduction to Python Programming: 28 - 30.6.2005 (3 days) Introduction to ANSYS: 21 - 24.6.2005 (4 days) IT3T/3 - Working remotely with Windows XP: 28.6.2005 (IT Technical Training Tutorial, free of charge) IT3T/4 - Editing Websites with Frontpage 2003: 30.6.2005 (IT Technical Training Tutorial, free of charge) Utilisation des fichiers PDF avec ACROBAT 7.0 : 5.7.2005 (1 jour) FrontPage 2003 - niveau 1 : 6-7.7.2005 (2 jours) LabVIEW base 1 : 4 - 6.7.2005 (3 jours) LabVIEW Basics 2: 7 - 8.7.2005 (2 days) WORD 2003 (Short Course I) - HowTo... Work with repetitive tasks /AutoText, AutoFormat, AutoCorrect, Find/Replace) : 4.7.2005 (afternoon) WORD 2003 (Short Course II) - HowTo... Mail merge: 5.7.2005 (afternoon) WORD 2003 (Short Course III) - HowTo (4 mornings) EXCEL 2003 (Short Course I) - HowTo... Work ...

  16. Technical Training: Places available

    CERN Multimedia

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: C++ for Particle Physicists : 8 - 12.3.2004 (6 X 4-hour sessions) Introduction to the CERN EDMS : 9.3.2004 (1 day, free of charge) The EDMS MTF in Practice : 10.3.2004 (morning, free of charge) CLEAN-2002 : Working in a Cleanroom : 10.3.2004 (afternoon, free of charge) The CERN EDMS for Engineers : 11.3.2004 (1 day, free of charge) LabVIEW...

  17. Technical Training: Places available

    CERN Document Server

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: Instructor-led WBTechT study or follow-up for Microsoft applications : 1.4.2004 (morning) FrontPage XP - niveau 1 : 5 & 6.4.2004 (2 jours) AutoCAD 2002 - niveau 1 : 19, 20.4 et 3, 4.5.2004 (4 jours) Oracle 8i/9i - Develop Web-based Applications with PL/SQL : 19 & 20.4.2004 (2 days) Introduction to ANSYS : 20 - 23.4.2004 (4 day...

  18. Technical Training: Places available

    CERN Document Server

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: LabVIEW base 1 : 25 - 27.2.2004(3 jours) Instructor-led WBTechT study or follow-up for Microsoft applications : 26.2.2004 (morning) CLEAN-2002 : Working in a Cleanroom : 10.3.2004 (afternoon - free of charge) C++ for Particle Physicists : 8 - 12.3.2004 (6 X 4-hour sessions) LabVIEW hands-on (E) : 16.3.2004 (afternoon) LabVIEW Basics 1 : 22 - 24.3.2004 ...

  19. TECHNICAL TRAINING: Places available**

    CERN Multimedia

    2003-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval Tel. 74924 technical.training@cern.ch ** The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: The EDMS-MTF in practice (free of charge) : 28 -  30.10.03 (6 half-day sessions) AutoCAD 2002 – Level 1 : 3, 4, 12, 13.11.03 (4 days) LabVIEW TestStand ver. 3 : 4 & 5.11.03 (2 days) Introduction to PSpice : 4.11.03 p.m. (half-day) Hands-on Introduction to Python Programming : 12 – 14.11.03 (3 days) ACCESS ...

  20. Technical Training: Places available

    CERN Document Server

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: Computational Electromagnetics with the ELEKTRA Module of OPERA-3D : 27 & 28.4.2004 (2 days) Hands-on Introduction to Python Programming : 3 - 5.5.2004 (3 days) LabVIEW Base 2 : 6 & 7.5.2004 (2 jours) Project Planning with MS-Project : 6 & 13.5.2004 (2 days) Word 2003 - niveau 1 : 10 & 11.5.2004 (2 jours) Oracle 9i : SQL : 10 - 12.5.2004 (3...

  1. Technical Training: Places available

    CERN Multimedia

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: Project Planning with MS-Project :6 & 13.5.2004 (2 days) Word 2003 - niveau 1 : 10 & 11.5.2004 (2 jours) Oracle 9i : SQL : 17 - 19.5.2004 (3 days) Word 2003 - niveau 2 : 24 & 25.5.2004 (2 jours) EXCEL 2003 - niveau 1: 27 & 28.5.2004 (2 jours) STEP7 Programming Level 1 : 1 - 4.6.2004 (4 days) Oracle 9i : Programming with PL/SQL : 2 - 4.6.2...

  2. Technical Training: Places available

    CERN Document Server

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: Instructor-led WBTechT study for Microsoft applications :12.2.2004 (morning) Instructor-led WBTechT study or follow-up for Microsoft applications : 19.2.2004 (morning) LabVIEW TestStand I (E) : 23 & 24.2.2004 (2 days) LabVIEW base 1 : 25 - 27.2.2004 (3 jours) Instructor-led WBTechT study or follow-up for Microsoft applications : 19.2.2004 (morning) CLEAN-2002 ...

  3. Technical Training: Places available

    CERN Multimedia

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: AutoCAD 2002 - niveau 1 : 19, 20.4 et 3, 4.5.2004 (4 jours) Oracle 8i/9i - Develop Web-based Applications with PL/SQL : 19 & 20.4.2004 (2 days) Introduction to ANSYS : 20 - 23.4.2004 (4 days) LabVIEW Hands-on : 20.4.2004 (half-day, p.m.) FrontPage XP - niveau 2 : 26 & 27.4.2004 (2 jours) The Joint PVSS JCOP Framework : 26 -...

  4. Technical Training: Places available**

    CERN Multimedia

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch ** The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: The JAVA Programming Language Level 1 : 9 & 10.1.2004 (2 days) LabVIEW TestStand I (E) : 23 & 24.2.2004 (2 days) LabVIEW base 1 : 25 - 27.2.2004 (3 jours) CLEAN-2002 : Working in a Cleanroom : 10.3.2004 (afternoon - free of charge) C++ for Particle Physicists : 8 - 12.3.2004 ( 6 X 4-hour sessions) LabVIEW hands-on (E) 16.3...

  5. Technical Training: Places available

    CERN Document Server

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: Instructor-led WBTechT study or follow-up for Microsoft applications : 19.2.2004 (morning) LabVIEW TestStand I (E) : 23 & 24.2.2004 (2 days) LabVIEW base 1 : 25 - 27.2.2004 (3 jours) Instructor-led WBTechT study or follow-up for Microsoft applications : 26.2.2004 (morning) CLEAN-2002 : Working in a Cleanroom : 10.3.2004 (afternoon - free of charge) C++ for Pa...

  6. Technical Training: Places available

    CERN Document Server

    Monique Duval

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an 'application for training' form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. Technical Training Monique Duval - Tel.74924 technical.training@cern.ch The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: Word 2003 - niveau 2 : 24 & 25.5.2004 (2 jours) VisualEliteHDL : 25 & 26.5.2004 (2 days) EXCEL 2003 - niveau 1 : 27 & 28.5.2004 (2 jours) STEP7 Programming Level 1: 1 - 4.6.2004 (4 days) Oracle 9i : Programming with PL/SQL: 2 - 4.6.2004 (3 days) CST Microwave Studio: 3 & 4.6.2004 (2 days) Oracle 9...

  7. Technical Training: Places Available

    CERN Document Server

    Monique Duval

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an 'application for training' form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. Technical Training Monique Duval - Tel.74924 technical.training@cern.ch The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: Oracle 9i: SQL: 17 - 19.5.2004 (3 days) Word 2003 - niveau 2 : 24 & 25.5.2004 (2 jours) EXCEL 2003 - niveau 1 : 27 & 28.5.2004 (2 jours) STEP7 Programming Level 1: 1 - 4.6.2004 (4 days) Oracle 9i : Programming with PL/SQL: 2 - 4.6.2004 (3 days) CST Microwave Studio: 3 & 4.6.2004 (2 days) Oracle 9i : New f...

  8. Technical Training: Places available

    CERN Multimedia

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: FrontPage XP - niveau 2 : 26 & 27.4.2004 (2 jours) The Joint PVSS JCOP Framework : 26 - 30.4.2004 (5 days) Computational Electromagnetics with the ELEKTRA Module of OPERA-3D : 27 & 28.4.2004 (2 days) Hands-on Introduction to Python Programming : 3 - 5.5.2004 (3 days) LabVIEW Base 2 : 6 & 7.5.2004 (2 jours) Project Pla...

  9. TECHNICAL TRAINING: Places available**

    CERN Document Server

    2003-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch ** The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: Hands-on Introduction to Python Programming : 12 - 14.11.03(3 days) ACCESS 2000 - niveau 1 : 13 & 14.11.03 (2 jours) C++ for Particle Physicists : 17 - 21.11.03 (6 X 3-hour lectures) Programmation automate Schneider TSX Premium - niveau 2 : 18 - 21.11.03 (4 jours) Project Planning with MS-Project  (free of charg...

  10. Technical Training: Places available

    CERN Multimedia

    Monique Duval

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: C++ for Particle Physicists : 8 - 12.3.2004 (6 X 4-hour sessions) Introduction to the CERN EDMS : 9.3.2004 (1 day, free of charge) The EDMS MTF in Practice : 10.3.2004 (morning, free of charge) CLEAN-2002: Working in a Cleanroom : 10.3.2004 (afternoon, free of charge) The CERN EDMS for Engineers : 11.3.2004 (1 day, free of charge) LabVIEW hands-on (E):...

  11. Technical training: places available

    CERN Multimedia

    HR Department

    2007-01-01

    CERN Technical Training: Open Courses (April - June 2007) The following course sessions are currently scheduled in the framework of the CERN Technical Training Programme 2007:   AutoCAD 2006 - niveau 1 (course in French): 25.4.- 26.4.2007 & 2.5. - 3.5.2007 (4 days in 2 modules, 5 places available) AutoCAD 2006 - niveau 1 (course in French): 27.6.- 28.6.2007 & 3.7. - 4.7.2007 (4 days in 2 modules, 5 places available) AutoCAD Mechanical 2006 (course in French) 21.6.-22.6.2007 (2 days, 8 places available) * NEW COURSE* Automate de securite S7 (course in French) 14.5.-16.5.2007 (3 days, 4 places available) * NEW COURSE* Automate de securite S7 (course in French): 9.5.-11.5.2007 (3 days, 4 places available) JCOP - Joint PVSS-JCOP Frameswork (course in English): 21.5.-25.5.2007 (5 days, 12 places available) JCOP - Finite State Machines in the JCOP Frameswork (course in English): 12.6.-14.6.2007 (3 days, 12 places available) LabVIEW Basics 1 (in English): 2.-4.5.2007 (3 days, 7 places ...

  12. CEEM Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Bowers, John [Univ. of California, Santa Barbara, CA (United States)

    2014-11-26

    The mission of the Center for Energy Efficient Materials (CEEM) was to serve the Department of Energy and the nation as a center of excellence dedicated to advancing basic research in nano-structured materials and devices for applications to solar electricity, thermoelectric conversion of waste heat to electricity, and solidstate lighting. The foundation of CEEM was based on the unique capabilities of UCSB and its partner institutions to control, synthesize, characterize, model, and apply materials at the nanoscale for more efficient sustainable energy resources. This unique expertise was a key source of the synergy that unified the research of the Center. Although the Center’s focus was basic research, It’s longer-term objective has been to transfer new materials and devices into the commercial sector where they will have a substantial impact on the nation’s need for efficient sustainable energy resources. As one measure of the impact of the Center, two start-up companies were formed based on its research. In addition, Center participants published a total of 210 archival journal articles, of which 51 were exclusively sponsored by the DOE grant. The work of the Center was structured around four specific tasks: Organic Solar Cells, Solid-State Lighting, Thermoelectrics, and High Efficiency Multi-junction Photovoltaic devices. A brief summary of each follows – detailed descriptions are in Sections 4 & 5 of this report. Research supported through CEEM led to an important shift with respect to the choice of materials used for the fabrication of solution deposited organic solar cells. Solution deposition opens the opportunity to manufacture solar cells via economically-viable high throughput tools, such as roll to roll printing. Prior to CEEM, most organic semiconductors utilized for this purpose involved polymeric materials, which, although they can form thin films reliably, suffer from batch to batch variations due to the statistical nature of the chemical

  13. Technical standards in the law of technical safety

    International Nuclear Information System (INIS)

    Marburger, P.

    1985-01-01

    Technical standards are of great importance for the closer definition of inexact terms of law, for instance ''generally accepted technical rules'', ''state of the art'', ''state of science and technology'' or similar normative terms, in the law of technical safety. The paper discusses with whom the authority for regulating this sector of law rests, deals with the different ways of how technical standards are used by the law (''anticipated expert opinion'', reference to such standards in law and administration) and points out demands on the procedure of standardization. (orig.) [de

  14. Technical Support Essentials Advice to Succeed in Technical Support

    CERN Document Server

    Sanchez, Andrew

    2010-01-01

    Technical Support Essentials is a book about the many facets of technical support. It attempts to provide a wide array of topics to serve as points of improvement, discussion, or simply topics that you might want to learn. The topics range from good work habits to the way technical supportgroups establish their own style of work. This book applies theories, models, and concepts synthesized from existing research in other fields-such as management, economics, leadership, and psychology-and connects them to technical support. The goal is to build on the work of others and allow their success to

  15. The role of non-technical skills in surgery.

    Science.gov (United States)

    Agha, Riaz A; Fowler, Alexander J; Sevdalis, Nick

    2015-12-01

    Non-technical skills are of increasing importance in surgery and surgical training. A traditional focus on technical skills acquisition and competence is no longer enough for the delivery of a modern, safe surgical practice. This review discusses the importance of non-technical skills and the values that underpin successful modern surgical practice. This narrative review used a number of sources including written and online, there was no specific search strategy of defined databases. Modern surgical practice requires; technical and non-technical skills, evidence-based practice, an emphasis on lifelong learning, monitoring of outcomes and a supportive institutional and health service framework. Finally these requirements need to be combined with a number of personal and professional values including integrity, professionalism and compassionate, patient-centred care.

  16. Endogenous induced technical change and the costs of Kyoto

    International Nuclear Information System (INIS)

    Buonanno, Paolo; Carraro, Carlo; Galeotti, Marzio

    2003-01-01

    We present a model for climate change policy analysis which accounts for the possibility that technology evolves endogenously and that technical change can be induced by environmental policy measures. Both the output production technology and the emission-output ratio depend upon a stock of knowledge, which accumulates through R and D activities. Two versions of this model are studied, one with endogenous technical change but exogenous environmental technical change and the other with both endogenous and induced technical change. A third version also captures technological spillover effects. As an application, the model is simulated allowing for trade of pollution permits as specified in the Kyoto Protocol and assessing the implications in terms of cost efficiency, economic growth and R and D efforts of the three different specifications of technical change

  17. Current technical issues in international safeguards

    International Nuclear Information System (INIS)

    Bennett, C.A.

    1977-01-01

    Safeguards systems, and the associated need for technical and systems development, reflect changing conditions and concerns associated with the nuclear fuel cycle and the safety and security of nuclear materials and facilities. In particular, the implementation of international safeguards has led to the recognition of certain technical issues, both old and new, which are in need of resolution. These are: 1. The grading of nuclear materials and facilities with respect to their relative safeguards significance. 2. The extension and upgrading of safeguards techniques to maintain adequate protection in view of constantly increasing amounts of material to be safeguarded. 3. The balance between safeguards mechanisms based on physical protection and material accounting, and the role of surveillance and containment in each case. 4. The role of information systems as a basis for both analytical feedback and the determination of the factors affecting system effectiveness and their interrelationship. 5. A determination of the degree to which the overall technical effectiveness of international inspection activities can be quantified. Each of these technical issues must be considered in light of the specific objectives of international safeguards, which differ from domestic safeguards in terms of the level of the threat, the safeguards mechanisms available, and the diversion strategies assumed. Their resolution in this international context is essential if the effectiveness and viability of international safeguards are to be maintained

  18. History of research reactor fuel fabrication at Babcock and Wilcox

    International Nuclear Information System (INIS)

    Freim, James B.

    1983-01-01

    B and W Research Reactor Fuel Element facility at Lynchburg, Virginia now produces national laboratory and university fuel assemblies. The Company's 201000 square foot facility is devoted entirely to supplying research fuel and related products. B and W re-entered the research reactor fuel market in 1981

  19. Augusta Y. olaore & chidinma Aham-chiabotu Babcock University ...

    African Journals Online (AJOL)

    FUST) as viable guidelines for a collaborative work with families of university students involved ... social harm. The problem of drug use among youths in Nigeria has a unique slant because Nige- rian Universities admit students who are still.

  20. The profile of tuberculosis infection at the Babcock University ...

    African Journals Online (AJOL)

    Background: Tuberculosis is the leading cause of death from any single pathogen and it has consistently continued to be a major public health challenge globally. Data show that Nigeria ranks tenth among the 22 high tuberculosis burden countries. Aim: This study intends to describe the profile of tuberculosis infections in ...

  1. The profile of tuberculosis infection at the Babcock University ...

    African Journals Online (AJOL)

    2016-01-23

    Poor. Countries: Challenges and Opportunities. Clinical Microbiology Reviews 2011;24:314-350. 12. Ansari NA, Kombe AH, Kenyon. TA.Pathology and causes of death in a group of. 128 predominantly HIV-positive patients in.

  2. Tendering specification and contracting

    International Nuclear Information System (INIS)

    Koch, E. von

    1975-01-01

    The lecture tendering, specification and contracting is prepared in two parts: This first part deals with technical aspects while part two features the commercial and legal situation in the partnership of two: the supplier of the fuel bundles and the utility. In this lecture a look is given on the way how a supplier can offer its fuel and some certain points are mentioned which are important to compare the bid of one competitor to the other. The major points are summarized which are or at least should be in an offer so as to find out which offer is the best. (orig./FW) [de

  3. Technical knowledge creation

    DEFF Research Database (Denmark)

    Søberg, Peder Veng

    2017-01-01

    Purpose - The purpose of the paper is to amend shortcomings of existing theory concerning organizational learning and knowledge management. Design/methodology/approach – The paper reviews and refines existing theory. Findings - Findings from cognitive neuroscience suggest that technical knowledge...... domains essential for product development are largely nonlinguistic. Operations management/strategy tools enable the use of tacit knowledge in its tacit form and discourage premature standardization. Similarly, language use introduces standardization, which if introduced prematurely, causes incrementalism...... in line with findings from product development research. However, frameworks on organizational learning and knowledge management focus on language development and neglect use of tacit knowledge and the benefits involved with allowing elements of new product ideas to mature in a tacit form. Originality...

  4. Technical Training Seminar

    CERN Multimedia

    2003-01-01

    Wednesday 19 November From 9:30 to 17:30 - IT Amphitheatre bldg.31 3-004 2003 Data Transmission Design Seminar - TEXAS INSTRUMENTS The one-day 2003 Data Transmission Design Seminar is part of a series of technical seminars produced by Texas Instruments. This series of seminars will introduce system solutions based on different standards according to their respective requirements. It will include topics containing a blend of basic principles and hands-on application examples, along with layout-guidelines. • Basics and Practical Examples of Data-Transmission • Low Voltage Differential Signaling (LVDS) • Connectivity and PC-based Links • Industrial Interfaces • Parallel Bus Systems and Clock-Distribution-Circuits (CDC) This Seminar will be of interest to hardware designers and system engineers dealing with the realization of system- or board-level interfaces based on various transmission standards. Language: English Free seminar, no registration Organiser: John ...

  5. Technical Math For Dummies

    CERN Document Server

    Schoenborn, Barry

    2010-01-01

    Technical Math For Dummies is your one-stop, hands-on guide to acing the math courses you’ll encounter as you work toward getting your degree, certifacation, or�license in the skilled trades. You’ll get easy-to-follow, plain-English guidance on mathematical formulas and methods that professionals use every day in the automotive, health, construction, licensed trades, maintenance, and other trades. You’ll learn how to apply concepts of algebra, geometry, and trigonometry and their formulas related to occupational areas of study. Plus, you’ll find out how to perform basic arithmetic

  6. Technical applications of aerogels

    International Nuclear Information System (INIS)

    Hrubesh, L.W.

    1997-01-01

    Aerogel materials posses such a wide variety of exceptional properties that a striking number of applications have developed for them. Many of the commercial applications of aerogels such as catalysts, thermal insulation, windows, and particle detectors are still under development and new application as have been publicized since the ISA4 Conference in 1994: e.g.; supercapacitors, insulation for heat storage in automobiles, electrodes for capacitive deionization, etc. More applications are evolving as the scientific and engineering community becomes familiar with the unusual and exceptional physical properties of aerogels, there are also scientific and technical application, as well. This paper discusses a variety of applications under development at Lawrence Livermore National Laboratory for which several types of aerogels are formed in custom sizes and shapes. Particular discussions will focus on the uses of aerogels for physics experiments which rely on the exceptional, sometimes unique, properties of aerogels

  7. Technical Training: ELEC-2005

    CERN Multimedia

    Davide Vitè

    2005-01-01

    ELEC-2005 - Electronics in High Energy Physics: Autumn Term (November-December 2005) ELEC-2005 is a new course series on modern electronics, given by CERN physicists and engineers within the framework of the 2005 Technical Training Programme, in an extended format of the ELEC-2002 course series. This new, comprehensive course series is designed for people who are not electronics specialists, for example physicists, engineers and technicians working at or visiting the laboratory, who use or will use electronics in their present or future activities, in particular in the context of the LHC accelerator and experiments. ELEC-2005 is composed of four Terms. The Winter (Introduction to electronics in HEP), Spring (Integrated circuits and VLSI technology for physics), and Summer (System electronics for physics: Issues) Terms already took place. The Autumn Term: Electronics applications in HEP experiments (November-December, 10 lectures) is now open for online registration, and will start on November 8th with the...

  8. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Eggeman, Tim [ZeaChem Inc., Lakewood, CO (United States); O' Neill, Brian [ZeaChem Inc., Lakewood, CO (United States)

    2016-08-17

    ZeaChem Inc. and US DOE successfully demonstrated the ZeaChem process for producing sugars and ethanol from high-impact biomass feedstocks. The project was executed over a 5-year period under a $31.25 million cooperative agreement (80:20 Federal:ZeaChem cost share). The project was managed by dividing it into three budget periods. Activities during Budget Period 1 were limited to planning, permitting, and other pre-construction planning. Budget Period 2 activities included engineering, procurement, construction, commissioning, start-up and initial operations through the Independent Engineer Test Runs. The scope of construction was limited to the Chem Frac and Hydrogenolysis units, as the Core Facility was already in place. Construction was complete in December 2012, and the first cellulosic ethanol was produced in February 2013. Additional operational test runs were conducted during Budget Period 3 (completed June 2015) using hybrid poplar, corn stover, and wheat straw feedstocks, resulting in the production of cellulosic ethanol and various other biorefinery intermediates. The research adds to the understanding of the Chem Frac and Hydrogenolysis technologies in that the technical performance of each unit was measured, and the resulting data and operational experience can be used as the basis for engineering designs, thus mitigating risks for deployment in future commercial facilities. The Chem Frac unit was initially designed to be operated as two-stage dilute acid hydrolysis, with first stage conditions selected to remove the hemicellulose fraction of the feedstock, and the second stage conditions selected to remove the cellulose fraction. While the Chem Frac unit met or exceeded the design capacity of 10 ton(dry)/day, the technical effectiveness of the Chem Frac unit was below expectations in its initial two-stage dilute acid configuration. The sugars yields were low, the sugars were dilute, and the sugars had poor fermentability caused by excessive inhibitors

  9. Technical Report - FINAL

    Energy Technology Data Exchange (ETDEWEB)

    Barbara Luke, Director, UNLV Engineering Geophysics Laboratory

    2007-04-25

    Improve understanding of the earthquake hazard in the Las Vegas Valley and to assess the state of preparedness of the area's population and structures for the next big earthquake. 1. Enhance the seismic monitoring network in the Las Vegas Valley 2. Improve understanding of deep basin structure through active-source seismic refraction and reflection testing 3. Improve understanding of dynamic response of shallow sediments through seismic testing and correlations with lithology 4. Develop credible earthquake scenarios by laboratory and field studies, literature review and analyses 5. Refine ground motion expectations around the Las Vegas Valley through simulations 6. Assess current building standards in light of improved understanding of hazards 7. Perform risk assessment for structures and infrastructures, with emphasis on lifelines and critical structures 8. Encourage and facilitate broad and open technical interchange regarding earthquake safety in southern Nevada and efforts to inform citizens of earthquake hazards and mitigation opportunities

  10. Technical applications of aerogels

    Energy Technology Data Exchange (ETDEWEB)

    Hrubesh, L.W.

    1997-08-18

    Aerogel materials posses such a wide variety of exceptional properties that a striking number of applications have developed for them. Many of the commercial applications of aerogels such as catalysts, thermal insulation, windows, and particle detectors are still under development and new application as have been publicized since the ISA4 Conference in 1994: e.g.; supercapacitors, insulation for heat storage in automobiles, electrodes for capacitive deionization, etc. More applications are evolving as the scientific and engineering community becomes familiar with the unusual and exceptional physical properties of aerogels, there are also scientific and technical application, as well. This paper discusses a variety of applications under development at Lawrence Livermore National Laboratory for which several types of aerogels are formed in custom sizes and shapes. Particular discussions will focus on the uses of aerogels for physics experiments which rely on the exceptional, sometimes unique, properties of aerogels.

  11. LLNL 1981: technical horizons

    International Nuclear Information System (INIS)

    1981-07-01

    Research programs at LLNL for 1981 are described in broad terms. In his annual State of the Laboratory address, Director Roger Batzel projected a $481 million operating budget for fiscal year 1982, up nearly 13% from last year. In projects for the Department of Energy and the Department of Defense, the Laboratory applies its technical facilities and capabilities to nuclear weapons design and development and other areas of defense research that include inertial confinement fusion, nonnuclear ordnances, and particle-beam technology. LLNL is also applying its unique experience and capabilities to a variety of projects that will help the nation meet its energy needs in an environmentally acceptable manner. A sampling of recent achievements by LLNL support organizations indicates their diversity

  12. Mechanical engineering department technical review

    International Nuclear Information System (INIS)

    Carr, R.B.; Denney, R.M.

    1981-01-01

    The Mechanical Engineering Department Technical Review is published to: (1) inform the readers of various technical activities within the department, (2) promote exchange of ideas, and (3) give credit to the personnel who are achieving the results. The report is formatted into two parts: technical acievements and publication abstracts. The first is divided into eight sections, one for each division in the department providing the reader with the names of the personnel and the division accomplishing the work

  13. Mechanical Engineering Department. Technical review

    Energy Technology Data Exchange (ETDEWEB)

    Simecka, W.B.; Condouris, R.A.; Talaber, C. (eds.)

    1980-01-01

    The Mechanical Engineering Department Technical Review is published to (1) inform the readers of various technical activities within the Department, (2) promote exchange of ideas, and (3) give credit to the personnel who are achieving the results. The report is formatted into two parts: technical achievements and publication abstracts. The first is divided into eight sections, one for each Division in the Department providing the reader with the names of the personnel and the Division accomplishing the work.

  14. TECHNICAL CULTURE AND HUMAN AXJOSPHERE

    OpenAIRE

    ­Krystyna Chałas

    2014-01-01

    Technical culture is the value of each historical period. It is the subject of the ongoing development. While it is a value which is associated with different categories of values, mainly material, cognitive, social. Between culture and these three categories of values ​ there is a cognitive effect. Technical culture determines the quality of human axjosphere. The aim of this study is to show the relationships and dependencies between technical culture and the structures in which a person liv...

  15. Mechanical engineering department technical review

    Energy Technology Data Exchange (ETDEWEB)

    Carr, R.B. Denney, R.M. (eds.)

    1981-01-01

    The Mechanical Engineering Department Technical Review is published to: (1) inform the readers of various technical activities within the department, (2) promote exchange of ideas, and (3) give credit to the personnel who are achieving the results. The report is formatted into two parts: technical acievements and publication abstracts. The first is divided into eight sections, one for each division in the department providing the reader with the names of the personnel and the division accomplishing the work.

  16. Mechanical Engineering Department technical abstracts

    International Nuclear Information System (INIS)

    Denney, R.M.

    1982-01-01

    The Mechanical Engineering Department publishes listings of technical abstracts twice a year to inform readers of the broad range of technical activities in the Department, and to promote an exchange of ideas. Details of the work covered by an abstract may be obtained by contacting the author(s). Overall information about current activities of each of the Department's seven divisions precedes the technical abstracts

  17. Mechanical Engineering Department. Technical review

    International Nuclear Information System (INIS)

    Simecka, W.B.; Condouris, R.A.; Talaber, C.

    1980-01-01

    The Mechanical Engineering Department Technical Review is published to (1) inform the readers of various technical activities within the Department, (2) promote exchange of ideas, and (3) give credit to the personnel who are achieving the results. The report is formatted into two parts: technical achievements and publication abstracts. The first is divided into eight sections, one for each Division in the Department providing the reader with the names of the personnel and the Division accomplishing the work

  18. Mechanical Engineering Department technical abstracts

    Energy Technology Data Exchange (ETDEWEB)

    Denney, R.M. (ed.)

    1982-07-01

    The Mechanical Engineering Department publishes listings of technical abstracts twice a year to inform readers of the broad range of technical activities in the Department, and to promote an exchange of ideas. Details of the work covered by an abstract may be obtained by contacting the author(s). Overall information about current activities of each of the Department's seven divisions precedes the technical abstracts.

  19. The story of technical cooperation

    International Nuclear Information System (INIS)

    Park, Yang Taek

    1989-09-01

    This book gives descriptions of technical cooperation, which is about why does technology transfer?, process of technology transfer with model, decisive cause and cooperation of technology transfer, cost and effect of technology transfer, historical experience of technology transfer, cases of technology transfer by field such as rubber tire, medicine and computer industry and automobile industry, technology transfer process and present condition of technical cooperation, and strategy for rising of technical cooperation : selection of technology for object of cooperation and development of human resources.

  20. Technical resource documents and technical handbooks for hazardous-wastes management

    Energy Technology Data Exchange (ETDEWEB)

    Schomaker, N.B.; Bliss, T.M.

    1986-07-01

    The Environmental Protection Agency is preparing a series of Technical Resource Documents (TRD's) and Technical Handbooks to provide best engineering control technology to meet the needs of the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA) respectively. These documents and handbooks are basically compilation of research efforts of the Land Pollution Control Division (LPCD) to date. The specific areas of research being conducted under the RCRA land disposal program relate to laboratory, pilot and field validation studies in cover systems, waste leaching and solidification, liner systems and disposal facility evaluation. The technical handbooks provide the EPA Program Offices and Regions, as well as the states and other interested parties, with the latest information relevant to remedial actions.

  1. The logic of Technical Standardisation

    DEFF Research Database (Denmark)

    Nedergaard, Peter

    In this paper technical standardisation is understood and explained in a model where economic analysis is coupled with an analysis of the political system as proposed in rational choice theory. The aim is to answer both the question why various countries (e.g. the United States versus European...... countries) let either the market or public intervention determine the mode of technical standardisation and the possible implications of these two ways of organizing technical standardisation from an economic and a political point of view. Based upon the analysis of the paper a couple of general policy...... recommendations are made concerning the mode of technical standardisation....

  2. Predictors of employer satisfaction: technical and non-technical skills.

    Science.gov (United States)

    Danielson, Jared A; Wu, Tsui-Feng; Fales-Williams, Amanda J; Kirk, Ryan A; Preast, Vanessa A

    2012-01-01

    Employers of 2007-2009 graduates from Iowa State University College of Veterinary Medicine were asked to respond to a survey regarding their overall satisfaction with their new employees as well as their new employees' preparation in several technical and non-technical skill areas. Seventy-five responses contained complete data and were used in the analysis. Four technical skill areas (data collection, data interpretation, planning, and taking action) and five non-technical skill areas (interpersonal skills, ability to deal with legal issues, business skills, making referrals, and problem solving) were identified. All of the skill area subscales listed above had appropriate reliability (Cronbach's alpha>0.70) and were positively and significantly correlated with overall employer satisfaction. Results of two simultaneous regression analyses indicated that of the four technical skill areas, taking action is the most salient predictor of employer satisfaction. Of the five non-technical skill areas, interpersonal skills, business skills, making referrals, and problem solving were the most important skills in predicting employer satisfaction. Hierarchical regression analysis revealed that all technical skills explained 25% of the variation in employer satisfaction; non-technical skills explained an additional 42% of the variation in employer satisfaction.

  3. Non-technical skills in histopathology: definition and discussion.

    Science.gov (United States)

    Johnston, Peter W; Fioratou, Evie; Flin, Rhona

    2011-09-01

    Health care is a high-risk industry, with most documented adverse incidents being associated with 'human factors' including cognitive and social skills termed 'non-technical skills'. Non-technical skills complement the diagnostic and specialist skills and professional attributes required by medical practitioners, including histopathologists, and can enhance the quality of practice and delivery of health-care services and thus contribute to patient safety. This review aims to introduce histopathologists to non-technical skills and how these pertain to everyday histopathological practice. Drawing from other domains in medicine, specifically anaesthesia and surgery, a variety of non-technical skills are identified and described in the context of histopathology to illustrate the role each plays, often collectively, in daily practice. The generic non-technical skills are defined as situation awareness, decision-making, communication, teamwork, leadership, managing stress and coping with fatigue. Example scenarios from histopathology are presented and the contributions to outcomes made by non-technical skills are explained. Consideration of these specific non-technical skills as a component in histopathology training may benefit practitioners as well as assuring patient safety. © 2011 Blackwell Publishing Limited.

  4. Managing non-technical factors in healthcare IT projects.

    Science.gov (United States)

    Rosenthal, David A

    2002-01-01

    The implementation of IT within any healthcare organization is a demanding and intense exercise in the management of both technical (systemic) and non-technical (social) influences and factors, and the project process is often fraught with unforeseen obstacles or impediments to success. Project success depends as much on a specific understanding of the non-technical project impediments such as conflicting personalities and corporate culture as it does on the performance of the applied technology or the viability of the implementation process itself.

  5. The role of non-technical skills in surgery

    Directory of Open Access Journals (Sweden)

    Riaz A. Agha

    2015-12-01

    This narrative review used a number of sources including written and online, there was no specific search strategy of defined databases. Modern surgical practice requires; technical and non-technical skills, evidence-based practice, an emphasis on lifelong learning, monitoring of outcomes and a supportive institutional and health service framework. Finally these requirements need to be combined with a number of personal and professional values including integrity, professionalism and compassionate, patient-centred care.

  6. Technical and Technological Skills Assessment in Laparoscopic Surgery

    OpenAIRE

    Sarker, Sudip K.; Chang, Avril; Vincent, Charles

    2006-01-01

    Objectives: Surgical appraisal and revalidation are key components of good surgical practice and training. Assessing technical skills in a structured manner is still not widely used. Laparoscopic surgery also requires the surgeon to be competent in technological aspects of the operation. Methods: Checklists for generic, specific technical, and technological skills for laparoscopic cholecystectomies were constructed. Two surgeons with >12 years postgraduate surgical experience assessed each op...

  7. Recommendations for the Technical Infrastructure for Standardized International Rights Statements

    OpenAIRE

    Charles, Valentine; Cowles, Esmé; Estlund, Karen; Isaac, Antoine; Johnson, Tom; Matienzo, Mark A.; Peiffer, Patrick; Urban, Richard J.; Zeinstra, Maarten

    2015-01-01

    This white paper is the product of a joint Digital Public Library of America (DPLA)-Europeana working group organized to develop minimum rights statement metadata standards for organizations that contribute to DPLA and Europeana. This white paper deals specifically with the technical infrastructure of a common namespace (rightsstatements.org) that hosts the rights statements to be used by (at minimum) the DPLA and Europeana. These recommendations for a common technical infrastructure for righ...

  8. Dependability of technical items: Problems of standardization

    Science.gov (United States)

    Fedotova, G. A.; Voropai, N. I.; Kovalev, G. F.

    2016-12-01

    This paper is concerned with problems blown up in the development of a new version of the Interstate Standard GOST 27.002 "Industrial product dependability. Terms and definitions". This Standard covers a wide range of technical items and is used in numerous regulations, specifications, standard and technical documentation. A currently available State Standard GOST 27.002-89 was introduced in 1990. Its development involved a participation of scientists and experts from different technical areas, its draft was debated in different audiences and constantly refined, so it was a high quality document. However, after 25 years of its application it's become necessary to develop a new version of the Standard that would reflect the current understanding of industrial dependability, accounting for the changes taking place in Russia in the production, management and development of various technical systems and facilities. The development of a new version of the Standard makes it possible to generalize on a terminological level the knowledge and experience in the area of reliability of technical items, accumulated over a quarter of the century in different industries and reliability research schools, to account for domestic and foreign experience of standardization. Working on the new version of the Standard, we have faced a number of issues and problems on harmonization with the International Standard IEC 60500-192, caused first of all by different approaches to the use of terms and differences in the mentalities of experts from different countries. The paper focuses on the problems related to the chapter "Maintenance, restoration and repair", which caused difficulties for the developers to harmonize term definitions both with experts and the International Standard, which is mainly related to differences between the Russian concept and practice of maintenance and repair and foreign ones.

  9. Specific phobia.

    Science.gov (United States)

    Silverman, Wendy K; Moreno, Jacqueline

    2005-10-01

    This article describes specific phobia of childhood and its clinical presentation, discusses issues related to the differential diagnosis of specific phobia, considers the issue of comorbidity among phobic and anxiety disorders and developmental trends in the manifestation of fears, summarizes the epidemiology, causes, and course of specific phobia, and presents assessment and treatment issues. Finally, a case study is offered that serves to illuminate the major topics outlined in the article.

  10. Final Scientific/Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Yale [Johns Hopkins University, Laurel, MD (United States). Applied Physics Laboratory; Thomas, Michael E. [Johns Hopkins University, Laurel, MD (United States). Applied Physics Laboratory; Siegrist, Karen M. [Johns Hopkins University, Laurel, MD (United States). Applied Physics Laboratory; Lennon, Andrew M. [Johns Hopkins University, Laurel, MD (United States). Applied Physics Laboratory; Hunter, Lawrence W. [Johns Hopkins University, Laurel, MD (United States). Applied Physics Laboratory; Oguz, Hasan O. [Johns Hopkins University, Laurel, MD (United States). Applied Physics Laboratory

    2014-06-30

    JHU/APL conducted solid propellant fire characterization tests in warm, humid, ambient conditions near sea level. Yttria and ceria surrogate materials were placed in the fires. The substrates simulating ground surfaces were concrete from a Kennedy Space Center launch pad, and steel covered with a protective ablative material representing a launch platform. In-situ instrumentation consisted of witness materials, thermocouples, air handlers, filters, and cascade impactors; remote instrumentation consisted of optical cameras and spectrometers. Test and analysis team members included the Naval Air Warfare Center Aircraft Division, Sandia National Laboratories (SNL), Alliant Techsystems, and the Johns Hopkins University. Test data were analyzed, reported, and delivered, including plume rise and transport captured on video. Derivation of the alumina particle size distributions formed the basis for condensing vapor and agglomeration estimates. Assessment of alumina mass in the plume, along with the surrogate fraction from filter forensics, provided an estimate of airborne surrogate mass. Technical interchange meetings were held with SNL and the Jet Propulsion Laboratory. Specifications for the fire environment were developed and delivered. A thermochemistry model that simultaneously provides the maximum temperature and heat flux was developed and delivered. An SPIE paper on 3D pyrometry of the fire was written and presented.

  11. 1993 DOE technical standards managers workshop: Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    This workshop is focused on the benefits of the DOE technical standards program, which is focused toward the preferred use of non-Government standards for DOE activities and the development of DOE technical standards when non-Government standards are not available or are inappropriate. One goal of the program is to replace redundant site-specific standards with more universally accepted documents that have been scrutinized by experts. This replacement is discussed at the workshop along with the problems encountered and solutions found. The workshop provided an opportunity for geographically dispersed people to meet and advance their standards knowledge and efforts to support the program. Safety issues have been the driving force behind the program to date. Several companies offer products and services that support the development, processing, and retrieval of standards. This document mostly comprise vugraphs.

  12. Technical diagnosis of cuban school swimmers backstroke

    Directory of Open Access Journals (Sweden)

    Hery Leyva González Leyva González

    2017-07-01

    Full Text Available The teaching-learning process of swimming, in the conditions of Cuba, comprises several stages; the first initiation, with a duration of three to four years. Once the ten years have passed, the perfection stage begins, and finally, to the high performance of sports in adolescence. Although their improvement process favors the formation of specific motor skills in the Back stroke technique of junior swimmers, they do not show similarity in their underwater strokes with the theoretical model of technical efficiency. The following work intends from a field study and, using the empirical observation, to diagnose the mechanics of swimming of the movement of arms of the school back stroke swimmers in order to point out the technical patterns used and to identify, the main potentialities and errors of these.

  13. NASA Hydrogen Peroxide Propellant Hazards Technical Manual

    Science.gov (United States)

    Baker, David L.; Greene, Ben; Frazier, Wayne

    2005-01-01

    The Fire, Explosion, Compatibility and Safety Hazards of Hydrogen Peroxide NASA technical manual was developed at the NASA Johnson Space Center White Sands Test Facility. NASA Technical Memorandum TM-2004-213151 covers topics concerning high concentration hydrogen peroxide including fire and explosion hazards, material and fluid reactivity, materials selection information, personnel and environmental hazards, physical and chemical properties, analytical spectroscopy, specifications, analytical methods, and material compatibility data. A summary of hydrogen peroxide-related accidents, incidents, dose calls, mishaps and lessons learned is included. The manual draws from art extensive literature base and includes recent applicable regulatory compliance documentation. The manual may be obtained by United States government agencies from NASA Johnson Space Center and used as a reference source for hazards and safe handling of hydrogen peroxide.

  14. The logic of Technical Standardisation

    DEFF Research Database (Denmark)

    Nedergaard, Peter

    countries) let either the market or public intervention determine the mode of technical standardisation and the possible implications of these two ways of organizing technical standardisation from an economic and a political point of view. Based upon the analysis of the paper a couple of general policy...

  15. Technical Education and Economic Growth

    Indian Academy of Sciences (India)

    Technical Education and Economic Growth. Technical Education and Economic Growth. Review of the Present Status. Expanding no.s and impairment of quality; Faculty shortage; Grim situation ... Absence of International flavour. Consequences of Low Research. Some Success Stories. New Models of Institutional Structure ...

  16. The Digital technical documentation handbook

    CERN Document Server

    Schultz, Susan I; Kavanagh, Frank X; Morse, Marjorie J

    1993-01-01

    The Digital Technical Documentation Handbook describes the process of developing and producing technical user information at Digital Equipment Corporation. * Discusses techniques for making user information _more effective * Covers the draft and reviewprocess, the production and distribution of printed and electronic media, archiving, indexing, testing for usability, and many other topics * Provides quality assurance checklists, contains a glossary and a bibliography of resources for technicalcommunicators

  17. Aligning Career and Technical Education

    Science.gov (United States)

    Workman, Ed; Stubbs, Joyce

    2011-01-01

    The issues and concerns facing Kentucky Career and Technical Teacher Education (KY CTTE), university teacher educators and state department Career and Technical Education (CTE) leaders in providing and preparing the best CTE teachers possible are not unique to Kentucky. In an effort to better understand these issues and concerns a team of state…

  18. Technical Education and Economic Growth

    Indian Academy of Sciences (India)

    First page Back Continue Last page Graphics. Technical Education and Economic Growth. Technical Education and Economic Growth. Review of the Present Status. Expanding no.s and impairment of quality; Faculty shortage; Grim situation at Masters and PhD levels; Regional imbalance; Absence of International flavour ...

  19. COMPASS Accelerator Design Technical Overview

    Energy Technology Data Exchange (ETDEWEB)

    Nanni, Emilio; Dolgashev, Valery; Tantawi, Sami; Neilson, Jeff; /SLAC

    2016-03-14

    This report is a survey of technical options for generating a MeV-class accelerator for space based science applications. The survey was performed focusing on the primary technical requirements of the accelerator in the context of a satellite environment with its unique challenges of limited electrical power (PE), thermal isolation, dimensions, payload requirement and electrical isolation.

  20. Radon-technical design methods based on radon classification of the soil

    International Nuclear Information System (INIS)

    Kettunen, A.V.

    1993-01-01

    Radon-technical classification of the foundation soil divides the foundation soil into four classes: negligible, normal, high and very high. Separate radon-technical designing methods and radon-technical solutions have been developed for each class. On regions of negligible class, no specific radon-technical designing methods are needed. On regions of normal radon class, there is no need for actual radon-technical designing based on calculations, whereas existing radon-technical solutions can be used. On regions of high and very high radon class, a separate radon-technical designing should be performed in each case, where radon-technical solutions are designed so that expected value for indoor radon content is lower than the maximum allowable radon content. (orig.). (3 refs., 2 figs., 2 tabs.)

  1. Technical planning activity: Final report

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    In April 1985, the US Department of Energy's (DOE's) Office of Fusion Energy commissioned the Technical Planning Activity (TPA). The purpose of this activity was to develop a technical planning methodology and prepare technical plans in support of the strategic and policy framework of the Magnetic Fusion Program Plan issued by DOE in February 1985. Although this report represents the views of only the US magnetic fusion community, it is international in scope in the sense that the technical plans contained herein describe the full scope of the tasks that are prerequisites for the commercialization of fusion energy. The TPA has developed a well-structured methodology that includes detailed definitions of technical issues, definitions of program areas and elements, statements of research and development objectives, identification of key decision points and milestones, and descriptions of facility requirements.

  2. Technical planning activity: Final report

    International Nuclear Information System (INIS)

    1987-01-01

    In April 1985, the US Department of Energy's (DOE's) Office of Fusion Energy commissioned the Technical Planning Activity (TPA). The purpose of this activity was to develop a technical planning methodology and prepare technical plans in support of the strategic and policy framework of the Magnetic Fusion Program Plan issued by DOE in February 1985. Although this report represents the views of only the US magnetic fusion community, it is international in scope in the sense that the technical plans contained herein describe the full scope of the tasks that are prerequisites for the commercialization of fusion energy. The TPA has developed a well-structured methodology that includes detailed definitions of technical issues, definitions of program areas and elements, statements of research and development objectives, identification of key decision points and milestones, and descriptions of facility requirements

  3. [Evaluation of technical skills in surgical training].

    Science.gov (United States)

    Kasparian, Andres C; Martinez, A C; JoverClos, R J; Chércoles, R A

    2014-01-01

    technical skills acquisition is considered to be of paramount importance in surgical training. Yet, formal assessment of technical skills is the weakest and less developed area. Currently available resources to evaluate technical skills are largely subjective, and lack of validity and reliability. Direct observation, one of the most frequently used methods, is largely biased by interpersonal subjectivity and personality traits. We propose the creation and use of a new procedure-specific tool for objective assessment of technical skills in surgery to evaluate validity and reliability. laparoscopic cholecystectomy and Lichstenstein's inguinal hernia repair were the chosen procedures. Three groups of comparison were defined according to surgical expertise: initial, intermediate, and experts. Surgeries were videorecorded in real time without identification of the patient or the surgeon. Tapes without any posterior edition were assigned to two expert surgeons in a blind and randomized sequence. A newly proposed procedure-specific rating scale was used for evaluation, as well as Reznick's OSATS global scale. Kruskal-Wallis non-parametric test was used to assess validity. p 0.8 granted reliability. from April 2010 to December 2012 36 laparoscopic cholecystectomies and 31 inguinal hernia repairs were recorded. Significant difference was found among groups of comparison for every item (ptechnical skills in surgery is feasible and useful. The tool we proposed showed construct validity and reliability. Video recording of surgical procedures grants durability over time to an ephemeral phenomenon. The objectivity is based on the explicit statements and quantification of every step to be evaluated, and the blind randomization and anonymous treatment of the sample. Sharing the same quality criteria between evaluators is of paramount importance to reach satisfactory results. The process of evaluation always implies a shortened view of the reality.

  4. AIMES Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Katz, Daniel S [Univ. of Illinois, Urbana-Champaign, IL (United States). National Center for Supercomputing Applications (NCSA); Jha, Shantenu [Rutgers Univ., New Brunswick, NJ (United States); Weissman, Jon [Univ. of Minnesota, Minneapolis, MN (United States); Turilli, Matteo [Rutgers Univ., New Brunswick, NJ (United States)

    2017-01-31

    This is the final technical report for the AIMES project. Many important advances in science and engineering are due to large-scale distributed computing. Notwithstanding this reliance, we are still learning how to design and deploy large-scale production Distributed Computing Infrastructures (DCI). This is evidenced by missing design principles for DCI, and an absence of generally acceptable and usable distributed computing abstractions. The AIMES project was conceived against this backdrop, following on the heels of a comprehensive survey of scientific distributed applications. AIMES laid the foundations to address the tripartite challenge of dynamic resource management, integrating information, and portable and interoperable distributed applications. Four abstractions were defined and implemented: skeleton, resource bundle, pilot, and execution strategy. The four abstractions were implemented into software modules and then aggregated into the AIMES middleware. This middleware successfully integrates information across the application layer (skeletons) and resource layer (Bundles), derives a suitable execution strategy for the given skeleton and enacts its execution by means of pilots on one or more resources, depending on the application requirements, and resource availabilities and capabilities.

  5. GEM Technical Design Report

    International Nuclear Information System (INIS)

    1993-01-01

    The GEM collaboration was formed in June 1991 to develop a major detector for the SSC. The primary physics objectives of GEM are those central to the motivation for the SSC, to study high p T physics - exemplified by the search for Higgs bosons - and to search for new physics beyond the standard model. The authors present in this Technical Design Report (TDR) a detector with broad capabilities for the discovery and subsequent study of electroweak symmetry breaking, the origin of mass and flavor, and other physics requiring precise measurements of gammas, electrons, and muons - hence the name, GEM. In addition, as a design goal, they have taken care to provide the robustness needed to do the physics that requires high luminosity. Finally, good coverage and hermeticity allow the detection of missing transverse energy, E T . The GEM design emphasizes clean identification and high resolution measurement of the primary physics signatures for high p T physics. The approach is to make precise energy measurements that maximize the sensitivity to rare narrow resonances, to detect the elementary interaction products (quarks, leptons, and photons), and to build in the features required to reduce backgrounds

  6. GEM Technical Design Report

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-31

    The GEM collaboration was formed in June 1991 to develop a major detector for the SSC. The primary physics objectives of GEM are those central to the motivation for the SSC, to study high p{sub T} physics - exemplified by the search for Higgs bosons - and to search for new physics beyond the standard model. The authors present in this Technical Design Report (TDR) a detector with broad capabilities for the discovery and subsequent study of electroweak symmetry breaking, the origin of mass and flavor, and other physics requiring precise measurements of gammas, electrons, and muons - hence the name, GEM. In addition, as a design goal, they have taken care to provide the robustness needed to do the physics that requires high luminosity. Finally, good coverage and hermeticity allow the detection of missing transverse energy, E{sub T}. The GEM design emphasizes clean identification and high resolution measurement of the primary physics signatures for high p{sub T} physics. The approach is to make precise energy measurements that maximize the sensitivity to rare narrow resonances, to detect the elementary interaction products (quarks, leptons, and photons), and to build in the features required to reduce backgrounds.

  7. Technical training - Places available

    CERN Multimedia

    Davide Vitè

    2006-01-01

    Places available as of 16.5.2006 (May-November course sessions) Technical Training: Places available The number of places available may vary. Please check our Web site to find out the current availability. Places are available on the following courses: Title Hours Date Language ACROBAT 7.0 : Utilisation de fichiers PDF 8 8.05.06 F WORD 2003 - niveau 2 : ECDL 16 22-23.05.06 23-24.05.06 F Comprehensive VHDL for FPGA Design 40 29.05-2.06.06 E C++ Programming Part 2 - Advanced C++ and its Traps and Pitfalls 32 30.05-2.06.06 E ACROBAT 7.0 : Utilisation de fichiers PDF 24 7-9.06.06 E AutoCAD Mechanical 2006 16 13-14.06.06 F CERN EDMS for Local Administrators 16 13-14.06.06 E LabVIEW Base 2 32 27.06-5.07.06 F C++ Programming Part 3 - Templates and the STL (Standard Template Library) 16 27-28.06.06 E C++ Programming Part 4 - Exceptions 8 29.06.06 E FrontPage 2003 - niveau 1 16 29-...

  8. Technical Training: Places available

    CERN Multimedia

    Monique Duval

    2005-01-01

    The number of places available may vary. Please check our Web site to find out the current availability. Places are available on the following courses: PowerPoint 2003 (F) : 25.4.2005 (1 jour) WORD 2003 - niveau 1 : 2 & 3.5.2005 (2 jours) FrontPage 2003 - niveau 1 : 9 & 10.5.2005 (2 jours) ANSYS Workbench (F) : 9 - 12.5.2005 (4 jours) ELEC-2005 - Summer Term: System electronics for physics - Issues : 10, 12, 17, 19, 24, 26 & 31.5.2005 (7 x 2h lectures) AutoCAD 2005 - niveau 1 : 11, 12, 18, 19.5.2005 (4 jours) ACCESS 2003 - Level 1: ECDL M5 : 11 & 12.5.2005 (2 days) La technique du vide : 12 & 13.5.2005 (2 jours) Finite State Machines in the JCOP Framework: 24 - 26.5.2005 (3 days) The Joint PVSS JCOP Framework: 30.5 - 3.6.2005 (5 days) LabVIEW Migration 6 to 7: 14.6.2005 (1 day) Introduction to ANSYS: 21 - 24.6.2005 (4 days) ENSEIGNEMENT TECHNIQUE TECHNICAL TRAINING Monique Duval 74924 tech...

  9. VLLEEM-2 technical workshop

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    In order to overcome the limits of the energy-environment models, and to benefit at the same time of their past experiences, the VLEEM project proposes a genuine approach and innovative modelling tools to assess the energy-environment systems over the very long term, which are based on the strengths of existing long term energy models, but focussed on two major objectives: to describe normative futures which fit with a set of overall constraints, like the stabilisation of the concentration of green-house gases in the atmosphere, or the stabilisation of the overall inventory of plutonium and minor actinides, etc...; to describe and formalize the association of causalities necessary to bring the system from the present situation to the targeted future, through a '' back-casting '' approach. This first technical workshop presents the state of the art of the different Work Programmes. WP1:Enhancement of the Conceptual framework. WP2: Data base on conventional demand/supply technologies. WP3: Complement and up-date technology monographs. WP4: Formalization and computing of final VLEEM submodels. WP5: Case study 2030, 2050, 2100. (A.L.B.)

  10. Technical Training: Places available

    CERN Multimedia

    Monique Duval

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an 'application for training' form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. The number of places available may vary. Please check our Web site to find out the current availability. Places are available in the following courses: AutoCAD 2002 - niveau 1 : 13, 14, 23, 24.09.2004 (4 jours) Introduction to the CERN EDMS : 22.6.2004 (1 day) The CERN EDMS for local administrators : 23 & 24.6.2004 (2 days) MAGNE-04 : Magnétisme pour l'électrotechnique : 6 - 8.7.2004 (3 jours) Introduction au VHDL et utilisation du simulateur NCVHDL de CADENCE : 7 & 8.9.2004 (2 jours) ENSEIGNEMENT TECHNIQUE TECHNICAL TRAINING...

  11. Technical approach document

    International Nuclear Information System (INIS)

    1988-04-01

    This document describes the general technical approaches and design criteria adopted by the US Department of Energy (DOE) in order to implement Remedial Action Plans (RAPs) and final designs that comply with EPS standards. This document is a revision to the original document. Major revisions were made to the sections in riprap selection and sizing, and ground-water; only minor revisions were made to the remainder of the document. The US Nuclear Regulatory Commission (NRC) has prepared a Standard Review Plan (NRC-SRP) which describes factors to be considered by the NRC in approving the RAP. Sections 3.0, 4.0, 5.0, and 7.0 of this document are arranged under the same headings as those used in the NRC-SRP. This approach is adopted in order to facilitate joint use of the documents. Section 2.0 (not included in the NRC-SRP) discusses design considerations; Section 3.0 describes surface-water hydrology and erosion control; Section 4.0 describes geotechnical aspects of pile design; Section 5.0 discusses the Alternate Site Selection Process; Section 6.0 deals with radiological issues (in particular, the design of the radon barrier); Section 7.0 discusses protection of groundwater resources; and Section 8.0 discusses site design criteria for the RAC

  12. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Stoessel, Chris

    2013-11-13

    This project developed a new high-performance R-10/high SHGC window design, reviewed market positioning and evaluated manufacturing solutions required for broad market adoption. The project objectives were accomplished by: identifying viable technical solutions based on modeling of modern and potential coating stacks and IGU designs; development of new coating material sets for HM thin film stacks, as well as improved HM IGU designs to accept multiple layers of HM films; matching promising new coating designs with new HM IGU designs to demonstrate performance gains; and, in cooperation with a window manufacturer, assess the potential for high-volume manufacturing and cost efficiency of a HM-based R-10 window with improved solar heat gain characteristics. A broad view of available materials and design options was applied to achieve the desired improvements. Gated engineering methodologies were employed to guide the development process from concept generation to a window demonstration. The project determined that a slightly de-rated window performance allows formulation of a path to achieve the desired cost reductions to support end consumer adoption.

  13. Waste Management Technical Manual

    Energy Technology Data Exchange (ETDEWEB)

    Buckingham, J.S. [ed.

    1967-08-31

    This Manual has been prepared to provide a documented compendium of the technical bases and general physical features of Isochem Incorporated`s Waste Management Program. The manual is intended to be used as a means of training and as a reference handbook for use by personnel responsible for executing the Waste Management Program. The material in this manual was assembled by members of Isochem`s Chemical Processing Division, Battelle Northwest Laboratory, and Hanford Engineering Services between September 1965 and March 1967. The manual is divided into the following parts: Introduction, contains a summary of the overall Waste Management Program. It is written to provide the reader with a synoptic view and as an aid in understanding the subsequent parts; Feed Material, contains detailed discussion of the type and sources of feed material used in the Waste Management Program, including a chapter on nuclear reactions and the formation of fission products; Waste Fractionization Plant Processing, contains detailed discussions of the processes used in the Waste Fractionization Plant with supporting data and documentation of the technology employed; Waste Fractionization Plant Product and Waste Effluent Handling, contains detailed discussions of the methods of handling the product and waste material generated by the Waste Fractionization Plant; Plant and Equipment, describes the layout of the Waste Management facilities, arrangement of equipment, and individual equipment pieces; Process Control, describes the instruments and analytical methods used for process control; and Safety describes process hazards and the methods used to safeguard against them.

  14. Technical Training Seminar

    CERN Multimedia

    2003-01-01

    Thursday 4 September From 14:00 to 17:00 - Training Centre Auditorium bldg. 593, room 11 The Summit Design VisualElite 4.0 Release Jean Marie St Paul / SUMMIT DESIGN, Europe, Technical Manager Michel Delcroix / SUMMIT DESIGN, Southern Europe, Sales F-95015 CERGY PONTOISE, France Summit Design is an important EDA digital hardware design tool supplier, and the industry leader in the emerging Electronic System Level design domain. Its VisualElite program has been used at CERN for several years. This seminar will include the highlights of the program's latest release. It will be illustrated how Summit Design products can provide a high-level C/C++ and SystemC functional modelling design and verification environment, enabling engineers to analyse system concepts before the implementation stage. The seminar will show how mixed SystemC and HDL simulation can be done, along with solutions for hardware/software development. • HDL new features: Connectivity Table Editor. Xemacs full integration. New NCsi...

  15. Technical Training Seminar

    CERN Multimedia

    2003-01-01

    Thursday 4 September From 14:00 to 17:00 - Training Centre Auditorium bldg. 593, room 11 The Summit Design VisualElite 4.0 Release Jean Marie St Paul / SUMMIT DESIGN, Europe, Technical Manager Michel Delcroix / SUMMIT DESIGN, Southern Europe, Sales F-95015 CERGY PONTOISE, France Summit Design is an important EDA digital hardware design tool supplier, and the industry leader in the emerging Electronic System Level design domain. Its VisualElite program has been used at CERN for several years. This seminar will include the highlights of the program's latest release. It will be illustrated how Summit Design products can provide a high-level C/C++ and SystemC functional modelling design and verification environment, enabling engineers to analyse system concepts before the implementation stage. The seminar will show how mixed SystemC and HDL simulation can be done, along with solutions for hardware/software development. • HDL new features: Connectivity Table Editor. Xemacs full integration. New NCsim ...

  16. Bibliography - Technical Reports, Special Reports, and Technical Notes, FY 1981.

    Science.gov (United States)

    1982-03-01

    AD-A113 798 NAVY PERSONNEL RESEARCH AND DEVELOPMENT CENTER SAN D--ETC F/6 5/9 BIBLIOGRAPHY - TECHNICAL REPORTS. SPECIAL REPORTS. AND TECHNICA-ETC( U ...TH4IS PAGE ( MOM , Dole gnto,.d) FOREWORD This report lists all technical reports, special reports, and technical notes that were published by this Center...TR 81-16. July 1981. J. I. Borack and K. W. Gay . (AD-A102 910) A new computerized management system, the structured accession planning (STRAP) system

  17. CTBT technical issues handbook

    International Nuclear Information System (INIS)

    Zucca, J.J.

    1994-05-01

    The purpose of this handbook is to give the nonspecialist in nuclear explosion physics and nuclear test monitoring an introduction to the topic as it pertains to a Comprehensive Test Ban Treaty (CTBT). The authors have tried to make the handbook visually oriented, with figures paired to short discussions. As such, the handbook may be read straight through or in sections. The handbook covers four main areas and ends with a glossary, which includes both scientific terms and acronyms likely to be encountered during CTBT negotiations. The following topics are covered: (1) Physics of nuclear explosion experiments. This is a description of basic nuclear physics and elementary nuclear weapon design. Also discussed are testing practices. (2) Other nuclear experiments. This section discusses experiments that produce small amounts of nuclear energy but differ from explosion experiments discussed in the first chapter. This includes the type of activities, such as laser fusion, that would continue after a CTBT is in force. (3) Monitoring tests in various environments. This section describes the different physical environments in which a test could be conducted (underground, in the atmosphere, in space, underwater, and in the laboratory); the sources of non-nuclear events (such as earthquakes and mining operations); and the opportunities for evasion. (4) On-site inspections. A CTBT is likely to include these inspections as an element of the verification provisions, in order to resolve the nature of ambiguous events. This chapter describes some technical considerations and technologies that are likely to be useful. (5) Selecting verification measures. This chapter discusses the uncertain nature of the evidence from monitoring systems and how compliance judgments could be made, taking the uncertainties into account. It also discusses how to allocate monitoring resources, given the likelihood of testing by various countries in various environments

  18. CTBT technical issues handbook

    Energy Technology Data Exchange (ETDEWEB)

    Zucca, J.J. [ed.

    1994-05-01

    The purpose of this handbook is to give the nonspecialist in nuclear explosion physics and nuclear test monitoring an introduction to the topic as it pertains to a Comprehensive Test Ban Treaty (CTBT). The authors have tried to make the handbook visually oriented, with figures paired to short discussions. As such, the handbook may be read straight through or in sections. The handbook covers four main areas and ends with a glossary, which includes both scientific terms and acronyms likely to be encountered during CTBT negotiations. The following topics are covered: (1) Physics of nuclear explosion experiments. This is a description of basic nuclear physics and elementary nuclear weapon design. Also discussed are testing practices. (2) Other nuclear experiments. This section discusses experiments that produce small amounts of nuclear energy but differ from explosion experiments discussed in the first chapter. This includes the type of activities, such as laser fusion, that would continue after a CTBT is in force. (3) Monitoring tests in various environments. This section describes the different physical environments in which a test could be conducted (underground, in the atmosphere, in space, underwater, and in the laboratory); the sources of non-nuclear events (such as earthquakes and mining operations); and the opportunities for evasion. (4) On-site inspections. A CTBT is likely to include these inspections as an element of the verification provisions, in order to resolve the nature of ambiguous events. This chapter describes some technical considerations and technologies that are likely to be useful. (5) Selecting verification measures. This chapter discusses the uncertain nature of the evidence from monitoring systems and how compliance judgments could be made, taking the uncertainties into account. It also discusses how to allocate monitoring resources, given the likelihood of testing by various countries in various environments.

  19. Tore Supra: technical description

    International Nuclear Information System (INIS)

    1985-08-01

    This report is aimed, after a brief recall of physics and technologic perspectives of Tore Supra, at giving a detailed description of the basic machine; details of each component are defined. Volume 1 is specifically concerned with the general aspects of Tore Supra and the toroidal field system [fr

  20. Engineering Technical Review Planning Briefing

    Science.gov (United States)

    Gardner, Terrie

    2012-01-01

    The general topics covered in the engineering technical planning briefing are 1) overviews of NASA, Marshall Space Flight Center (MSFC), and Engineering, 2) the NASA Systems Engineering(SE) Engine and its implementation , 3) the NASA Project Life Cycle, 4) MSFC Technical Management Branch Services in relation to the SE Engine and the Project Life Cycle , 5) Technical Reviews, 6) NASA Human Factor Design Guidance , and 7) the MSFC Human Factors Team. The engineering technical review portion of the presentation is the primary focus of the overall presentation and will address the definition of a design review, execution guidance, the essential stages of a technical review, and the overall review planning life cycle. Examples of a technical review plan content, review approaches, review schedules, and the review process will be provided and discussed. The human factors portion of the presentation will focus on the NASA guidance for human factors. Human factors definition, categories, design guidance, and human factor specialist roles will be addressed. In addition, the NASA Systems Engineering Engine description, definition, and application will be reviewed as background leading into the NASA Project Life Cycle Overview and technical review planning discussion.

  1. Field convergence between technical writers and technical translators

    DEFF Research Database (Denmark)

    Gnecchi, M.; Maylath, B.; Mousten, Birthe

    2011-01-01

    As translation of technical documents continues to grow rapidly and translation becomes more automated, the roles of professional communicators and translators appear to be converging. This paper updates preliminary findings first presented at the 2008 International Professional Communication...

  2. Bid specifications and bid evaluations

    International Nuclear Information System (INIS)

    Zijl, N.A. van

    1977-01-01

    Bid specifications are in view of the size of these projects important and comprehensive documents. The basic content and set up of the specifications are discussed such as: 1) Bid invitation letter, 2) instruction to bidders, 3) draft contract (terms and conditions), 4) technical specifications, 5) side data and information. - The evaluations of bids for nuclear power stations is due to the complexity of such bids a difficult undertaking. Evaluation methods and approaches which can be applied for such bid evaluations are discussed as well as the preparations which are required for carrying out such evaluations. (orig.) [de

  3. LHC Availability 2017: Technical Stop 1 to Technical Stop 2

    CERN Document Server

    Todd, Benjamin; Apollonio, Andrea; Walsh, David John; CERN. Geneva. ATS Department

    2017-01-01

    This document summarises the LHC machine availability for the period of Technical Stop 1 (TS1) to Technical Stop 2 (TS2) in 2017. This period was dedicated to proton physics with a bunch spacing of 25ns. This note has been produced and ratified by the Availability Working Group which has complied fault information for the period in question using the Accelerator Fault Tracker.

  4. 77 FR 58421 - Model Safety Evaluation for Plant-Specific Adoption of Technical Specifications Task Force...

    Science.gov (United States)

    2012-09-20

    ... Item Improvement Process AGENCY: Nuclear Regulatory Commission. ACTION: Notice of availability. SUMMARY... Agencywide Documents Access and Management System (ADAMS): You may access publicly available documents online... currently require operating the ventilation system for at least 10 continuous hours with the heaters...

  5. Technical/economical analysis of bioenergy systems

    International Nuclear Information System (INIS)

    Solantausta, Y.

    1998-01-01

    The objectives of the IEA Bioenergy Technoeconomic Analysis Activity are: (1) To promote development of thermochemical biomass conversion methods by carrying out selected site specific feasibility studies in participating countries. Both agricultural and woody biomasses will be converted either into electricity or boiler fuels; (2) To compare advanced technologies to commercial alternatives based on technoeconomic basis to establish future development needs, and (3) To facilitate information exchange between participants on relevant basic process issues. Five countries (Finland, Canada, USA, Norway, Austria) are participating to the Activity. Initially two feasibility studies are planned for each country. Each study has three common elements: site specific, technical, and economic data. The site specific cases are described below in short. Products in the cases are electricity, heat and fuel oil. Total of two cases per country are planned. (orig.)

  6. Lessons Learned and Technical Standards: A Logical Marriage

    Science.gov (United States)

    Gill, Paul; Vaughan, William W.; Garcia, Danny; Gill, Maninderpal S. (Technical Monitor)

    2001-01-01

    A comprehensive database of lessons learned that corresponds with relevant technical standards would be a boon to technical personnel and standards developers. The authors discuss the emergence of one such database within NASA, and show how and why the incorporation of lessons learned into technical standards databases can be an indispensable tool for government and industry. Passed down from parent to child, teacher to pupil, and from senior to junior employees, lessons learned have been the basis for our accomplishments throughout the ages. Government and industry, too, have long recognized the need to systematically document And utilize the knowledge gained from past experiences in order to avoid the repetition of failures and mishaps. The use of lessons learned is a principle component of any organizational culture committed to continuous improvement. They have formed the foundation for discoveries, inventions, improvements, textbooks, and technical standards. Technical standards are a very logical way to communicate these lessons. Using the time-honored tradition of passing on lessons learned while utilizing the newest in information technology, the National Aeronautics and Space Administration (NASA) has launched an intensive effort to link lessons learned with specific technical standards through various Internet databases. This article will discuss the importance of lessons learned to engineers, the difficulty in finding relevant lessons learned while engaged in an engineering project, and the new NASA project that can help alleviate this difficulty. The article will conclude with recommendations for more expanded cross-sectoral uses of lessons learned with reference to technical standards.

  7. Innovative methods of popularizing technical education

    Science.gov (United States)

    Shkitsa, L. Y.; Panchuk, V. G.; Kornuta, V. A.

    2017-05-01

    There have been analyzed reasons of the loss of technical education’s popularity. Also, the analysis of known educational and production methods, oriented at the innovative model of development of society, was performed. It is stated that the acquisition of 21st century’s skills as a result of competition of technical education are natural for the DIY ideology, which was realized in the institutions like Fab Lab. The new educational strategy, based on project-based learning, is proposed to be implemented as a special laboratory with equipment, which would be a center of innovative development for students at the Technical University. Moreover, the list of projects planned for implementation, that includes not only projects, specific to a particular university, but also projects, demanded by society as a whole, is specified. It is worth to implement trendy projects in the laboratory, such as toy-like, ecological projects; projects of the energy dependence decrease or the energy efficiency increase, modern digital or innovative projects etc. The student should gain knowledge, skills and, possibly, equipment that are available for immediate usage on the labor market or for the realization of his own projects or the community’s projects in everyday life after the realization of the particular project at the laboratory

  8. The environment and directed technical change: comment

    International Nuclear Information System (INIS)

    Hourcade, Jean-Charles; Pottier, Antonin; Espagne, Etienne

    2011-11-01

    This paper discusses the growth model with environmental constraints recently presented in (Acemoglu et al., 2011) which focuses on the redirection of technical change by climate policies with research subsidies and a carbon tax. First, Acemoglu et al.'s model and chosen parameters yield numerical results that do not support the conclusion that ambitious climate policies can be conducted 'without sacrificing (much or any) long-run growth'. Second, they select unrealistic key parameters for carbon sinks and elasticity of substitution. We find that more realistic parameters lead to very different results. Third, the model leads to an unrealistic conclusion when used to analyse endogenous growth, suggesting specification problems. (authors)

  9. Marine renewable energies. Stakes and technical solutions

    International Nuclear Information System (INIS)

    Lacroix, Olivier; Macadre, Laura-Mae

    2012-05-01

    Marine renewable energies are able to supply carbon free energy from various ocean resources (tides, waves, currents, winds, salinity and temperature gradients). This sector, currently at an early stage of deployment, has good prospects of development in the coming years. ENEA releases a report on marine renewable energies giving a transversal vision of the associated stakes and prospects of development. Technical and economic characteristics, maturity level and specificities of each marine energy are analyzed. French and European sources of funding, regulatory framework and potential environmental and social impacts are also reported

  10. Multidirectional analysis of technical efficiency for pig production systems

    DEFF Research Database (Denmark)

    Labajavo, Katarina; Hansson, Helena; Asmild, Mette

    2016-01-01

    Declining profitability and ongoing structural changes in the pig sector require thorough efficiency analysis of individual production factors. In this study we calculated technical efficiency indices for each input and output using multidirectional efficiency analysis and examined the relationship...... between ‘farm-specific characteristics’ and input and output technical efficiencies by production type (piglet, growing-finishing, finish-to-farrow). The results indicated that advisory services and farm location were not significantly correlated with technical efficiency. Similar results were obtained...... for ‘housing practices’, with the exception of the latest technology such as heated floors in relation to input labour technical efficiency for growing-finishing and finish-to-farrow productions. Use of written instructions for feeding for growing-finishing and finish-to-farrow production and written...

  11. Technical Training: CLEAN-2002: Working in a Cleanroom

    CERN Multimedia

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch CERN Technical Training Programme: Learning for the LHC! CLEAN-2002 is a free of charge, half-day seminar in the context of Technical Training for the LHC. The course is designed for personnel working or managing activities in an assembly cleanroom, for example physicists, engineers and technicians working at or visiting the laboratory. CLEAN-2002 is aimed at raising awareness about good working practices in a cleanroom, and at providing practical examples, analysis tools, and documentation. Specific ...

  12. Dose measurements with a HPGe detector - a technical manual

    International Nuclear Information System (INIS)

    Lidstroem, K.; Nordenfors, C.; Aagren, G.

    2000-06-01

    This paper is a technical manual for estimations of dose based on a gamma spectrum. The method used is based on the Monte Carlo code EGS4. Since dose estimations from spectra are specific for each detector, this work is performed on two mobile HPGe detectors at FOA NBC Defence in Umeaa. This technical manual describes the method used in three steps: Part 1 explains how to construct a model of the detector geometry and the specific material for a new detector. Part 2 describes the underlying work of Monte Carlo simulations of a detector given geometry and material. Part 3 describes dose estimations from a gamma spectrum

  13. New functions for technical supervision

    Energy Technology Data Exchange (ETDEWEB)

    Herkommer, E.; Kressel, E.; Wollenschlaeger, M.

    1988-07-01

    The discussion concerns the foundation of a new Institution namely an 'Environmental Technical Inspection Board', in order to implement faster the technical and scientific findings in conservation and to control more efficiently the adherence to safety regulations. The article presents a review of the legal regulations in conservation, describes their constitutional status, tasks and legal status of the experts in the technical control societies, tasks and legal position of an environmental technical inspection board as well as its financing. It is stated that the execution deficit in pollution control can be decreased by better participation of experts and permanent control of all potentially dangerous installations. In order to realize this concept, the extension of already available structures presents itself, especially the consultation of officially approved experts, without a new administrative machinery having to be created. (orig./HSCH).

  14. Polar source analysis : technical memorandum

    Science.gov (United States)

    2017-09-29

    The following technical memorandum describes the development, testing and analysis of various polar source data sets. The memorandum also includes recommendation for potential inclusion in future releases of AEDT. This memorandum is the final deliver...

  15. NASA Technical Reports Server (NTRS)

    Data.gov (United States)

    National Aeronautics and Space Administration — The NTRS is a valuable resource for researchers, students, educators, and the public to access NASA's current and historical technical literature and engineering...

  16. Hydrogen Storage Technical Team Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-06-01

    The mission of the Hydrogen Storage Technical Team is to accelerate research and innovation that will lead to commercially viable hydrogen-storage technologies that meet the U.S. DRIVE Partnership goals.

  17. S-Chip Technical Assistance

    Data.gov (United States)

    U.S. Department of Health & Human Services — The page will provide access to reports and other published products designed to assist states with complicated S-Chip technical issues. The reports and products...

  18. Fuel Cell Technical Team Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-06-01

    The Fuel Cell Technical Team promotes the development of a fuel cell power system for an automotive powertrain that meets the U.S. DRIVE Partnership (United States Driving Research and Innovation for Vehicle efficiency and Energy sustainability) goals.

  19. Technical management courses (before July)

    CERN Multimedia

    2015-01-01

    Please find below the courses in the field of technical management scheduled before July and which have places available.       For more details about a course and to register, please go to the Training Catalogue. If you need a course which is not in the catalogue, please contact your supervisor, your Departmental Training Officer or HR-LD at Technical.Management.Training@cern.ch.

  20. Technical framework for groundwater restoration

    International Nuclear Information System (INIS)

    1991-04-01

    This document provides the technical framework for groundwater restoration under Phase II of the Uranium Mill Tailings Remedial Action (UMTRA) Project. A preliminary management plan for Phase II has been set forth in a companion document titled ''Preplanning Guidance Document for Groundwater Restoration''. General principles of site characterization for groundwater restoration, restoration methods, and treatment are discussed in this document to provide an overview of standard technical approaches to groundwater restoration